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| number = ML16089A389
| number = ML16089A389
| issue date = 03/22/2016
| issue date = 03/22/2016
| title = Surry, 2014-301 Section 10
| title = 301 Section 10
| author name =  
| author name =  
| author affiliation = NRC/RGN-II/DNMS
| author affiliation = NRC/RGN-II/DNMS
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=Text=
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{{#Wiki_filter:Appendix D                                      Scenario Outline                                    Form ES-D-1 NRC EXAM - SCENARIO #1 Facility: Surry Power Station              Scenario No.: 1                        Op-Test No.: 2014-001 Examiners: ____________________________ Operators:                        _____________________________
Initial Conditions: Unit 1 and 2 at 100% power; MOL.
* A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Turnover:  The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Event            Malf. Event                                        Event No.            No.      Type*                                      Description 1                RCMOV_5      N BOP      Test Cycle Pressurizer PORV, Block Valve breaker will trip when re-35_BKR,      N SRO      opened Open        TS SRO 2                RC4903,      I RO        PRZR Level Transmitter Fails Low, requiring IAs of AP-53.00 to control
                  -.2 DEG                  CH flow.
TS SRO 3                FW1803,      I BOP      Feed Flow Channel fails high requiring manual FRV control, IAs of AP-
                  +1 DEG                  53.00 TS SRO 4                SD0201      C BOP      Loss of High Pressure Drain, AP-18.00 5                            R RO R SRO      Ramp to 75% power IAW AP-23.00 N - BOP C RO 6                RC2402      C SRO      Steam Generator Tube Leak B SG at approximately 74 gpm. AP-16.00, E0.
Auto Actions of Air Ejector Hi Rad do not function, BOP manually aligns.
AS02,        C - BOP    A/E RM Annunciator Response Procedure.
AS05 RC5601                  Reactor Coolant Pumps trip on electrical power swap to Reserve Station RC5602                  Service Transformers (30 seconds after reactor trip).
RC5603 7                RC2402,      M - All    SGTL B SG escalates to Design Basis rate (800 gpm) in ES-0.1. AP-79%, 710                16.00, Manual SI, E-0, E-3.
gpm, 60 sec ramp 8                PCV455C      M - All    PZR PORV 1-RC-1455C will not open when switch placed in open - Go
_OPEN,                  to ECA-3.3 OFF
 
Appendix D                                  Scenario Outline                                    Form ES-D-1 NRC EXAM - SCENARIO #1 9          SI2409      C BOP          BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-SI2505                    100A/B not close.
*      (N)ormal,  (R)eactivity, (I)nstrument,  (C)omponent,    (M)ajor Event 1: PT-18.6 I, PZR Block Valve Stroke Test. (N- BOP/SRO)
The Team will pre-brief this evolution prior to entering the Simulator. Upon entry of the Team to the Simulator, the Scenario brief will be given, Questions answered, and the Team allowed ~ 5 minutes to become acclimated to the Simulator Environment.
When the BOP closes 1-RC-MOV-1535, 1-RC-PCV-1456 block valve, and attempts to re-open 1-RC-MOV-1535, a series of triggers actuate to trip the power supply breaker to 1-RC-MOV 1535.
Verifiable Action(s):
: 1) BOP will close 1-RC-MOV-1535 and time the stroke.
: 2) RO/BOP will place the 1-RC-MOV-1456 PORV control switch in the close position following Tech Spec review.
Technical Specifications:
The SRO will review Tech Specs (3.1.A.6.d) and determine a one (1) hour clock exists to place 1-RC-PCV-1456 in manual (switch to close); and a 72 hour clock to return the block valve to an OPERABLE status, or be in HSD in 6 hours and RCS temperature <350&deg;F within the next 6 hours.
This Event sets up entry into ECA-3.3, SGTR without Pressure Control; Major Event later in the Scenario.
Event 2: PRZR level Upper Channel Fails Low (-.2 DEG) PRZR level on selected Upper Channel fails to ~34%. (I - RO, TS - SRO). ARP 1C-D8, PRZR LO Level.
The RO will diagnose the failure based on CH to Regen HX Hi/Low flow alarm (Annunciator 1D-E5) or identification of CH flow increasing and PZR level Channel III decreasing.
Verifiable Actions(s):
: 1) The RO will place CH flow in Manual and control PRZR level at setpoint IAW AP-53.00, Loss of Vital Instrumentation/Controls.
: 2) BOP will select an operable channel on the pressurizer level recorder.
: 3) The RO will defeat the failed channel IAW AP-53.00, and return CH flow to automatic when normal PRZR level restored.
Technical Specifications:
: 1) The SRO will Review Tech Specs and determine a 72 hour clock to place the Failed Channel in trip (TS 3.7, Table 3.7-1, item 9 (Pressurizer High Water Level), Operator Action 7. With the number of OPERABLE Channels less than the Total number of channels; place the failed channel in trip in 72 hours, allowable to bypass the channel for up to 12 hours for surveillance, if requirements not met reduce power to less than P-7 (10%) within the next 6 hours.
 
Appendix D                                Scenario Outline                            Form ES-D-1 NRC EXAM - SCENARIO #1
: 2) TS-Table 3.7-6, item 14, Pressurizer Level, 2 Channels required, condition met.
(Referred by check of CEP 99-0029, RG 1.97).
TRM Actions:
: 1) TRM section 3.3.2, Table 3.3.2-1, Pressurizer Level Channel 1-RC-LI-1461.
Condition A applies, Implement a Fire Watch in cable vault and tunnel and the emergency switchgear room of the affected Unit (Unit 1) IAW TRM Section 5.2 (Hourly) within 14 days and restore the failed channel in 60 days. (Usually an STA Function to identify, may be performed as a follow-up).
Reg. Guide 1.97:
: 1) CEP-99-0029, Reg. Guide 1.97 Operability/Functionality, Reportability and Alternate Indications, Attachment 1, Post Accident Monitoring Equipment, A-13 variable, 2 channels required, Condition is met. Refers to TS Table 3.7-6. (Usually an STA Function to identify - could be covered as a follow-up).
Event 3: Feed Flow Channel III, B SG fails high. (I - BOP, TS - SRO)
BOP will diagnose the failure based upon alarms and indications received and take the Immediate Actions of AP-53.00. The Team will implement AP-53.00, Loss of Vital Instrumentation/Controls and shift SGWLC input to Channel IV for B SG. The BOP will restore B SG NR level to program.
Verifiable Action(s):
: 1) BOP will place the B FRV in manual and regain control of B SG NR level.
: 2) RO will defeat the failed channel.
: 3) BOP will return the B FRV to automatic.
Technical Specifications:
Tech Spec Table 3.7-1
: 1) Item 17, Low steam generator water level with steam flow/feedwater flow mismatch, Operator Action 6.
: 2) With the number of OPERABLE Channels less than the TOTAL number of channels, operation may continue if the failed channel is placed in trip in 72 hours, the channel may be bypassed for 12 hours for surveillance, if conditions not satisfied in the time permitted, be in Hot Shutdown within 6 hours.
Technical Requirements Manual. Reg. Guide 1.97:
: 1) The TRM Section 3.3, Appendix R Instrumentation unaffected; and RG 1.97 requires one channel of Feed Flow indication per steam generator and no further actions are required are by this failure.
 
Appendix D                                  Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #1 Event #4: Loss of the HP Heater Drain Pump (1-SD-P-1A) (C - BOP)
The BOP will diagnose the failure based upon alarms and indication received. The Team will initiate AP-18.00, Loss of HP Heater Drain Pump/ Network 90 failure Verifiable Actions:
: 1) The BOP will place the tripped High Pressure Drain pump control switch in PTL.
: 2) Reduce Turbine Load as necessary to maintain reactor power less than 100% using the valve position limiter or using Turbine Manual (approximately 50 MW reduction required).
Event 5: Power Reduction to less than 75% power using AP-23.00, Rapid Load Reduction. (R - RO, R - SRO, N - BOP)
The SRO will lead a Team Brief where the reactivity plan will be discussed to reduce reactor power to less than 75% power in order to restore the Polishing Building to service. The RO and SRO will be credited with a Reactivity Manipulation and the BOP with a Normal Evolution.
Verifiable Action(s):
: 1) RO will manipulate control rods to control delta flux and/or Tave.
: 2) RO will manipulate CVCS controls to Emergency Borate.
: 3) RO will manipulate CVCS control to establish a normal boration to assist in Tave control.
: 4) BOP will manipulate Turbine Controls to establish power reduction.
Event #6: Steam Generator Tube Leak B Steam Generator. Failure of Auto actions of A/E RM. Trip of all RCPs on electrical transfer to RSSTs. (C - RO, C - BOP)
When the Evaluation Team is satisfied with the Reactivity manipulation, the event will be triggered. A SGTL of approximately 74 gpm will initiate requiring the RO to perform the actions of 1-AP-16.00 to quantify the leakrate. The A/E RM will go into High alarm due to the primary to secondary leakage; the BOP will manually align A/E discharge to containment IAW A/E RM ARP. When the RCS leakrate is identified as greater than 50 gpm, the RO will trip the reactor and perform the Immediate Actions of 1-E-0.
Verifiable Actions:
: 1) RO will isolate LD flow and place charging flow in manual to quantify leakrate.
: 2) BOP will respond to failure of auto actions on A.E RM High alarm by swapping A/E discharge to containment.
 
Appendix D                                  Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #1 Event #7: SGTR in B SG, approximately 710 gpm. (M - ALL)
When the evaluation Team is ready, a SGTR in the B SG will be implemented. The RO will re-assess RCS leakage in response to alarms and indications received. The RO will determine that RCS leakage exceeds the capacity of a single CH pump, and the Team will return to E-0 and manually initiate SI.
The SRO will perform a commensurate brief and continue with E-0. While the RO and SRO continue with E-0, the BOP will be directed to perform E-0 Attachments 1 through 3.
Verifiable Actions:
: 1) RO will increase CH flow in manual per Immediate Action Steps of 1-AP-16.00, Excessive RCS Leakage to determine if RCS leakage is greater than the capacity of a single CH pump.
: 2) RO re-perform High Level Steps of E-0, and manually Safety Inject on Step 4 of 1-E-0.
: 3) BOP will perform actions of Attachments 1 through 3 of E-0. BOP Failures in E-0 Attachments: 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not auto close, 1-VS-MOD-103A not auto close, 1-MS-TV-109 and 1-DA-TV-100A/B will not auto close (Listed as Event 9).
Critical Task:
: 1)  SPS E G: LHSI pumps will not undergo significant degradation while operating under very low flow conditions during the onset of a SBLOCA (implicit in SBLOCA analysis). Operators will secure one LHSI pump as directed by Emergency Operating Procedures to prevent pump damage while on recirculation. Secure one LHSI pump within 30 minutes of initiation of SI (KOA). NOTE: If the BOP Fails to Start 1-SI-P-1B, Critical Task becomes Not Applicable.
: 2)    WOG E-3 -- A:      Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs. Example: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs (KOA).
KOA: For the design basis tube rupture, isolate the ruptured SG from the atmosphere/Turbine building within 30 minutes. Note: The 30 minute criteria in the CT is ONLY for the design basis tube rupture.
Event #8: SGTR with Loss of Pressure control. (M - All)
The Team continues through the EOP progression E-0 to E-3.
After the Team has completed the rapid cooldown of E-3 and moves to the Depressurization steps, the Team will be presented with the inability to depressurize the RCS (No RCPs - No Spray available), 1 PZR PORV inoperable, and the last Pzr PORV not responding to placing the control switch in Open. This will require the Team to Transition to ECA-3.3, SGTR without Pressure Control.
When ECA-3.3 is entered, it is expected that the ruptured SG level will be > 73% NR leading to Team moving to Step 6, Check If SI Can Be Terminated.
 
Appendix D                              Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #1 Verifiable Actions:
: 1) RO will isolate AFW flow to the Ruptured SG.
: 2) BOP will reset SI and secure A CH pump and one of the running LHSI pumps.
(Discretionary CT - within 30 minutes).
: 3) RO will manipulate steam dump controls for rapid cooldown.
: 4) RO/BOP will block SI signals when conditions established.
: 5) RO will manipulate SI/CVCS control to terminate SI, establish CH flow, and restore letdown flow.
Classification:
Follow-up Classification question for SGTR: Alert FA-1.1.
The Scenario is terminated at Lead Evaluator discretion or at Step 11 of ECA-3.3, Check If CS Should Be Stopped (CH and LD flow have been re-established).
 
Appendix D                                        Scenario Outline                                    Form ES-D-1 NRC EXAM - SCENARIO #1 Initial Conditions: Unit 1 and 2 Operating at 100%.
Turnover: The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Pre-load malfunctions: (Trigger 30s) o SI2409 SI RELAY CI1A FAILS TO ACTUATE o SI2505 SI RELAY SI5B FAILS TO ACTUATE o AS02 DISABLE SV-TV-102 OPEN o AS05 DISABLE SV-TV-103 CLOSE o AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:
o    AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
Turnover:
Unit 1 and 2 at 100% power; MOL.
A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon dilutions followed by a manual makeup for training.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Turnover: Team will perform PT-18.6I, PZR Block Valve Stroke Test. The performance of this procedure has been analyzed based on the current plant configurations and the PRA indicates green.
Event      Malf. #s    Severity                        Instructor Notes and Required Feedback 1          RCMOV_53      Open        Test Cycle Pressurizer PORV, Block Valve breaker will trip when re-opened.
5_BKR, 2          RC4903,      -.2 DEG      PRZR Level Transmitter Fails Low, requiring IAs of AP-53.00 to control CH flow. 0-AP-53.00.
3          FW1803,      +1 DEG      Feed Flow Channel fails high requiring manual FRV control, IAs of AP-53.00 4          SD0201        True        Loss of High Pressure Drain, AP-18.00 5          N/A          N/A Ramp to 75% power IAW AP-23.00
 
Appendix D                                Scenario Outline                                  Form ES-D-1 NRC EXAM - SCENARIO #1 6      RC2402      8%        Steam Generator Tube Leak B SG at approximately 74 gpm. AP-16.00, E0.
AS02,                Auto Actions of Air Ejector Rad Mon on High alarm do not function, BOP manually AS05                  aligns. A/E RM Annunciator Response Procedure.
RC5601 RC5602                Reactor Coolant Pumps trip on electrical power swap to Reserve Station Service RC5603      TRUE      Transformers (30 seconds after reactor trip).
: 7. RC2402      88%, 60  SGTL B SG escalates to Design Basis rate (710 gpm) in AP-24.01. AP-16.00, sec ramp  Manual SI, E-0, E-3.
Failure of Auto Air Ejector to re-align on A/E RM High Alarm.
AS02/03 8      PCV455C    OFF      PZR PORV 1-RC-1455C will not open when switch placed in open - Go to ECA-
_OPEN,                3.3 PCV455C    ON
_CLOSE 9      SI409      TRUE      BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.
SI2505 Scenario Objectives:
A. Given a failure of 1-RC-MOV-1535 to re-open during performance of 1-PT-18.6I, PZR Block Valve Stroke Test, Implement the Applicable Tech Spec LCO.
B. Given a pressurizer level channel deviation, respond IAW 0-AP-53.00 to the failure.
C. Given a High Failure of SG Feed Flow Channel II on B SG, take action IAW 0-AP-53.00 to control SG level, and apply the applicable Tech Spec LCOs for the failure.
D. Given a trip of the running High Pressure Drain pump, ramp the Unit 1 <75% IAW 1-AP-18.00 and 0-AP-23.00.
E. Given a SG Tube Leak, respond IAW 1-AP-16.00 to quantify the leak rate, trip Unit 1, and perform the Immediate Action Steps of 1-E-0, Reactor Trip or Safety Injection.
F. Given a Design Basis SG Tube Rupture, respond IAW 1-E-0, and 1-E-3, Steam Generator Tube Rupture.
G. Given the Failure of 1-RC-PCV-1445C to open to depressurize the RCS, transition to 1-ECA-3.3, Steam Generator Tube Rupture without Pressurizer Pressure Control.
H. Given SI relay failures, manually align components IAW E-0, Attachment 1, 2, and 3.
 
SHIFT TURNOVER INFORMATION OPERATING PLAN:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance. Expected to be returned to services in 3 days. Per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
The last shift performed two 35 gallon dilutions followed by a manual makeup for training. A BAST concentration is 8.0 w/%.
Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, PZR Block Valve Stroke Test. Performance of this procedure has been authorized and has been PSA analyzed for current plant conditions.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                    Event No.: 1                    Page 10 of 92 Event
 
== Description:==
Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.
Cue: By Examiner.
Note:  An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.
The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.
A facility representative will be present for consultation with the Evaluation Team, as needed.
Time        Position                                  Applicants Action or Behavior 1-PT-18.6I SRO/BOP        NOTE - Team will pre-brief this evolution prior to entering the simulator. Initial Conditions and Precautions and Limitations will be completed before entering the simulator.
BOP        Verify closed or close PRZR PORV 1-RC-PCV-1456.
Verify key switch for PRZR PORV 1-RC-PCV-1456 OVPRESS BOP Mitigating System is in DISABLE.
Verify PRZR PORV Block Valve 1-RC-MOV-1535 is open.
BOP Stroke PRZR PORV Block Valve 1-RC-MOV-1535 through one complete cycle, timing valve movement in each direction. Time from signal initiation to complete valve travel.
BOP Valve closes and fails to reopen.
SRO Refer to Technical Specification 3.1.A.6 for required action
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 1                      Page 11 of 92 Event
 
== Description:==
Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.
Cue: By Examiner.
SRO        Refer to Technical Specification 3.1.A.6 for required actions.
With one block valve inoperable, within 1 hour either restore the block valve to operable status or place the associated PORV in manual. In addition, restore the block valve to operable status in the next 72 hours or, be in at least HSD within the next 6 hours and reduce RCS temperature to < 350&deg;F within the following 6 hours.
BOP        Places 1-RC-PCV-1456 in CLOSE.
SRO        Start 72 Hour Clock to repair Block Valve.
SRO        Direct RO/BOP to notify Service Building Operator to check status of 1H1-2S 6A breaker for 1-RC-MOV-1535.
RO/BOP        Contact Service Building Operator to check status of 1-RC-MOV-1535 Breaker.
RO/BOP        When notified by field operator that 1H1-2S 6A. Breaker is tripped, report information to the Team using a Focus Brief.
SRO        Notify Shift Manager of Block Valve failure and suspension of PT performance.
Request Electrical Maintenance support to investigate breaker trip.
SRO        Exit 1 hour clock to place 1-RC-PCV-1456 in manual.
SRO        Perform brief to update Team on Technical Specification requirements. Brief driven by brief card and placards.
END of Event #1.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 2                    Page 12 of 92 Event
 
== Description:==
PRZR Level Transmitter Fails Low, 0-AP-53.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior RO      Diagnoses failure of 1-RC-LI-1461 with the following indications/alarms:
Alarms:
* 1C-D8 PRZR LO LEVEL Indications:
* CH Flow rises on 1-CH-FI-1122A to ~109 gpm
* PRZR Level on 1-RC-LI-1461 lowers to 34%
In accordance with the immediate actions of AP-53.00 the RO will take manual control of pressurizer level control by placing 1-CH-FV-1122 in manual and lowering charging flow to maintain program level (per AP-53.00).
SRO      Enters 0-AP-53.00, Loss of Vital Instrumentation / Controls.
RO      [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL Checks 1-RC-LI-1459, Pressurizer Level Channel 1, and 1-RC-LI-1460, Pressurizer Level Channel 2 are NORMAL.
RO      [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-CH-FV-1122 in manual and raises charging flow.
SRO      Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.
SRO will provide a band for control of PRZR level with CH flow in MANUAL.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
Step 3, AP-53.00 RO      VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO will identify that reactor power is less than 100% using PCS Display of Core Thermal Power.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 2                        Page 13 of 92 Event
 
== Description:==
PRZR Level Transmitter Fails Low, 0-AP-53.00.
Cue: By Examiner.
SRO      Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO      *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
* PRZR Level Control, Step 11.
RO      The RO will identify that 1-RC-LI-1461 has failed.
Step 11, AP-53.00 SRO      11. CHECK PRZR LEVEL CONTROL CHANNELS - NORMAL RO          Responds NO, 1-RC-LI-1461 Abnormal.
SRO      11 a) RNO 1) Place either of the following in MANUAL:
* 1-CH-FC-1122C, CHG FLOW CNTRL, OR
* 1-CH-LC-1459G, PRZR LEVEL CNTRL RO          Responds 1-CH-FC-1122 in MANUAL SRO      11 a) RNO 2) Control PRZR Level at Program Level.
RO          Responds Maintain PRZR Level at program +/- band set by SRO SRO      11 a) RNO 3) Move PRZR Level - CH SEL switch to Defeat the failed channel.
RO/BOP          Transfers CH SEL switch to 1 / 2 Position.
SRO      11 a) RNO 4) Check or place recorder 1-RC-LR-1459 on an operable channel.
BOP          Checks or adjusts PRZR Level Recorder to 1-RC-LI-1459 or 1-RC-LI-1460.
SRO      11a) RNO 5) Refer to Tech Spec 3.7-1, Item 9 and Table 3.7-6, Item 13.
TS 3.7, Table 3.7-1, item 9; Operator Action 7. Number of Operable channels one less than Total number of channels: Place Inoperable channel in trip within 72 hours, allowed to bypass channel for 12 hours for surveillance, If conditions not met within allowed time, reduce power to less than P-7 in the next 6 hours.
TS Table 3.7-6m Item 13: Required Number of channels to meet function = 2.
11 a) RNO 6) Refer to Attachment 3.
SRO hands Attachment 3, Pressurizer Level Control diagram to RO/BOP for SRO review.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 2                    Page 14 of 92 Event
 
== Description:==
PRZR Level Transmitter Fails Low, 0-AP-53.00.
Cue: By Examiner.
Step 11, AP-53.00, Continued:
SRO      Step 11 b) Check Pressurizer Heaters - Energized.
RO          Checks Required Pressurizer Heaters energized, and reports that Pressurizer heaters are energized.
SRO      Step 11 c) Check Letdown - IN SERVICE.
RO          Reports Letdown in service.
SRO      Step 11 d) Check PRZR level control - IN AUTOMATIC.
RO          Reports pressurizer level control in MANUAL.
SRO      Step 11 d) RNO When pressurizer level restored to program level, un-saturate 1-CH-LC-1459G, PRZR LEVEL CNTRL. Place 1-CH-FCV-1122 in automatic.
RO          Acknowledges direction and notifies SRO when pressurizer level returned to AUTOMATIC.
Step 13, AP-53.00 SRO      SRO recalls NOTE 2 Prior to Step 4 and goes to Step 13 of AP-53.00.
SRO      Step 13 Check Calorimetric - Functional IAW 1-OPT-RX-001, Attachment 4.
RO/BOP      Checks Calorimetric unaffected by this failure, and reports to the SRO.
Step 14, AP-53.00 SRO          CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-RC-LI-1461 is a Reg. Guide 1.97 component.
STEP 15, AP-53.00 SRO          REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that the Reg. Guide 1.97 Review is complete and has been reviewed with the Shift Manager.
[CEP 99-0029 requires two channels of pressurizer level indication and refers to TS Table 3.7-6.]
 
Appendix D                                Required Operator Actions                                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 2                          Page 15 of 92 Event
 
== Description:==
PRZR Level Transmitter Fails Low, 0-AP-53.00.
Cue: By Examiner.
STEP 16, AP-53.00 SRO      Review the following:
* TS 3.7
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO determines that TS Table 3.7.1, Item 9 is applicable (72-hours to place the channel in trip). SRO determines that 3.1.A.5 is not applicable since pressurizer heaters did not de-energize and that Table 3.7-6 item 1 is Not Applicable.
SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
[TRM Section 3.3, Condition A, requires a Fire Watch be established in the Cable Vault and Tunnel and Emergency Switchgear Room of the affected Unit within 14 days, and restore the instrument to Functional status in 60 days. Hourly Fire Watch Requirement established in TRM Section 5.2. NO VPAP-2802 requirement for this failure.]
Step 17, AP-53.00 SRO            CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS The team will identify that no new additional failures exist (i.e., all failures have already been addressed), proceed to the RNO section, and this will direct the team to Step 19.
Step 19, AP-53.00 SRO      PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C END EVENT 2
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                    Event No.: 3                    Page 16 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
Time        Position                                  Applicants Action or Behavior BOP        Diagnoses failure FT-1487 with the following indications/alarms:
Alarms:
* 1H-E6 STM GEN 1B FW >< STM FLOW
* 1F-D8 STM GEN 1B CH 3 FW < STM FLOW
* 1H-G6 STM GEN 1B LVL ERROR.
Indications:
* Step increase in 1B SG Feed Flow indication CH-3
* decrease in 1B SG Feed Flow indication CH-4
* decreasing level on B SG.
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS Step 1, AP-53.00 BOP        [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL BOP identifies Channel IV indication for feed flow is NORMAL.
Step 2, AP-53.00 BOP        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and increases demand (FF >
SF) to restore level to program using Channel IV indication.
SRO        Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.
SRO will provide a band for control of B SG level with B FRV in MANUAL.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                  Event No.: 3                      Page 17 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
Step 3, AP-53.00 SRO
* VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO              Checks Reactor Power < 100% using PCS Calorimetric. Due to restoration of FF on 1B SG, power increase may be noted. As required, the SRO may direct the BOP to reduce turbine load to prevent exceeding 100% Calorimetric power.
Note: 0-AP-53.00, Attachment 7 Actions are contained at the end of this section starting on page 20.
Step 4, AP-53.00, Notes SRO        NOTE: When the affected instrument/controller malfunction has been addressed by this procedure, recovery actions may continue at Step 13.
Step 4, AP-53.00 SRO        DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
RO/BOP            Identifies 1B SG Feed Flow affected.
SRO              Goes to Step 7.
Step 7, AP-53.00 SRO        CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.
SRO        CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS - NORMAL
* Steam Pressure
* Steam Flow
* Feed Flow
* Steam Generator Level BOP        Determines CH III Feed flow instrumentation for B SG is NOT normal.
Step 7. RNO, AP-53.00 IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level Control system has failed, THEN do the following:
BOP              a) Place the associated Feed Reg Valve in MANUAL.
BOP        Verifies B SG MFRV controller, 1-FW-FCV-1488, in manual BOP              b) Control SG level at program level (44%, a band will be given).
BOP        Verifies B SG NR level is returning to program level.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                      Event No.: 3                  Page 18 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
RO              c) Select the redundant channel for affected SG(s)
RO        Selects Channel IV Feed Flow for B SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV)
BOP              d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.
BOP        Places B SG FRV controller, 1-FW-FCV-1488, in automatic control.
Step 6, RNO, AP-53.00 (Continued)
SRO        Perform follow-up actions:
a)  Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.
If asked the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
b) Refer to the following Tech Spec 3.7 items:
SRO
* Table 3.7-1, 12 and 17
* Table 3.7-2, 1.c, 1.e, and 3.a
* Table 3.7-3, 2.a, and 3.a
* Table 3.7-6, 15 and 16 Determines Table 3.7-1 item 17, is applicable (place channel in trip w/in 72 hours).
SRO c)  Refer to Attachment 1.
d) IF no other instrumentation failure exists, THEN GO TO Step 13.
Step 13, AP-53.00 SRO        13. Review OPT-RX-001, Rx Power Calorimetric using PCS computer program, Attachment 4, to determine operability of calorimetric and need to perform OPT-RX-007, Shift Average Power Calculation.
RO            Determines that OPT-RX-001 is NOT impacted and OPT-RX-007 will NOT need to be performed.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                  Event No.: 3                    Page 19 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
Step 13, RNO, AP-53.00 SRO            a) Initiate ( )-OPT-RX-007, SHIFT AVERAGE POWER CALCULATION, as necessary.
Note: The Team will determine that the Calorimetric Program is functional based on a recent change to 1-OPT-RX-001, Calorimetric, Attachment 4.
Step 14, AP-53.00 SRO        14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 14 if not Reg. Guide 1.97)
SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-FW-FT-1487 is a Reg. Guide 1.97 component.
Step 15, AP-53.00 SRO        15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 requirements have been reviewed with the Shift Manager.
[Reg. Guide 1.97 requires one channel of Feed Flow indication per steam generator and no further actions are required.]
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                  Event No.: 3                  Page 20 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
SRO        16 REVIEW THE FOLLOWING:
* Tech Spec 3.7
* VPAP-2802, NOTIFICATIONS AND REPORTS
* TRM SECTION 3.3, INSTRUMENTATION SRO            Directs STA to perform Review of Tech Spec 3.7, VPAP-2802, and TRM Section 3.3.
STA            The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
[VPAP-2802 - no requirement associated with the failure, No TRM requirements for this failure].
SRO        17. CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS Goes to Step 19 SRO        19. PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C END OF EVENT 3 0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 1    IF a rise in Reactor Power is caused by secondary transient, THEN GO TO Step 2.
IF a rise in Reactor Power is caused by primary transient, THEN GO TO Step 6.
NOTE: During secondary transient conditions, the most reliable indications of Reactor Power are Core T and Power Range NI. These indications should be used as the basis for Reactor Power until stable conditions have been reestablished.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 3                      Page 21 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 2  Mitigate a rise in Reactor Power caused by secondary transients by lowering steam demand or Turbine load as follows:
a) Reduce the Turbine Setter by an appropriate amount.
b) Place the Load Rate Selector thumbwheel to 1% / min.
c) Depress the GO pushbutton.
3  IF Turbine load can NOT be reduced using Operator Auto, THEN lower Turbine load using the Valve Position Limiter.
4  IF Turbine load still can NOT be reduced, THEN do the following.
a) Push the Turbine Manual pushbutton.
b) Check Turbine controls in Manual.
c) Depress the GV down pushbutton to reduce GV position.
NOTE: The CALCALC 10 minute Average Power will lag actual Reactor Power following a transient, and may continue to rise even after core thermal power has been reduced to less than 100%.
5  Check Reactor Power reduced to less than 100%.
* Power Range NI power.
* Core T power
* CALCALC Instantaneous power (if reliable)
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 3                      Page 22 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 6  Mitigate a rise in Reactor Power caused by primary transients as follows. Enter N/A for Steps 6 through 9 if NOT applicable.
a) Place the Rod Control Selector switch in Manual.
b) Insert control rods.
NOTE: The CALCALC 10 minute Average Power will lag actual Reactor Power following a transient, and may continue to raise even after core thermal power has been reduced to less than 100%.
7  Check Reactor Power reduces to less than 100%.
* Power Range NI power.
* Core T power
* CALCALC Instantaneous power (if reliable) 8  IF necessary, THEN initiate a normal boration to control  Flux.
: 9. WHEN Tave and Tref are within 1&deg;F, THEN place control rods in Auto.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 1                  Event No.: 4                  Page 23 of 92 Event
 
== Description:==
Loss of High Pressure Drain Pump, 1-AP-18.00.
Cue: By Evaluator BOP        Diagnose the trip of the High Pressure Drain Pump, 1-SD-P-1A based on the following indications:
* 1K-D4 4 KV BKR AUTO TRIP
* 1H-F3 CN POLISHING SYS TRBL
* 1H-D3 CN POLISHING BYPASS AOV OPEN
* 1J-B4 HP HTR DR RCVR TK HI LVL
* 1H-G5/6/7 SG 1A/1B/1C LVL ERROR Step 1, AP-18.00 SRO        Enter 1-AP-18.00 CHECK HP HEATER DRAIN PUMP STATUS:
SRO            a)  Check HP Heater Drain Pump - TRIPPED OR NOT PROVIDING SUFFICIENT FLOW BOP              Reports that 1-SD-P-1, HP Heater Drain pumps tripped.
SRO            b) Place pump control Switch in PTL BOP            Places 1-SD-P-1A control switch in PTL Step 2, 1-AP-18.00 SRO        CHECK REACTOR POWER - GREATER THAN OR EQUAL TO 75%
RO/BOP            Reports reactor power at 100%
Step 3, AP-18.00 SRO        START THIRD CONDENSATE PUMP AS REQUIRED BY PLANT CONDITIONS BOP            Starts 1-CN-P-1A and verifies Proper Operation.
Step 4, AP-18.00 SRO        NOTE: With unit at 100% power, Turbine load should be decreased approximately 50 MW.
REDUCE TURBINE LOAD AS NECESSARY TO MAINTAIN LOOP Ts -
LESS THAN 100%
* Use Valve Position Limiter OR
* Reduce Turbine load using Turbine Manual BOP            Using Guidance of NOTE preceding the Step, Turbine load will be reduced.
 
Appendix D                                  Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 1                Event No.: 4                  Page 24 of 92 Event
 
== Description:==
Loss of High Pressure Drain Pump, 1-AP-18.00.
Cue: By Evaluator Step 5, 1-AP-18.00 SRO        NOTE: Ramping to 75% allows the Condensate Polishing Building to be placed fully in service.
COMMENCE RAMP TO 75% POWER IAW 0-AP-23.00, RAPID LOAD REDUCTION Step 6, 1-AP-18.00 SRO
* USE CONTROL RODS AND CHEMICAL SHIM TO MAINTAIN FLUX IN BAND Step 7, 1-AP-18.00 SRO        MONITOR MAIN FEED REG VALVE RESPONSE - MAINTAINING SG LEVEL IN BAND BOP            Acknowledges Step direction.
SRO            Initiate AP-23.00, Rapid Load Reduction END EVENT #4
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                    Event No.: 5                    Page 25 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior AP-23.00, Rapid Load Reduction SRO      The team will hold a transient brief. During the brief the upcoming ramp will be discussed.
The RO and BOP will report critical parameters, as per placard on Main Control Room Bench Board. It is expected that the RO will discuss reactivity parameters associated with the ramp from the pre-planned ramp plan.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
The following reactivity plan will be discussed for a ramp to 75%:
* Gallons of boric acid required as per plan - 146 gallons
* D control bank end at 197 steps
* 5.8 gpm Boric Acid Flow, average rate during ramp.
* 1957 gallon PG required to stabilize at 75% power.
* The Team will discuss duration of Emergency Borate at start of Ramp, and remaining boron to be added via normal boration flowpath.
NOTE: RO Emergency borates for 25 seconds which corresponds to ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.
Step 1, 0-AP-23.00 SRO      Caution Prior to Step 1:
* Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.
Notes Prior to Step 1:
* Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
* When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
* Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
* The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
* For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                    Event No.: 5                      Page 26 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Step 1, 0-AP-23.00 RO      TURN ON ALL PRZR HEATERS.
Step 2 0-AP-23.00 INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:
BOP          a) Check turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter. If turbine is on limiter; reduce setter an appropriate amount, set load rate thumbwheel to 2% (or higher), press GO.
When Turbine limiter light OFF, press HOLD button.
RO          b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5&deg;F.
BOP          c) Check or place turbine in IMP IN or IMP OUT as determined by Shift Supervision The SRO chooses IMP IN.
BOP          d) Adjust SETTER to desired power level BOP          e)  Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute)
BOP          f)  Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button)
BOP          g) Reduce Turbine Valve Position Limiter as load decreases Periodically reduce the limiter setpoint during the ramp.
Step 3, 0-AP-23.00 SRO          CHECK EMERGENCY BORATION - REQUIRED RO          Reports Emergency Boration required.
Step 4, 0-AP-23.00 SRO      NOTE: Step 4 or Step 5 may be performed repeatedly to maintain Tref and Tave matched,  Flux in band, and control rod position above the LO-LO insertion limit.
RO      Acknowledges NOTE.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                    Event No.: 5                  Page 27 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Step 4, 0-AP-23.00 SRO      PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:
RO          a) Check or raise CHG flow to greater than 75 gpm RO          b) Transfer the in-service BATP to FAST RO          c) Open 1-CH-MOV-1350 for required time (~25 seconds)
RO          d) Monitor EMRG BORATE FLOW
                                      * ( )-CH-FI-( )110 e)  After required emergency boration, perform the following:
RO                1) Close 1-CH-MOV-1350 RO                2) Transfer the in-service BATP to AUTO
: 3) Restore Charging flow control to normal.
Step 5, 0-AP-23.00 RO          ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.
Step 6, 0-AP-23.00, NOTES SRO      NOTES:
* If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
* RCS Tave must be maintained less than or equal to 577&deg;F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
* I & C should be contacted to provide assistance with adjusting IRPIs.
Step 6, 0-AP-23.00 RO/BOP          CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG Step 7, 0-AP-23.00 RO
* CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                Event No.: 5                    Page 28 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Step 8, 0-AP-23.00 BOP      MONITOR STEAM DUMPS FOR PROPER OPERATION Step 9, 0-AP-23.00 SRO      NOTIFY THE FOLLOWING:
* Energy Supply (MOC)
* Polishing Building
* Chemistry
* OMOC Step 10, 0-AP-23.00 SRO      EVALUATE THE FOLLOWING:
* EPIP applicability
* VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.
[VPAP-2802 and EPIP are not applicable for this event.]
Step 11, 0-AP-23.00 SRO          CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR.
When reactor power has decreased >15%, then chemistry will be notified.
END EVENT #5
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1      Scenario No.: 1                    Event No.: 5                  Page 29 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO      1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO      2. Adjust 1-CH-YIC-1113 to desired total gallons RO      3. Adjust 1-CH-FC-1113A to desired flow rate.
RO      4. Place the MAKE-UP MOD SEL switch in the BORATE position.
RO      5. Place the MAKE MODE CNTRL switch in the START position.
RO      6. Check proper valve positions.
RO      7. Adjust boration rate using 1-CH-FC-1113A, as necessary.
RO      8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.
a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.
b) Enter N/A for the remaining steps in this Attachment.
Attachment 5 is on the next page RO      9. Check controllers for Primary Grade water and Boric Acid are set correctly.
RO      10. Place the MAKE-UP MODE SEL switch in the AUTO position.
RO      11. Place the MAKE-UP MODE CNTRL switch in the START position.
RO      12. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                    Event No.: 5                  Page 30 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Time        Position                              Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions RO      1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO      2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
RO      3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
RO      4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
RO      5. Place the MAKE-UP MODE CNTRL switch in the START position.
RO      6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
RO      7. Check proper valve positions.
RO      8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1113B in the AUTO position RO      9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO      10. Check or place the control switches in the AUTO position.
RO      11. Check controllers for Primary Grade water and Boric Acid are set correctly.
RO      12. Place the MAKE-UP MODE SEL switch in the AUTO position.
RO      13. Place the MAKE-UP MODE CNTRL switch in the START position.
RO      14. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 6                      Page 31 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Time        Position                              Applicants Action or Behavior Team      Diagnose SGTL B SG based on the following:
Alarms:
* 1A-B3 N-16 ALERT
* 1A-A3 N-16 HIGH
* RM-G8 CNDSR AIR EJECTOR ALERT/FAILURE
* RM-H8 1-SV-RI-111 HIGH Indications:
* Increasing trend on 1-MS-RR-193, Control Room N16 Trend Recorder, from Normal to 200 GPD.
* STM LINE B Trend will Lead STM LINE A and STM LINE B.
SRO          Direct Unit to Perform Annunciator Response Procedure for A/E Alert and High Alarms.
Note: Unit 2 Operator will perform ARP for A/E RM Alarms. Unit 2 will hand Page 3 and 4 of RM-H8 ARP to BOP to check Auto Actions complete; following E-0 Team Brief.
Verification of ARP RM-H8, A/E RM High Alarm RM-H8, Step 6 BOP      NOTE: On a high alarm, air ejector gaseous effluent is diverted from vent stack to containment.
CHECK AUTOMATIC ACTIONS - VALVES POSITIONED AS FOLLOWS:
* 1-SV-TV-103 - CLOSED Identifies 1-SV-TV-103 Open, places control switch in close.
* 1-SV-TV-102 - OPEN Identifies 1-SV-TV-102 Closed, places control switch in open.
RM-H8, Step 7 BOP      CHECK AIR EJECTOR VENT TO CTMT VV - OPEN
* 1-SV-TV-102A Identifies 1-EV-RV-102A open Report to SRO that A/E manually aligned to containment.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                  Event No.: 6                    Page 32 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
1-AP-16.00 SRO            Direct the RO to perform the Immediate Action Steps of 1-AP-16.00.
Step 1, 1-AP-16.00 RO      NOTE:
* If SI Accumulators are isolated, 1-AP-16.01, SHUTDOWN LOCA, should be used for guidance.
* RCS average temperature has a direct impact on pressurizer level.
[ 1 ] ___ MAINTAIN PRZR LEVEL:
RO
* Isolate Letdown Close 1-CH-LCV-1460A and 1-CH-LCV-1460B
* Control Charging flow Place 1-CH-FCV-1122, CH Flow Control Valve, in Manual Monitor CH Flow on 1-CH-FI-1122 Identify RCS leak rate less than the capacity of a single CH pump Continue adjustment of CH flow to quantify leak rate to determine if reactor trip required Step 1, 1-AP-1600 SRO            Upon report of completion of Immediate Action Step of 1-AP-16.00, Perform a commensurate brief; continue to Step 2 of 1-AP-16.00.
Step 2, 1-AP-16.00 SRO CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING
* PRZR level
* PRZR pressure
* RCS subcooling RO            Report that PRZR Level, Pressure, and Subcooling Stable RO continues actions to quantify leakrate Step 3, 1-AP-16.00 SRO            PLACE THE FOLLOWING COMPONENTS IN OFF:
RO
* CTMT sump pumps Places 1-DA-P-4B control switch on OFF
* CTMT vacuum pumps Places 1-CV-P-1A control switch in OFF
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 6              Page 33 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 4, 1-AP-16.00 SRO      NOTE: Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.
SRO      CHECK REACTOR TRIP - REQUIRED
* Leak rate - GREATER THAN 50 GPM OR
* Adequate makeup not being provided by blender RO          Reports RCS leak rate greater than 50 gpm.
NOTE: Due to transient on RCS caused by Ramp for previous event, exact quantification of leak rate may be difficult.
Step 5, 1-AP-16.00 SRO          ALIGN CHG PUMP SUCTION TO RWST a) Open 1-CH-MOV-1115B and 1-CH-MOV-1115D RO          Opens CH pump Suction MOVs from RWST, 1-CH-MOV-1115B/D b) Close 1-CH-MOV-1115C and 1-CH-MOV-1115E Closes CH pump Suction from VCT MOVs, 1-CH-MOV-1115C/E Step 6, 1-AP-16.00 SRO      GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 1                    Event No.: 6              Page 34 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
1-E Reactor Trip or Safety Injection RO      [1] CHECK REACTOR TRIP:
a)  Manually trip reactor Pushes the reactor trip push buttons.
b)  Check the following:
* All Rods On Bottom light - LIT
* Reactor trip and bypass breakers - OPEN
* Neutron flux - DECREASING RO Reports Reactor Tripped at completion of Step 1. SRO Acknowledges.
RO      [2] CHECK TURBINE TRIP:
RO          a)  Manually trip the turbine Pushes the turbine trip push buttons.
b)  Check all turbine stop valves - CLOSED c)  Isolate reheaters by closing MSR steam supply SOV
* 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)
RO Reports Turbine Tripped at completion of Step 2. SRO Acknowledges.
RO      [3] VERIFY BOTH AC EMERGENCY BUSES - ENERGIZED RO Reports Both AC Emergency Buses Energized at completion of Step 3. SRO acknowledges.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 6                    Page 35 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
RO      [4] CHECK IF SI INITIATED:
a)    Check if SI is actuated:
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3 SI INITIATED - TRAIN A
* A-F-4 SI INITIATED - TRAIN B RO will determine that SI has not occurred and perform step 4a RNO actions:
RO 4a RNO Check if SI is required or imminent as indicated by any of the following:
* Low PRZR pressure
* High CTMT pressure
* High steamline differential pressure
* High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.
RO reports SI is not in service or required; Immediate Actions of E-0 are complete; recommend transition to ES-0.1 after completion of Step 4. SRO Acknowledges.
After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0 and announce a transition to ES-0.1. After the immediate actions are verified, the team will conduct a brief.
During the Brief RO/BOP reports that ALL RCPs are tripped.
Team Identify 1B SG experiencing a Large SG Tube Leak.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal, with the exception of the alarms already received. He will also state that containment conditions and the electrical conditions are as you see them (or as reported by the RO/BOP).
If not previously performed, Unit 2 Operator will Provide BOP/SRO with ARP pages Unit 2 for A/E RM High alarm for verification of Auto Actions.
Establish priorities at Brief End, RO:
SRO
* Continue with SRO in 1-AP-24.01, Large Steam Generator Tube Leak, BOP:
* Complete verification of A/E High Alarm auto actions.
* Throttle AFW to the SGs IAW Attachment 8 of AP-24.01.
* Contact Service Building Operator to check status of RCP breakers.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 6                  Page 36 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
SRO      When Brief is complete Announce Transition to ES-0.1, Reactor Trip Response, Read the First NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.
Transitions to 1-AP-24.01 Step 1, 1-AP-24.01 SRO      CAUTION: If the leak rate increases to 150 gpm, 1-E-0, Reactor Trip or Safety Injection, must be implemented.
NOTE:
* Procedure 1-ES-0.1, Reactor Trip Response, must not be performed when implementing this procedure.
* Refer to Attachment 8 for guidance on transient AFW control.
CHECK SI - IN SERVICE RO            Identifies NO not required. Team Goes To Step 3.
Note: Attachment 8 actions are start on Page 40.
Step 3, 1-AP-24.01 SRO      CHECK CONDENSATE POLISHING BUILDING - BYPASSED RO            Identifies Polishing Building bypassed Step 4, 1-AP-24.01 SRO      CHECK ALL AC BUSSES - ENERGIZED BY OFFSITE POWER RO          Identifies all AC Buses energized by off-site power by:
* Checks breakers 15H8/15J8 closed
* Station Service buses energized using Voltage/Current indications on Benchboard.
* Checks for Abnormal Electrical System alarms on K Annunciator Panel.
Step 5, 1-AP-24.01 SRO
* CHECK PRZR LEVEL - GREATER THAN 22%
RO      Reports actual pressurizer level and trend.
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 6                  Page 37 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 6, 1-AP-24.01 SRO      CHECK FW STATUS:
a) Check RCS Average temperatures - LESS THAN 554&deg;F RO      Identifies RCS Tave less than 554&deg;F b) Check Feed REG valves - CLOSED RO      Identifies FRVs closed c) Close SG FW isolation MOVs
* 1-FW-MOV-154A
* 1-FW-MOV-154B
* 1-FW-MOV-154C RO/BOP      Closes SG FW Isolation MOVs d) Check AFW pumps - RUNNING
* Motor Driven AFW pumps
* TD AFW pump RO/BOP      Identifies MD and TD AFW Running e) Check total AFW flow - GREATER THAN 540 GPM (350 W/O RCPs)
RO/BOP      Identifies AFW flow indicated f) Check emergency buses - BOTH ENERGIZED RO      Identifies Emergency buses energized g) Control feed flow to maintain narrow range level between 22% and 50%
BOP      Acknowledges control of SG level when returned to NR scale.
Step 7, 1-AP-24.01 SRO      CHECK PCS POINTS USING GROUP 80 REVIEW OR MAIN STEAM P & ID:
* R1RM204C, RI-MS-124
* R1RM205C, RI-MS-125
* R1RM206C, RI-MS-126 RO/BOP      Checks points for abnormal indication.
 
Appendix D                                  Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 6            Page 38 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 8, 1-AP-24.01 SRO      IDENTIFY AFFECTED SG(S):
* Unexpected rise in any SG narrow range level OR
* High radiation from any SG MS line monitor OR
* High radiation from any SG blowdown line OR
* High radiation from any SG sample OR
* High radiation from any SG N-16 monitor RO/BOP      Identifies rise in B SG NR level Step 9, 1-AP-24.01 SRO
* CHECK AFFECTED SG LEVEL:
a) Narrow range level - GREATER THAN 12%
BOP      Acknowledges when B SG NR Level > 12%, perform substep b).
b) Stop feed flow to affected SG(s)
BOP      Isolates AFW flow to B SG, by closing 1-FW-MOV-151 C / D.
 
Appendix D                                Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 6            Page 39 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 10, 1-AP-24.01 SRO      ISOLATE AFFECTED SG(S):
a) Adjust affected SG PORV controller setpoint to 1035 psig BOP      Checks B SG PORV setpoint at 1035 psig b) Check affected SG PORV - CLOSED BOP      Identifies B SG PORV closed c) Check blowdown TVs from affected SG - CLOSED RO      Identifies B SG BD TVs closed.
d) Locally close steam supply valve to TD AFW pump:
* 1-MS-87 for SG A
* 1-MS-120 for SG B
* 1-MS-158 for SG C BOP      Directs Service Building operator to close 1-MS-120.
e) Close SG FW Isolation MOV, 1-FW-MOV-154A, B, or C BOP      Identifies 1-FW-MOV-154B closed f) GO TO Step 13
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 6                  Page 40 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 1, AP-24.01, Attachment 8 BOP      Maintain minimum AFW flow of 540 gpm with RCP(s) in service until one SG Narrow Range level is greater than 12%.
Checks AFW ~1050 gpm Step 2, AP-24.01, Attachment 8 Maintain minimum AFW flow of 350 gpm with NO RCPs running, until one SG BOP      Narrow Range level is greater than 12%.
Throttles AFW to SGs per Step 2 to flow rate established by SRO or ~ 120 gpm per SG using 1-FW-MOV-151 A through F control switches.
Step 3, AP-24.01, Attachment 8 BOP      NOTE: AFW to idle loop(s) (RCP secured), should be throttled to prevent depressurization of the SG and subsequent Header / Line SI. AFW flow between approximately 60 gpm and 100 gpm should be adequate to prevent a Header / Line SI.
Identifies NOTE as not applicable for this event.
When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50% by throttling AFW Isolation MOVs:
* SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
* SG B, 1-FW-MOV-151C and 1-FW-MOV-151D
* SG C, 1-FW-MOV-151A and 1-FW-MOV-151B Identifies need to monitor flow rate as SG NR level recovers.
Step 4, AP-24.01, Attachment 8 BOP      Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves:
Identifies Step as not applicable.
Contact Service Building operator to check status of RCP breakers.
BOP          When contacted the Service Building operator will report no abnormalities with the RCP breakers, but the Speed Sensing Panel appears to be malfunctioning.
Performs a Focus Brief to apprise the other Team members of RCP status.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                      Page 41 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
SG Tube Leak escalates to 710 gpm Tube Rupture RO      Diagnose SG Tube Rupture by:
RCS Pressure decrease.
Pressurizer Level decrease.
Manually raise CH flow to maximum.
Identify pressurizer level decreasing.
Report to SRO that Safety Injection is required.
Re-Perform High Level Steps, 1 through 3 of E-0.
Manually Initiate Safety Injection.
Check Annunciator 1A-F3, SI Initiated Train A - LIT Check Annunciator 1A-F4, SI Initiates Train B - LIT Check LHSI Pumps Running.
Report to SRO Immediate Actions of E-0 with SI Complete.
Critical Task 2) Isolate steam release from ruptured SG within 30 Minutes START Time: _____________
SRO      The team will hold a transition brief. During the brief it will be identified that SI was initiated and the SGTL has degraded into a SGTR.
The SRO will set priorities:
RO - Continue with SRO in performance of E-0 to E-3.
BOP - Perform Attachment 1 through 3 of E-0.
Step 5, E-0 SRO/BOP      Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained under last section of Event 9).
SRO/RO      SRO may direct the RO to perform Attachment 10 of 1-E-0 for Ruptured SG Isolation and AFW Control. This may or may not be initiated at any time during the performance of E-0. Attachment 10 actions are contained at the end of this section.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                    Page 42 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 6, E-0 RO
* CHECK RCS AVERAGE TEMPERATURE
* STABLE AT 547&deg;F OR
* TRENDING TO 547&deg;F The team will identify that RCS temperature is decreasing. The team should attribute this to the injection of SI into the RCS and AFW flow to the SGs. It is acceptable for the team to enter the RNO portion of this step and perform the applicable steps (summarized below):
Stop dumping steam Reduce AFW flow to the SG Close MSTVs if cooldown continues Step 7. E-0
: 7. CHECK PRZR PORVs AND SPRAY VALVES:
RO            a) PRZR PORVs - CLOSED b) PRZR spray controls
* Demand at Zero (or)
* Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN Step 8, E-0 SRO      NOTE: Seal injection flow should be maintained to all RCPs.
* CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
RO            a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RCS subcooling will NOT be less than 30 &deg;F RNO for the step is to go to step 9.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                      Event No.: 7                      Page 43 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 9, E-0 RO      CHECK IF SGs ARE NOT FAULTED:
* Check pressures in all SGs a)  STABLE OR INCREASING AND b)    GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.
Step 10, E-0 RO      CHECK IF SG TUBES ARE NOT RUPTURED:
* Condenser air ejector radiation - NOT NORMAL
* SG blowdown radiation - NOT NORMAL
* SG MS radiation - NORMAL
* TD AFW pump exhaust radiation - NORMAL
* SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO should observe B SG NR level going up uncontrollably.
SRO      RNO: GO TO 1-E-3, STEAM GENERATOR TUBE RUPTURE.
SRO      The team will hold a transition brief. During the brief it will be identified that B SG is ruptured, current isolation status of the ruptured SG and that the team is transitioning to 1-E-3.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified alarms. He will also state that containment conditions and the electrical conditions are as you see them.
 
Appendix D                                Required Operator Actions                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 7      Page 44 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
BEGIN Step 1, 1-E-3:
NOTE: Seal injection flow should be maintained to all RCPs.
                        *CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
RO a)  Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO will identify that two charging pumps are running.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RO will identify that RCS subcooling is greater than 30&deg;F RNO is to go to step 2 Step 2, E-3 IDENTIFY RUPTURED SG(s):
* Unexpected rise in any SG narrow range level SRO                OR
* High radiation from any SG MS line monitor OR
* High radiation from any SG blowdown line OR
* High radiation from any SG sample Team identifies B SG NR level rising unexpectedly.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 7                    Page 45 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 3, E-3 SRO      CAUTION:
* If the TD AFW pump is the only available source of feed flow, steam supply to the TD AFW pump must be maintained from at least one SG.
* At least one SG must be maintained available for RCS cooldown.
: 3. ISOLATE RUPTURED SG(s):
RO a) Adjust ruptured SG PORV controller setpoint to 1035 psig b) Check ruptured SG(s) PORV - CLOSED c) Verify blowdown TVs from ruptured SG(s) - CLOSED d) Locally close steam supply valve(s) to TD AFW pump:
* 1-MS-120 for B SG If 1-MS-120 not closed iaw attachment 10 of 1-E-0, then a field operator will be dispatched to close it at this time.
e)  Close ruptured SG(s) MSTV (B)
Partial completion of the critical task (WOG E-3A) to isolate the SG is accomplished by performance of this step. KOA: For the design basis tube rupture, isolate the ruptured SG from the atmosphere/Turbine building within 30 minutes.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                    Event No.: 7                    Page 46 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 4, E-3 SRO      CAUTION: If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless needed for RCS cooldown.
* CHECK RUPTURED SG LEVEL:
a) Narrow range level - GREATER THAN 12% [18%]
b) Stop feed flow to ruptured SG(s)
RO              Identifies B SG level >12%, closes 1-FW-MOV-151C/D to isolate AFW Flow c) Check ruptured SG AFW MOVs auto-open signal - DEFEATED Identifies auto-open signal not defeated, SRO goes to Step 4 c) RNO NOTE: BOP may have performed the following IAW Attachment 10.
: 1) Select the ruptured SG AFW MOVs using the following switches:
RO
* H TRAIN DISABLE SELECTOR SWITCH
* J TRAIN DISABLE SELECTOR SWITCH
: 2) Defeat the auto-open signal for the selected MOVs by placing the following key switches in the DISABLE SELECTED position:
* H TRAIN AUTO OPEN ENABLE SWITCH
* J TRAIN AUTO OPEN ENABLE SWITCH Step 5, E-3 SRO      CAUTION: Major steam flow paths from the ruptured SG(s) should be isolated before initiating RCS cooldown.
CHECK RUPTURED SG(S) PRESSURE - GREATER THAN 350 PSIG RO            Identifies B SG pressure ~ 1000 psig.
Step 6, E-3 SRO
* CHECK LOW PRZR PRESS SI SIGNAL - BLOCKED
* Permissive Status light C LIT RO              Identifies PSL C2 NOT LIT.
SRO      WHEN PRZR pressure less than 2000 psig, THEN do the following:
a) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block.
b) Check Permissive Status light C LIT.
NOTE: BOP may have completed this action in E-0, Attachment 1.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                      Event No.: 7                    Page 47 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 7, E-3 SRO      CHECK LOW TAVE SI SIGNAL - BLOCKED
* Permissive Status light F LIT RO            Identifies PSL F1 NOT LIT.
SRO            WHEN Tave less than 543&deg;F, THEN do the following:
a) Turn both HI STM FLOW & LO TAVG OR LP switches to block.
b) Check Permissive Status light F LIT.
NOTE: BOP may have completed this action in E-0, Attachment 1.
Step 8, E-3 SRO    CAUTION:
* Flow on each Main Steamline should be kept less than 1.0 x 106 PPH to prevent Main Steamline isolation during RCS cooldown with the Steam Dumps.
* If no RCPs are running, RCS cooldown and depressurization may cause a false Integrity Status Tree indication on the ruptured loop. The Cold Leg indication on the ruptured loop should be disregarded until after the performance of Step 36.
NOTE: RCP trip criteria does NOT apply after initiation of an operator controlled cooldown.
INITIATE RCS COOLDOWN:
a) Determine required core exit temperature (ONE TIME):
SRO/BOP          Concur Target CETC temperature 485 &deg;F if SG pressure between 901 and 1000 psig, or 495&deg; if SG pressure between 1001 and 1085 psig.
Step 8, E-3, Continued RO            b) Place Steam Dump Mode Select switch in Steam Pressure mode c) Check RCS Tave - LESS THAN 543&deg;F RO          d) Place the STM DUMP CNTRL switch in BYP INTLK and then return to ON e) Check Bypass Status light D LIT RO            f) Dump steam to condenser from intact SG(s) at maximum rate g) Check CETCs - LESS THAN REQUIRED TEMPERATURE SRO          When RCS Temperature < 543&deg;F, SRO will direct the block of HSF SI and check of PSL F1 LIT.
When RCS pressure < 2000 psig, SRO will direct the block of Low Pressure/Header-to-Line SI Signal, and check the PSL C2 LIT.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                      Page 48 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
RO          Performs the Block of SI Signals and check of PSLs when directed.
h) Stop RCS cooldown RO          When target CETC Temperature reached, RO throttles back on steam dumps.
i) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE SRO          SRO will direct a band for control of CETC temperature.
Step 9, E-3 SRO      CHECK INTACT SG LEVELS:
a) Any narrow range level - GREATER THAN 12% [18%]
b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%
RO/BOP            Adjust AFW to restore A and C SG NR Level to 22-50%.
Step 10, E-3 SRO      CAUTION: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure decreases to less than 2335 psig.
                              *CHECK PRZR PORVs AND BLOCK VALVES:
a) Power to PRZR PORV block valves - AVAILABLE b) PRZR PORVs - CLOSED c) PRZR PORV block valves - AT LEAST ONE OPEN Step 11. E-3 SRO            RESET BOTH TRAINS OF SI RO              Push SI Reset Pushbuttons. SI previously reset.
Step 12, E-3 SRO            RESET CLS:
a) Check CTMT pressure - HAS EXCEEDED 17.7 psia RO                  Report No, CTMT has not exceeded 17.7 psia.
RNO a) GO TO Step 13.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                  Page 49 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 13, E-3 SRO          CHECK INSTRUMENT AIR AVAILABLE:
a) Check annunciator B-E NOT LIT RO            Report Yes, B-E-6 Not Lit.
b) Check at least one CTMT IA compressor - RUNNING
* 1-IA-C-4A or 1-IA-C-4B RO            Report Yes, 1-IA-C-4A running c) Check 1-IA-TV-100 - OPEN RO            Report Yes, 1-IA-TV-100 open.
Step 14, E-3 SRO          ALIGN CONDENSER AIR EJECTOR TO CTMT:
a) Check the following:
* 1-SV-TV-102 - OPEN
* 1-SV-TV-103 - CLOSED RO            Reports valves in required position. Valves Manually Aligned by BOP on A/E RM auto failure during Event 6.
b) Open the following valve:
* 1-SV-TV-102A RO/BOP          Opens 1-SV-TV-102A.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                  Page 50 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 15, E-3 SRO      CAUTION: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.
                              *CHECK IF LHSI PUMPS SHOULD BE STOPPED:
a) Check LHSI pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST RO                Reports 1 LHSI pump running with suction aligned to RWST.
b) RCS pressure - GREATER THAN 250 PSIG [400 PSIG]
RO                Reports RCS pressure greater than 250 psig.
c) Stop LHSI pumps and put in AUTO RO                Stops running LHSI pump and places in AUTO.
Step 16, E-3 SRO          CHECK IF RCS COOLDOWN SHOULD BE STOPPED:
a) Check CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP          Reports CETCs < required temperature b) Stop RCS cooldown RO/BOP          Reports RCS Coodown stopped.
c) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP            Reports that RCS temperature being maintained in required band.
Step 17, E-3 SRO          CHECK RUPTURED SG(s) PRESSURE - STABLE OR INCREASING BOP                Reports B SG pressure stable.
Step 18. E-3 SRO      CHECK RCS SUBCOOLING BASED ON CETCs - GREATER THAN 50&deg;F [105&deg;F]
BOP                Reports indicated subcooling value.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                      Event No.: 7                Page 51 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 19, E-3 SRO      DEPRESSURIZE RCS TO MINIMIZE BREAK FLOW AND REFILL PRZR:
a) Check normal spray - AVAILABLE
* RCP C AND 1-RC-PCV-1455B - BOTH AVAILABLE OR
* RCPs A and B, AND 1-RC-PCV-1455A - BOTH AVAILABLE RO            Identifies No pressurizer spray available, SRO Goes To Step 20.
Step 20, E-3 SRO      CAUTION:
* The PRT may rupture if a PRZR PORV is used for RCS depressurization.
Rupturing the PRT may result in abnormal containment conditions.
* Cycling of the PRZR PORV should be minimized.
NOTE: The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PRZR level.
DEPRESSURIZE RCS USING PRZR PORV TO MINIMIZE BREAK FLOW AND REFILL PRZR:
a) PRZR PORV - AT LEAST ONE AVAILABLE b) Open one PRZR PORV until ANY of the following conditions satisfied:
(Attachment 4 lists conditions)
* PRZR level - GREATER THAN 69%
OR
* RCS subcooling based on CETCs - LESS THAN 30&deg;F [85&deg;F]
OR
* BOTH of the following exist:
: 1) RCS pressure - LESS THAN RUPTURE SG(s) PRESSURE
: 2) PRZR level - GREATER THAN 22% [50%]
RO                When Attempt Made to open 1-RC-PCV-1455C, PCV will Not Open.
SRO                Transition to ECA-3.3
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                    Page 52 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
ATTACHMENT 10 of 1-E-0
: 1. Check SI is in progress. If SI is not in progress, then return to procedure step in effect.
RO/BOP      RO/BOP identifies that SI is in progress.
ATTACHMENT 10 of 1-E-0 RO/BOP      2. Identify Ruptured SG by one of the following conditions:
* Unexpected rise in any SG Narrow Range level
* High radiation from any SG MS line monitor
* High radiation from any SG Blowdown line With SRO concurrence identifies B SG as the ruptured SG ATTACHMENT 10 of 1-E-0 RO/BOP      3. Check running or start AFW Pumps, as necessary
* 1-FW-P-3A
* 1-FW-P3B
* 1-FW-P-2 ATTACHMENT 10 of 1-E-0 RO/BOP      4. When ruptured SG Narrow Range level is greater than 12%, then isolate feed flow to ruptured SG by closing SG AFW Isolation MOVs:
* SG B, 1-FW-MOV-151C and 1-FW-MOV-151D RO/BOP closes 1-FW-MOV-151C/D when SG level is greater than 12% Narrow Range.
Completion of Critical Task: WOG - A; Isolate feed flow into and steam flow from ruptured SG before a transition is made to ECA-3.1. STOP Time: _________.
ATTACHMENT 10 of 1-E-0 RO/BOP      5. Select the ruptured SG AFW MOVs using the following switches:
* H TRAIN DISABLE SELECTOR SWITCH
* J TRAIN DISABLE SELECTOR SWITCH
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                  Page 53 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
RO/BOP      ATTACHMENT 10 of 1-E-0
: 6. Disable the auto-open signal for the selected MOVs by placing the following keyswitches in the DISABLE SELETED position:
* H TRAIN AUTO OPEN ENABLE SWITCH
* J TRAIN AUTO OPEN ENABLE SWITCH ATTACHMENT 10 of 1-E-0 RO/BOP      CAUTION: At least one SG must be maintained available for RCS heat sink.
: 7. Locally close steam supply valve to the TD AFW pump:
* 1-MS-120 RO/BOP directs field operator to close 1-MS-120.
The field operator will acknowledge the requirement to close 1-MS-120. The field operator will later report that 1-MS-120 is closed.
ATTACHMENT 10 of 1-E-0 RO/BOP      8. Control Feed Flow to the SG IAW the following requirements:
* Minimum AFW flow is 350 gpm with SI initiated, until one SG Narrow Range level is greater than 12%
* When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50%.
* SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
* SG C, 1-FW-MOV-151A and 1-FW-MOV-151B End EVENT #7
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 1                      Event No.: 8                Page 54 of 92 Event
 
== Description:==
1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.
Time        Position                                Applicants Action or Behavior 1-ECA-3.3 Actions SRO      1. CHECK RUPTURED SG(S) NARROW RANGE LEVEL - LESS THAN 75%
[73%]
RO      Reports that B SG Level is greater than 75%.
: 1. RNO - GO TO Step 6 SRO      6. CHECK IF SI CAN BE TERMINATED:
a)  Check RCS subcooling based on CETCs - GREATER THAN 30&deg;F [85&deg;F]
RO/BOP                Identifies that RCS subcooling is greater than 30&deg;F.
b) Check secondary heat sink:
* Total feed flow to SGs - GREATER THAN 350 GPM [450 GPM]
AVAILABLE OR
* Narrow range level in at least one intact SG - GREATER THAN 12%
[18%]
RO/BOP          Identifies A and C SG NR level >12% OR identify >350 gpm flow Available.
c)  Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs                RVLIS INDICATION Running      Full Range          Dynamic Range 0          GREATER THAN 63%
1                              GREATER THAN 36%
2                              GREATER THAN 51%
3                              GREATER THAN 82%
RO/BOP Identify that RVLIS Full Range is Greater than 63%.
d) Check any ruptured SG narrow range level - INCREASING IN AN UNCONTROLLED MANNER OR OFFSCALE HIGH BOP BOP will identify that B SG Level is Off-Scale High.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 1                  Event No.: 8                  Page 55 of 92 Event
 
== Description:==
1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.
SRO      7. STOP ALL BUT ONE CHG PUMP AND PUT IN AUTO RO      Secure one of the running charging pumps SRO      8. ISOLATE HHSI TO COLD LEGS:
a)  Verify the following:
RO              1) CHG pump suctions from RWST - OPEN
* 1-CH-MOV-1115B
* 1-CH-MOV-1115D
: 2) Check CHG pump miniflow recirc valves - OPEN
* 1-CH-MOV-1275A
* 1-CH-MOV-1275B
* 1-CH-MOV-1275C
* 1-CH-MOV-1373 b) Close HHSI to Cold Leg:
* 1-SI-MOV-1867C RO
* 1-SI-MOV-1867D
* 1-SI-MOV-1842 SRO      9. ESTABLISH CHARGING FLOW:
a) Close CHG flow control:
RO
* 1-CH-FCV-1122 a) b) Check CHG line isolation - OPEN
* 1-CH-HCV-1310A c) Open CHG line isolation MOVs RO
* 1-CH-MOV-1289A
* 1-CH-MOV-1289B RO          d) Establish at least 40 gpm charging flow using CHG flow control
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 1                Event No.: 8              Page 56 of 92 Event
 
== Description:==
1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.
SRO      10. CHECK SI FLOW NOT REQUIRED:
* RCS subcooling based on CETCs - GREATER THAN 30&deg;F [85&deg;F]
* Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs                RVLIS INDICATION Running      Full Range      Dynamic Range 0          GREATER THAN 63%
1                            GREATER THAN 36%
2                            GREATER THAN 51%
3                            GREATER THAN 82%
RO          Reports Full Range RVLIS >63%.
END Event 8 End Scenario
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 57 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
ATTACHMENT 1 OF E-0 BOP      1. CHECK FW ISOLATION:
* Feed pump discharge MOVs - CLOSED
* 1-FW-MOV-150A
* 1-FW-MOV-150B
* MFW pumps - TRIPPED
* Feed REG valves - CLOSED
* SG FW bypass flow valves - DEMAND AT ZERO
* SG blowdown TVs - CLOSED BOP      2. CHECK CTMT ISOLATION PHASE I:
* Phase I TVs - CLOSED
* 1-CH-MOV-1381 - CLOSED
* 1-SV-TV-102A - CLOSED
* PAM isolation valves - CLOSED
* 1-DA-TV-103A
* 1-DA-TV-103B BOP will identify 1-DA-TV-100A/B, and 1-MS-TV-109 OPEN and CLOSE them.
BOP      3. CHECK AFW PUMPS RUNNING:
a)  MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                      Event No.: 9                Page 58 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Attachment 1 of E-0 BOP      4. CHECK SI PUMPS RUNNING:
* CHG pumps - RUNNING
* LHSI pumps - RUNNING BOP starts 1-SI-P-1B 1-SI-P-1B START TIME: _____ (for critical task verification, CT-1)
BOP      5. CHECK CHG PUMP AUXILIARIES:
* CHG pump CC pump - RUNNING
* CHG pump SW pump - RUNNING
: 6. CHECK INTAKE CANAL:
BOP
* Level - GREATER THAN 24 FT
* Level - BEING MAINTAINED BY CIRC WATER PUMPS
: 7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:
a)  Check if ANY of the following annunciators - HAVE BEEN LIT
* E-F-10 (High Steam Flow SI)
* B-C-4 (Hi Hi CLS Train A)
BOP
* B-C-5 (Hi Hi CLS Train B)
Identifies annunciators not lit and goes to step 8.
BOP      *8. CHECK IF CS REQUIRED:
a)  CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 9                  Page 59 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Attachment 1 of E-0 BOP      *10. BLOCK LOW PRZR PRESS SI SIGNAL:
a)    Check PRZR pressure - LESS THAN 2000 psig b)  Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c)  Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.
BOP      *11. BLOCK LOW TAVE SI SIGNAL:
Step may not be performed at this time (if Tave is greater than 543&deg;F).
a)  Check RCS Tave - LESS THAN 543&deg;F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c)  Verify Permissive Status light F LIT NOTE:
* CHG pumps should be run in the following order of priority: C, B, A.
* Subsequent SI signals may be reset by re-performing Step 12.
BOP      12. CHECK SI FLOW:
a)  HHSI to cold legs - FLOW INDICATED
* 1-SI-FI-1961 (NQ)
* 1-SI-FI-1962 (NQ)
* 1-SI-FI-1963 (NQ)
* 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c)  Reset SI.
d) Stop one CHG pump and out in AUTO
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 9                      Page 60 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Attachment 1 of E-0 e)  RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:
: 1) Verify reset or reset SI.
: 2) Stop one LHSI pump and put in AUTO.
1-SI-P-1A or 1B STOP TIME: ______
: 3) GO TO Step 13.
Critical Task:    Secure one LHSI pump within 30 minutes of two LHSI pumps in service. [SPS E-1G, CT-1]
Note: If 1-SI-P-1B was not started on Step 4 of Attachment 1, CT becomes Not Applicable.
BOP      13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]
BOP      14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.
BOP      15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next page of this guide)
Depending on timing, this attachment may have already been completed.
BOP      16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Identify failure of 1-VS-MOD-103A CLOSES the MOD.
Unit 2 Operator will state that Unit 2 is at 100% power (if asked)
Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                    Page 61 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Time      Position                              Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 BOP      NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.
ATTACHMENT 2 of 1-E-0 BOP      1. Check opened or open CHG pump suction from RWST MOVs.
* 1-CH-MOV-1115B
* 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 BOP      2. Check closed or close CHG pump suction from VCT MOVs.
* 1-CH-MOV-1115C
* 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 BOP      3. Check running or start at least two CHG pumps. (listed in preferred order)
* 1-CH-P-1C
* 1-CH-P-1B
* 1-CH-P-1A ATTACHMENT 2 of 1-E-0 BOP      4. Check opened or open HHSI to cold legs MOVs.
* 1-SI-MOV-1867C
* 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 BOP      5. Check closed or close CHG line isolation MOVs.
* 1-CH-MOV-1289A
* 1-CH-MOV-1289B
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 62 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
ATTACHMENT 2 of 1-E-0 BOP      6. Check closed or close Letdown orifice isolation valves.
* 1-CH-HCV-1200A
* 1-CH-HCV-1200B
* 1-CH-HCV-1200C RO/BOP will CLOSE 1-CH-HCV-1200A and 1-CH-HCV-1200B ATTACHMENT 2 of 1-E-0 BOP      7. Check opened or open LHSI suction from RWST MOVs.
* 1-SI-MOV-1862A
* 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 BOP      8. Check opened or open LHSI to cold legs MOVs.
* 1-SI-MOV-1864A
* 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 BOP      9. Check running or start at least one LHSI pump.
* 1-SI-P-1A
* 1-SI-P-1B BOP Would have started 1-SI-P-1B as part of attachment 1.
ATTACHMENT 2 of 1-E-0 BOP      10. check High Head SI flow to cold legs indicated.
* 1-SI-FI-1961
* 1-SI-FI-1962
* 1-SI-FI-1963
* 1-SI-FI-1943 or 1-SI-FI-1943A
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                    Page 63 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
ATTACHMENT 2 of 1-E-0 BOP      11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.
* Alternate SI to Cold legs
* Hot leg injection
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 64 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 65 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 66 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                    Page 67 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
If asked, Unit 2 has throttled Chilled Water flow as required by CAUTION prior to Step 10.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 9              Page 68 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
If asked, pressure indicated on PDI-118, 116, 215, and 206 equals the pressure indicated on PDI-100/101/200/201 pressure indicators.
 
Appendix D                              Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 9                      Page 69 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Unit 2 will assume responsibility for this attachment at this point.
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 70 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 71 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 72 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 73 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                  Page 74 of 92 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:
Recall IC -261 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.
Acknowledge AAC System Alarm on Waste Disposal Panel Open the monitor window and add the following points to it:
* asp_ao_off
* MS-120, B Steam Supply to TDAFW Pump Enter the following MALFUNCTIONS:
Trigger Malfunction              Delay  Ramp        Trigger  Value    Final      Type (Auto or Manual)
RC4903 PRZR LEVEL XMTR CH                10      20          1      0.0      -0.2        Manual 3 FAILURE (461)
FW1803 B S/G MN FD FLOW                  10        0          3      0.0        1          Manual XMTR FT-1487 FAILS SD0201 HP HTR DRN PP SD-P-1A            10        0          5    FALSE      TRUE        Manual TRIPS: OVR-CURRENT RC2402 STEAM GENERATOR B                10      60          9      0.0        8          Manual TUBE RUPTURE PCV455C_OPEN PCV-1455C                    0        0          11      OFF        OFF        Manual PRZR RELIEF VALVE OPEN PCV455C_CLOSE PCV-1455C                  0        0          11      OFF        ON          Manual PRZR RELIEF VALVE CLOSE RCMOV535_BKR RC-MOV-535                  0        0          16        1        0          AUTO PORV Block Valve RC5601 RC-P-1A BKR 15A3                  0        0          17    FALSE      TRUE        AUTO SPURIOUS TRIP RC5602 SPURIOUS TRIP RCP 1B              0        0          17    FALSE      TRUE        AUTO RC5603 SPURIOUS TRIP RCP 1C              0        0          17    FALSE      TRUE        AUTO AS02 DISABLE SV-TV-102 OPEN              0        0          30    FALSE      TRUE        ACTIVE AS05 DISABLE SV-TV-103                    0        0          30    FALSE      TRUE        ACTIVE CLOSE SI2409 SI RELAY CI1A FAILS TO            0        0          30    FALSE      TRUE        ACTIVE ACTUATE SI2505 SI RELAY SI5B FAILS TO            0        0          30    FALSE      TRUE        ACTIVE ACTUATE
 
Appendix D                                    Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1                            Scenario No.: 1                                    Page 75 of 92 SIMULATOR OPERATORS GUIDE Enter the following EVENT TRIGGERS:
Trigger#                      EVENT                                          Command Trigger setup to trip 1-RC-MOV1535 breaker when control switch in open to stroke test open time, Event 1.
Trigger 14 sets when 1-RC-MOC-1535 closed. Trigger 15 sets when 1-RC-MOV-1535 control switch taken to open. Trigger 16 set when both Trigger 14 and 15 are TRUE. Trigger 16 implements Remote Function trip of 1-RC-MOV-1535 breaker.
14          "rcmov535 .le. 0.0002"                                    Sets Trigger 14 15          "mov535_open"                                              Sets Trigger 15 16          "et_array(14) .and. et_array(15)"                          Sets Trigger 16 Trigger setup to trip A, B, C, RCPs when Generator Output breakers open. (EL2 Auto Trigger). Actuates Trigger which implements Malfunction RC5601/5602/5603.
17          ".not. (elg102_bkr(2) .and.                                Sets Trigger 17 elg1t240_bkr)"
Trigger setup to override 1-RC-LCV-1460A and B control switch to Open to simulate removing PRZR level control output fuses.
20          "chw180<500.0"                              Set Trigger 20 when Letdown flow < 1 gpm.
21          "chlcv460a_open"                      Set Trigger 21 when 1-CH-LCV-1460A switch taken to Open.
22          "chlcv460b_open"                      Set Trigger 22 when 1-CH-LCV-1460B switch taken to Open.
23          "et_array(20) .and. et_array(21)"      Sets Trigger 23 when Trigger 20 and 21 are ACTIVE.
Actuates override for 1-CH-LCV-1460A switch in Open 24          "et_array(20) .and. et_array(22)"      Sets Trigger 24 when Trigger 20 and 22 are ACTIVE.
Actuates override for 1-CH-LCV-1460B switch in Open Enter the following Remote Functions:
Override                                    Set Condition                        Trigger AAC_SMS_MODE OFF AAC DG                                      OFF                                  30 LOCAL MODE SWITCH POSITION
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                  Page 76 of 92 SIMULATOR OPERATORS GUIDE Enter the following Switch Overrides:
Override                                Set Condition                      Trigger Override CH LCV-460A OPEN                                ON                              23 Override CH LCV 460B OPEN                                ON                              24 TRIGGER                  TYPE                                      DESCRIPTION 1                    MAN            Fails PZR Level CH III to ~34%.
3                    MAN            B SG MN Feed Flow Transmitter fails high.
5                    MAN            Trip running High Pressure Drain Pump Steam Generator Tube Leak, 74 gpm 9                    MAN 11                    MAN            Overrides 1-RC-PCV-1455C control switch Open OFF, Close ON 16                  AUTO            Open Breaker to 1-RC-MOV-1535 17                  AUTO            Spurious Trip A/B/C RCPs when Gen. Output Bkrs open 23                  AUTO            Overrides 1-CH-LCV-1460A control switch Open.
24                  AUTO            Overrides 1-CH-LCV-1460B control switch Open.
AS02 DISABLE SV-TV-102 OPEN AS03 DISABLE SV-TV-103 CLOSE SI2409 SI RELAY CI1A FAILS TO ACTUATE 30                  ACTIVE SI2505 SI RELAY SI5B FAILS TO ACTUATE AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION
 
Appendix D                                Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 1                          Page 77 of 92 SIMULATOR OPERATORS GUIDE Verify the following control room setup:
Place the simulator in RUN and verify normal 100% power operation indications.
Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:
Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).
Verify Ovation System operating.
Reset ICCMs.
Verify Component Switch Flags.
Verify Brass Caps properly placed.
Verify SG PORVs set for 1035 psig.
Verify Rod Control Group Step Counters indicate properly.
Verify Ovation CRT display.
Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)
Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:
AP-53.00            AP-18.00            AP-23.00                    AP-16.00 E-0                                    E-3 (2)                      ECA-3.3 OP-CH-007                                Reactivity Sheet OP-ZZ-002                              PT-18.6I Verify Reactivity Placard is current.
Verify ALL PINK MAGNETS are accounted for.
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 1                                  Page 78 of 92 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.
Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.
If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.
In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.
Assign operating positions.
Ask for and answer questions.
 
Appendix D                            Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 79 of 92 SIMULATOR OPERATORS GUIDE Conduct shift turnover:
The initial conditions have Unit 1 at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance. In accordance with VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
The last shift performed two 35 gallon dilutions followed by a manual makeup for training. A BAST boron concentration is 8.0 w/%.
Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, Pressurizer Block Valve Stroke Test. Performance of PT-18.6I has been authorized and has been PSA analyzed for current plant conditions.
When the team has accepted the shift, proceed to the Session Conduct Section.
 
Appendix D                          Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 80 of 92 SIMULATOR OPERATORS GUIDE Session Conduct:
* Ensure conditions in Simulator Set-up are established.
* Ensure Trigger 30 is active prior to team entering the simulator.
* Verify Exam Security has been established and ASP_AO_OFF = True.
EVENT 1        Test Cycle PORV Block Valves, 1-PT-18.6I BOOTH:
30 minutes prior to the beginning of the scenario, provide the team with a copy of 1-PT-18.6I, Pressurizer Block Valve Stroke Test. The team will pre-brief the PT prior to entering the simulator.
Trigger setup to trip 1-RC-MOV1535 breaker when control switch in open to stroke test open time, Event 1. Monitor the following triggers as 1-RC-MOV-1535 is closed/opened.
Trigger 14 sets (becomes Active) when 1-RC-MOC-1535 closed.
Trigger 15 sets (becomes Active) when 1-RC-MOV-1535 control switch taken to open.
Trigger 16 sets when both Trigger 14 and 15 are TRUE.
Trigger 16 implements Remote Function to trip 1-RC-MOV-1535 breaker.
Operations Supervisor/Management/Work Week Coordinator:
* If contacted, will acknowledge 1-RC-MOV-1535 breaker tripped when the valve was re-opened, suspension of the PT, and Tech Spec Clock identified (1 hour/72 hour).
Field Operator: (3 minute delay from request to answer)
* If Contacted, as Service Building Operator, to check the status of 1-RC-MOV-1535 breaker, 1H1-2S 6A; report that the breaker has tripped (in the trip free position).
 
Appendix D                                Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                Page 81 of 92 SIMULATOR OPERATORS GUIDE EVENT 2          PRZR Level Transmitter 1-RC-LI-1461 Fail to 34%, 0-AP-53.00.
When cued by examiner, implement Trigger #1.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00.
* If contacted, ask for SRO recommendation for performing 1-OP-RP-001, Shift Manager will call back).
* If contacted, will take responsibility for writing the CR.
STA:
* If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge (but not confirm/deny) any TS LCOs.
* If asked, the STA will report that 1-RC-LI-1461 is a Reg. Guide 1.97 component. The STA will also report that review of CEP 99-0029 has been discussed with the Shift Manager.
* If asked, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Field Operators:
Maintenance/Work Week Coordinator:
* If contacted, will acknowledge instrumentation failure and commence investigations and/or efforts to place the channel in trip.
Unit 2 Operator:
* No action for this event.
Role play as other individuals as needed.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                Page 82 of 92 SIMULATOR OPERATORS GUIDE EVENT 3          Feed Flow Channel Fails High, 0-AP-53.00.
When cued by examiner, implement Trigger #3.
Operations Supervisor/Management:
* If contacted, acknowledge feed flow channel failure. The individual(s) contacted will also acknowledge any TS LCOs.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into AP-53.00.
* If contacted, will ask SRO for recommendation concerning performance 1-OP-RP-001. Shift Manager will call back.
STA:
* If contacted, will acknowledge feed flow channel failure. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
* If contacted, will take responsibility for writing the CR.
* When asked: Failed channel is a RG 1.97 variable.
* When asked, CEP-0029 has been reviewed and discussed with the Shift Manager. VPAP-2802 and TRM section 3.3 have been reviewed and discussed with the Shift Manager.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Field Operators:
* Will perform actions as directed.
Maintenance/ Work Week Coordinator:
* If contacted, will acknowledge the feed flow channel failure and contact I&C to commence preparation to place the failed channel in trip.
Unit 2:
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                Page 83 of 92 SIMULATOR OPERATORS GUIDE
* If contacted, will acknowledge the failure of the feed flow channel.
Role-play as other individuals as needed.
EVENT 4          Loss of HPD, 1-AP-18.00.
When the Evaluator indicates Ready, Activate Trigger #5.
Operations Supervisor/Management:
* If contacted, will acknowledge the trip of 1-SD-P-1A, and the need to ramp at 1%/minute to 75%
power.
* If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC, the Shift Manager will direct a 1%/minute ramp rate.
STA:
* If contacted, will acknowledge the trip of 1-SD P-1A and the need to ramp at 1%/minute to 75%
power.
* If asked, the STA will acknowledge the need to borate and use rods (will acknowledge the team review of pre-planned reactivity plans and OP-RX-010, if performed). If asked to perform the OP-RX-010 review, the STA will state that he is not able to at this time.
* After directed, the STA will report that VPAP-2802 has reviewed and discussed with the hift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
* When contacted: EPIPs have been reviewed with the Shift Manager.
Maintenance/ Work Week Coordinator:
* If contacted, will acknowledge the failure and notify electrical maintenance to investigate.
 
Appendix D                            Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 1                                  Page 84 of 92 SIMULATOR OPERATORS GUIDE
* If contacted, will acknowledge the requirements to reduce reactor power.
Field Operators: (Wait three (3) minutes from direction of a local action to the report of local condition found.)
* If contacted, the condensate polishing building operator will acknowledge the need to ramp the unit.
* If asked, the condensate polishing building operator acknowledge bypass of the polisher.
* When contacted, as the Service Building Operator concerning the status of 1-SD-P-1A power supply breaker, 1-EP-BKR-15B6, report that the breaker is open with a timed overcurrent drop on A phase.
* When contacted, as the Turbine Building Operator to check the status of 1-SD-P-1A, report that there are no apparent abnormalities other than the A HPD pump has tripped and HPD tank high level divert, 1-SD-FCV-107, is diverting to the condenser.
Unit 2:
* If contacted, will acknowledge the trip of 1-SD-P-1A and the need to ramp at 1%/minute to 75%
power.
Role-play as other individuals as needed.
 
Appendix D                            Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 85 of 92 SIMULATOR OPERATORS GUIDE EVENT 5        Ramp to 75%, 0-AP-23.00.
Operations Supervisor/Management:
* If contacted, will acknowledge Ramp to 75% required due to the loss of 1-SD-P-1A.
* If contacted, will take responsibility for writing the CR.
* When contacted: The Shift Manager will review EPIPs for applicability. They are not applicable.
STA:
* If contacted, will acknowledge the impending ramp to 75% power.
* If contacted, will take responsibility for writing the WR and CR.
* When contacted: The STA reports that VPAP-2802 has been reviewed discussed with the Shift manager.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them. STA will acknowledge reactivity plan developed by RO/SRO.
Unit 2 Operator:
* If notified of Ramp: Acknowledge ramp of Unit 1.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 86 of 92 SIMULATOR OPERATORS GUIDE EVENT 6          SGTL 74 gpm, A/E RM Auto Actions Fail, RCPs Trip on swap to RSST.
When the Evaluator is ready and the Blender is in AUTO, implement Trigger # 9.
Note: It would be preferable to wait until power is <80% to implement this failure to allow for ramp stabilization prior to creating RCS leak to allow the team to assess leakrate with more precision.
Operations Supervisor/Management:
* If contacted, will acknowledge RCS leakage into the B SG. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into AP-16.00.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
 
Appendix D                          Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                Scenario No.: 1                                  Page 87 of 92 SIMULATOR OPERATORS GUIDE STA:
* If contacted, will acknowledge the RCS leakage into the B SG.
* If asked to calculate the RCS leak rate, state that it is difficult to ascertain at this time, but you will continue to monitor as time permits.
* If contacted, will take responsibility for writing the WR and CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
Health Physics:
* If contacted, will acknowledge B SGTL.
Role play as other individuals as needed.
Operations Supervisor/Management:
* If contacted, will acknowledge entry into 1-E-0, ES-0.1. AP-24.01.
* If contacted, will acknowledge the SGTR on B SG.
* If contacted, will acknowledge the isolation of B SG (if informed).
Field Operators:
* If contacted, to report abnormalities on RCPs, report no 86 devices drops apparent on RCP breakers, but the Speed Sensing Panel appears to be malfunctioning; lights blinking on and off.
 
Appendix D                            Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 88 of 92 SIMULATOR OPERATORS GUIDE EVENT 7                SGTL becomes SGTR (710) gpm). 0-AP-16.00, E-0, E-3.
Notify Examiner when B SG NR level reaches 12%. To increase SGTL to SGTR, double click on RC2402, set DEG at 79%, 60 sec ramp, Insert.
After the SGTR implemented, Actuate Trigger 11 to fail PORV 1455C control switch.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will acknowledge entry into 1-E-0, 1-E-3.
* If contacted, will acknowledge the SGTR on B SG.
* If contacted, will acknowledge the isolation of B SG (if informed).
STA:
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
Unit Two:
* If asked, blowdown and air ejector RM readings are [as indicated at the time].
* If requested, acknowledge RM alarms, and perform ARP actions.
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
* If asked: Unit 2 RWST cross-ties are open.
* If asked: take responsibility to notify HP of B SG PORV lifting.
Field Operators:
* If contacted, field operators will perform valve manipulations as required:
* 1-MS-120 - set ms_120 to zero upon request
 
Appendix D                            Required Operator Actions                  Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                      Page 89 of 92 SIMULATOR OPERATORS GUIDE
* Acknowledge direction to place Number 1 and 2 Turbine Building Sump pumps in OFF locally, and initiate 0-OSP-PL-003, Turbine Building Sump Pump Status Verification.
 
Appendix D                          Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 90 of 92 SIMULATOR OPERATORS GUIDE EVENT 8                PZR PORV 1-RC-PCV-1455C not open, 1-ECA-3.3.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will acknowledge entry into 1-ECA-3.3.
* If contacted, will acknowledge the SGTR on B SG.
* If contacted, will acknowledge the isolation of B SG (if informed).
STA:
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
Unit Two:
* If asked, blowdown and air ejector RM readings are [as indicated at the time].
* If requested, acknowledge RM alarms, and perform ARP actions.
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
Field Operators:
* If contacted, field operators will perform vale manipulations as required:
* 1-MS-120 - set ms_120 to zero upon request
 
Appendix D                          Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                        Page 91 of 92 SIMULATOR OPERATORS GUIDE EVENT 9                BOP Failures, 1-SI-P-1B no auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
Unit Two:
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
* If asked, MRC differential pressure is a found.
* If asked, Unit 2 has throttled Chilled Water flow IAW E-0, Attachment 3 guidance.
Field Operators:
* If contacted, field operators will perform valve manipulations as required.
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                                Page 92 of 92 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:
* If contacted, will acknowledge the failures and commence investigations.
HP:
* If contacted, will acknowledge B SGTR.
STA:
* If asked, will report that he will calculate the time to B fill, time permitting.
* If contacted, will enter the control room and commence reviewing status trees and prepare for the transient brief (items are reported as you see them or previously reported).
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. Radiological conditions are as indicated. He will also state that containment conditions and the electrical conditions are as you see them.
Role play as other individuals as needed.
The scenario will end upon reaching Step 11 of 1-ECA-3.3 or at the lead examiners discretion.
 
Appendix D                                              Scenario Outline                                      Form ES-D-1 NRC EXAM - SCENARIO #3 Facility: Surry Power Station                    Scenario No.: 3                          Op-Test No.: 2014-001 Examiners: ____________________________ Operators:                              _____________________________
Initial Conditions: Time in Core Life - Middle of Life; Core Cycle - Cycle 26 Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportablility is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
Event            Malf.      Event                                              Event No.            No.        Type*                                          Description N - BOP 1                    N/A        N - SRO        Deleted.
2                RC0801,            I - RO      Failure of Median Tave in the Low Direction, AP-53.00.
                  -1 Deg 3                                I - BOP MS0801, TS - SRO Failure of Steam Flow Channel III Low, A SG. AP-53.00
                  -1 Deg C - RO 4                EL4902 TS - SRO      1J 4160V emergency Bus Off-site Power Supply Breaker Trips.
Switch                        Test Button on Main Turbine Control Fails causing the LP Turbine 5                                R - RO O/R, TEST_IR R - SRO        1 Intercept and Reheat Stop Valve Closure. AP-23.00 Ramp to N - BOP      71% Power.
L_IIL RC04,                        RCS leak of 35 gpm. AP-16.00.
6              3.5% Deg          C - RO TS- SRO RM0202, 7                +.1 Deg, RM0201,        C - BOP        Containment Particulate and Gas RM auto actions on High Alarm
                  +.1 Deg                      fail to function CA03 CA04 RC0101, 8                .6% Deg M - All      SBLOCA. AP-16.00, E-0.
 
Appendix D                                    Scenario Outline                                  Form ES-D-1 NRC EXAM - SCENARIO #3 SETPT 9          for Hi-Hi CLS change to 60 psia.
O/R          M - All CLS_AC Hi and HI-HI CLS fail to function, requiring manual alignments of T_TRA        C - BOP        components, and FR-Z.1 entry.
O/R CLS_AC T_TRB
*      (N)ormal,    (R)eactivity,  (I)nstrument,  (C)omponent,    (M)ajor
: 1) Deleted Normal Evolution.
Event #2: Median Tave Fails Low. (I - RO)
The RO will diagnose this failure due to Rod motion and alarms received. The RO will place Rod Control to manual and place charging flow to manual IAW the Immediate Actions Steps of 0-AP-53.00, Loss of Vital Instrumentation/Controls. Following a short brief, the Team will complete AP-53.00.
Verifiable Actions:
: 1) RO/BOP will place Rod Control in manual to stop outward rod motion.
: 2) RO will place charging flow in manual and maintain Pressurizer level at program.
Technical Specifications:
: 1) Should the SRO review Tech Specs, no items will be found.
Technical Requirements Manual/RG 1.97
: 1) No TRM or RG 1.97 requirements are associated with this failure.
Event #3: Steam Flow Channel III Fails Low on A SG. (I - RO, TS-SRO)
The BOP will diagnose the failure based upon alarms and indications received, place the A FRV in manual to control A SG NR level, and restore SG NR level to program IAW 0-AP-53.00, Loss of Vital Instrumentation/Controls.
The affected channel of Steam Flow will be de-selected and the A FRV returned to automatic.
Verifiable Actions:
: 1) The BOP will place the A FRV in manual and restore the A SG NR level to program.
: 2) The RO will de-select the failed channel.
: 3) The BOP will return the A FRV to automatic.
Technical Specifications:
SRO will Review Technical Specifications and determine:
: 1) Tech Spec Table 3.7-1, Item 17, Operator Action 6. With the Number of Operable Channels less than the Total Number of channels, Operation may continue provided the channel is placed in trip within 72 hours, The channel may
 
Appendix D                                  Scenario Outline                                  Form ES-D-1 NRC EXAM - SCENARIO #3 be bypassed for 12 for surveillance testing, and if the requirement cannot be met be in at least Hot Shutdown in 6 hours.
: 2) Tech Spec Table 3.7-2, Item 1.e. High Steam flow in 2/3 steam lines coincident with Low Tavg or low steam line pressure, Operator Action 20. With the number of Operable channels less than the Total number of channels, Operation may continue provided the channel is placed in trip within 72 hours, the channel may be bypassed for surveillance for 12 hours. If these conditions are not satisfied in the time permitted, be in Hot Shutdown in the next 6 hours and reduce RCS temperature and pressure to < 350&deg;F/450 psig in the following 12 hours.
: 3) Tech Spec Table 3.7-3, Item 2a, Steam line Isolation, refers to requirements listed in 2) above.
Technical Requirements Manual/R.G. 1.97.
: 1) TRM - No requirements listed for this failure in section 3.3.2, Appendix R Instrumentation.
: 2) RG 1.97 - Attachment 1, D-19 Variable, 1 Channel per SG required.
Event #4: Loss of 1J 4160V Emergency Bus, Breaker 15J8 opens, #3 EDG Starts and Loads on 1J Bus. (C - RO, TS - SRO).
The Team will diagnose the loss of the 1J Emergency Bus and Start and Load of #3EDG on the bus based on alarms and indications received. The SRO will enter 1-AP-10.07, Loss of Unit 1 Power and proceed through the procedure until the end is reached.
Verifiable Actions:
: 1) BOP/RO will start the B CH pump to provide load to the #3EDG.
: 2) BOP/RO will secure the A and C CH pumps.
: 3) RO will place the B CC pump in PTL in order to re-close the J stub bus tie breaker.
: 4) RO will start A CC pump.
Technical Specifications:
: 1)      The SRO will consult Tech Specs 3.16.B.2 and determine the Unit may be operated for 7 days provided the dependable alternate source can be OPERABLE within 8 hours. SRO will consult with the Shift Manager concerning whether the Dependable alternate source can be Operable within 8 hours.
: 2)      SRO may refer to Tech Spec 3.6.I and determine AFW cross-tie clock is not required.
: 3)      SRO will identify 6/30 clock Tech Spec 3.16, while the alignment of running charging pumps is made using 1-AP-10.07, Attachment 4.
Technical Requirements Manual / RG 1.97:
: 1)      No TRM or RG 1.97 requirements are affected by this event. (The identification of TRM items is normally an STA function - follow-up question post-scenario is recommended at Lead Evaluator discretion.)
Event #5: #1 LP Turbine Left Intercept and Reheat Stop Valve Close, (R - RO, R - SRO, N -
BOP)
The RO/BOP will diagnose this failure based Indications received. The Team will initiate AP-53.00/AP-38.00 and determine that a power reduction to 71% is required using 0-AP-23.00, Rapid Load Reduction.
Verifiable Actions:
 
Appendix D                                  Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #3
: 1) RO will manipulate the CVCS system to Emergency Borate and establish a continuous boration to control RCS Tave during the Turbine Ramp.
: 2) RO will use control rods to adjust delta flux and assist in RCS Tave control.
: 3) BOP will operate Turbine controls to reduce turbine load.
Technical Specifications/TRM/RG-1.97:
: 1) None associated with this Failure.
Event #6: RCS leak of 35 gpm. (C - RO, TS-SRO)
Following completion of the ramp, the RCS leak will be initiated. The RO will perform 1-AP-16.00, Excessive RCS Leakage, Immediate Actions to quantify the leakage.
Verifiable Actions:
: 1) The RO will isolate letdown and control charging flow in manual to quantify RCS leakage.
Technical Specifications:
: 1) The SRO should consult Tech Specs Section 3.1.C, RCS leakage, and identify that RCS leakage is in excess of the allowed maximum and enter a second 6/30 clock to be in HSD/CSD.
Event #7: Failure of RM-159/160 auto actions. (C - BOP)
As the Team is responding to the RCS leak, RM-159/160 for containment Particulate and Gas Rad Monitors will alarm. The BOP will respond using the associated ARPs and determine that the auto functions for these RMs have not occurred. The BOP will follow the ARP guidance and swap containment Instrument Air compressor suction to the external source.
Verifiable Actions:
: 1) The BOP will swap containment instrument air compressors to outside suction by closing 1-IA-TV-101A and 1-IA-TV-101B.
Technical Specifications:
: 1) The SRO may consult Tech Specs and find no requirement for this failure.
Event #8: SBLOCA. (M - ALL)
The RO will diagnose the increase in RCS leakage due to the alarms and indications received, and re-perform the Immediate Actions of 1-AP-16.00. When leakage is determined to be greater than the capacity of a single CH pump, The RO will trip the reactor, perform the Immediate Actions of E-0, and manually safety inject on Step 4.
Due to the size of the RCS leak, several minutes will elapse before RCP trip criteria are met following the reactor trip.
Verifiable Actions:
: 1) RO will raise charging flow and determine leakage is beyond the capacity of single charging pump.
: 2) RO will trip the reactor and perform the Immediate Action Steps of E-0, including manual Safety Injection actuation.
Critical Task:
CT-1: WOG E-1C: Trip all RCPs so that CET temperatures do not become superheated when forced circulation in RCS stops; Trip all
 
Appendix D                                    Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #3 RCPs within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).
Event #9: Failure of Hi and Hi-Hi CLS auto and manual actuation The RO and SRO will continue with E-0 actions; the BOP will be assigned to perform Attachments 1, 2, and 3 of E-0. Upon transition to 1-E-1, Loss of Reactor or Secondary Coolant, containment pressure will have increased to the Hi and HI-HI CLS setpoint (~13 minutes following Event initiation), and CLS Train A and Train B pushbuttons overridden OFF will force entry into FR-Z.1 to start Containment Depressurization equipment.
Verifiable Actions:
: 1) BOP will reset SI, block SI signals when conditions permit, secure one of the three running CH pumps, and secure one of the two running LHSI pumps.
: 2) RO will throttle AFW to the SGs as directed in E-0.
: 3) RO will operate the CS pumps and valves to align CS to containment for depressurization in FR-Z.1, Response to High Containment Pressure.
: 4) BOP will continue manual alignment of valves for Hi and Hi-Hi CLS failure in Attachment 4 of E-0 following transition from FR-Z.1 to 1-E-1.
Critical Task:
CT-2: WOG E-0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (red-path) challenge develops to the CSF. Establish CS flow from at least one CS pump before containment pressure exceeds 60 psia AND at least one RS train before RMT.
Scenario should continue until Lead Evaluator Cue or Step 18 of 1-E-1.
Follow-up Classification: Site Area Emergency FS-1.1.
 
Appendix D                                              Scenario Outline                                        Form ES-D-1 NRC EXAM - SCENARIO #3 Initial Conditions: IC #1 100%, MOL - Cycle 26. The unit has been at 100% power for > 30 days Pre-load malfunctions: (Trigger 30s) o    Override Hi CLS Act pushbutton - TRA o    Override HI CLS Act pushbutton - TRB o    AC_SMS_MODE, OFF, AAC DG LOCAL MODE SWITCH POSITION o    RS0901, TRN A HI CLS FAILS TO ACTIVATE o    RS0902, TRN B HI CLS FAILS TO ACTIVATE Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:
. Unit 1 is at 100% power. All systems and crossties are operable with the following exception:
o AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Turnover:
Unit 1 is at 100% power. All systems and crossties are operable with the following exception:
AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. . IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* Unit boron 760 PPM.
* A BAST 8.0 w/%.
Event        Malf. #s        Severity                          Instructor Notes and Required Feedback 1                N/A                      Deleted 2            RC0801            -1 Deg    Failure of Median Tave in the Low Direction, AP-53.00.
3            MS0801            -1 Deg    Failure of Steam Flow Channel III Low, A SG. AP-53.00 4            EL4902            TRUE      1J 4160V emergency Bus Off-site Power Supply Breaker Trips.
Switch 5                O/R,                    Test Button on Main Turbine Control Fails causing the LP Turbine 1 ON TEST_IRL                    Intercept and Reheat Stop Valve Closure. AP-23.00 Ramp to 71% Power.
_IIL 6                                3.5%
RC04 Deg    RCS leak of 35 gpm. AP-16.00.
RM0202          +.1 Deg
: 7.            RM0201,          +.1 Deg    Containment Particulate and Gas RM auto actions on High Alarm fail to CA03            TRUE      function.
CA04            TRUE
                              .6 DEG, 8            RC0101          600 Sec    SBLOCA Ramp
 
Appendix D                              Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #3 SETPT for 9      Hi-Hi CLS  60 psia O/R CLS_ACT    ACTIVE
_TRA                Hi and HI-HI CLS fail to function, requiring manual alignments of components, and FR-Z.1 entry.
O/R CLS_ACT    ACTIVE
_TRB Scenario Objectives:
A. Deleted.
B. Given a failure of Median Tave in the Low Direction, respond IAW AP-53.00.
C. Given a failure of the selected Steam Flow channel on the A SG, respond IAW AP-53.00 to take manual control of the A FRV, control A SG NR level and return the A FRV to automatic.
D. Given the trip of the off-site power supply breaker to the 1J 4160V Bus and the subsequent start and load of #3 EDG on the bus, respond IAW AP-10.07 to restart/verify proper loads on the 1J bus.
E. Given the malfunction of the 1RL/1LL test pushbutton, respond IAW AP-53.00, AP-38.00, and AP-23.00 to ramp the Unit to 71 % power.
F. Given an RCS leak of 35 gpm, respond IAW AP-16.00 to quantify the leakrate.
G. Given a containment Gas High RM Alarm, respond IAW ARP to verify/perform the associated automatic actions.
H. Given a SBLOCA inside containment with the failure of Hi-Hi-CLS to actuate, respond IAW E-0 and E-1 to respond to the RCS transient; and restore containment depressurization equipment IAW FR-Z.1.
 
SHIFT TURNOVER INFORMATION OPERATING PLAN:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
Shift orders are to maintain 100% power on Unit #1.
The last shift performed two 35 gallon alt dilutions followed by a manual makeup for training.
A BAST at 8.0 W/%. .
 
Appendix D                              Required Operator Actions              Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3              Event No.: 1      Page 9 of 103 Event
 
== Description:==
Swap Running EH Pumps, 1-OP-EH-001, Section 5.6.
Cue: When team ready.
Time        Position                            Applicants Action or Behavior EVENT #1 DELETED.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                    Event No.: 2                  Page 10 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
Note:  An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.
The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.
A facility representative will be present for consultation with the Evaluation Team, as needed.
Time        Position                                  Applicants Action or Behavior Diagnoses failure of median Tave with the following indications/alarms:
Team Alarms:
* 1H-C4, LOW TAVE FW CONTROL
* 1H-A4, T AVG > < T REF DEVIATION
* 1G-F8, ROD BANK D WITHDRAW
* 1C-C8, PRZR HIGH LEVEL HEATERS ON Indications:
* Median Tave (recorder and indicator) off-scale low
* Individual Loop Taves indicating NORMAL
* Control Rods stepping OUT and reactor power decreasing SRO          Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS RO          [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL RO identifies individual loop Tave indications are normal
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                      Event No.: 2                  Page 11 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
RO        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION RO takes manual control of the control rods to stop the outward rod motion and also takes manual control of pressurizer level control (1-CH-FCV-1122) to maintain pressurizer level at program.
It should be noted that charging might not be placed in manual until procedurally directed.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
SRO Directs BOP to perform Annunciator Response Procedure 1G-F8.
Completes Brief and continues with AP-53.00.
NOTE: 1G-F8 response located at the end of this section.
SRO        *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO              Identify that reactor power is less than 100%.
SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
* Median Tave, Step 9 RO        Identify that Median Tave has failed LOW.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 2                      Page 12 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
SRO        Caution prior to step 9:
CAUTION: Delta flux must be monitored and maintained within band if rods have moved.
Note Prior to Step 9:
NOTE: Depending on the instrumentation failure, the TAVE input to the Steam Dumps may be invalid, causing the Steam Dumps to stay open longer or never open at all.
SRO        9. CHECK LOOP/MEDIAN T/Tave - NORMAL a)  Median Tave - NORMAL a)  RNO - Do the following:
: 1) Place ROD CONT MODE SEL switch in MANUAL, as required.
RO will report that Rod Control is already in manual.
: 2) Take manual control of charging, as necessary to maintain pressurizer level at program.
RO will report that charging flow is in manual or will place charging flow in manual.
: 3) Refer to Attachment 4 (Describes Tave control system)
: 4) If no other instrumentation failure exists, then go to step 13.
Goes to Step 13 0-AP-53.00 SRO        13.      CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001 RO        Checks 1-OPT-RX-001, Attachment 4, and determines that the Calorimetric program is unaffected.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                    Event No.: 2                  Page 13 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE SRO directs STA to review Reg. Guide 1.97. The STA will report that Median Tave is not a Reg. Guide 1.97 component.
: 13.      RNO - GO TO Step 16 SRO        16. Review the following:
* TS 3.7
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA reports that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
SRO        17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS RO        Reports no other instrument failure exists.
GOES TO STEP 19 SRO        19. PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C
                          - END -
Note: If Control Rods stepped out greater than 230 steps, the team will perform ARP 1G-F8. 1G-F8 Actions are contained on the next two pages
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                    Event No.: 2                Page 14 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
1G-F8 (Rod Bank D Withdrawal)
BOP        1. CHECK ALARM - ROD DEMAND POSITION GREATER THAN OR EQUAL TO 228 STEPS ON CONTROL BANK D - GP 1 DEMAND POSITION.
Identifies that Bank D is greater than 230 steps.
1G-F8 (Rod Bank D Withdrawal)
BOP
: 2. PUT ROD CONTROL MODE SEL SWITCH IN MANUAL.
Verifies that Rod Control is in Manual.
1G-F8 (Rod Bank D Withdrawal)
BOP
: 3. VERIFY ROD MOTION - STOPPED 1G-F8 (Rod Bank D Withdrawal)
: 4. CHECK BOTH CONTROL BANK D STEP COUNTERS - LESS THAN OR EQUAL TO 230 STEPS.
If less than 230 steps proceed to Step 5.
RNO -
a)  Step rods out to make both Bank D Step Counters equal. (Group step counters must be equalized by stepping out only, to prevent Rod Group Sequence Error).
Steps Rods out as needed to equalize group step counters.
b)  Reset Bank D Step Counters to 230 steps.
Uses a stylus to reset the Bank D Step Counters to 230 steps.
1G-F8 (Rod Bank D Withdrawal)
BOP NOTE:
Rods may have to be stepped in as many as two steps below the fully withdrawn position to clear Annunciator 1G-F8.
: 5. STEP CONTROL BANK D RODS IN AS NECESSARY TO CLEAR 1G-F8, ROD BANK D WITHDRAW.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 2                  Page 15 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
BOP        1G-F8 (Rod Bank D Withdrawal)
: 6. POSITION CONTROL BANK D RODS AS DETERMINED BY SHIFT SUPERVISION 1G-F8 (Rod Bank D Withdrawal)
BOP NOTE:
Both group step counters for Control Bank D should be the same before performing Step 7.
: 7. LOCALLY CHECK THE BANK OVERLAP COUNTER - AT 384 PLUS CURRENT CONTROL BANK D DEMAND POSITION.
Contacts a field operator to determine the bank overlap counter.
384 + 228 = 612 Field operator will report bank overlap position as indicated on the simulator.
1G-F8 (Rod Bank D Withdrawal)
BOP
: 8. NOTIFY SHIFT SUPERVISION END OF EVENT 2
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 3                  Page 16 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior Diagnoses failure 1-MS-FT-1474 with the following indications/alarms:
BOP Alarms:
* 1H-E5 STM GEN 1A FW >< STM FLOW
* 1F-D7 STM GEN 1A CH 4 FW < STM FLOW
* 1H-G5 STM GEN 1A LVL ERROR.
Indications:
* Step decrease in 1A SG Steam Flow indication CH-III
* Decreasing level on A SG.
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS BOP        [1] VERIFY REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL BOP identifies Channel IV indication for steam flow is NORMAL.
BOP        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of A SG feed reg valve and increases demand (FF >
SF) to restore level to program.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 3                  Page 17 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
SRO        *3        VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO        Identify that reactor power is less than 100%.
Note:    Based on the feed flow > steam flow mismatch established by the BOP, Calorimetric power may exceed 100% during restoration of A SG NR level to program.
SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
SG Steam Flow, Step 7 BOP            States A Steam Flow affected.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 3                  Page 18 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.
SRO        7. CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS -
NORMAL
* Steam Pressure BOP
* Steam Flow
* Feed Flow
* Steam Generator Level Determines CH III Steam flow instrumentation for A SG is NOT normal.
BOP Step 7. RNO IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level BOP        Control system has failed, THEN do the following:
a)  Place the associated Feed Reg Valve in MANUAL.
RO        Verifies A SG MFRV controller, 1-FW-FCV-1478, in manual b) Control SG level at program level (44%, a band will be given).
BOP        Verifies A SG NR level is returning to program level.
c) Select the redundant channel for affected SG(s)
RO        Selects Channel IV Steam Flow for A SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV).
d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.
BOP        Places A SG FRV controller, 1-FW-FCV-1478, in automatic control
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                      Event No.: 3                  Page 19 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
SRO        Step 7. RNO (Continued)
Perform follow-up actions:
a)  Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.
b) Refer to the following Tech Spec 3.7 items:
* Table 3.7-1, 12 and 17
* Table 3.7-2, 1.c, 1.e, and 3.a
* Table 3.7-3, 2.a, and 3.a Determines Table 3.7-1 item 17, 3.7-2 item 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours).
c)  Refer to Attachment 1.
d) IF no other instrumentation failure exists, THEN GO TO Step 13.
SRO        13. Review OPT-RX-001, Rx Power Calorimetric using PCS computer program, Attachment 4, to determine operability of calorimetric and need to perform OPT-RX-007, Shift Average Power Calculation.
SRO/RO determines that OPT-RX-001 is NOT impacted and OPT-RX-007 will NOT need to be performed.
If it appears that the SRO/RO will take action to perform 1-OPT-RX-007, the Unit 2 Operator will state that he will perform 1-OPT-RX-007.
Note: Lead Evaluator must concur with Unit 2 action to perform 1-OPT-RX-007.
SRO        14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 14 if not Reg. Guide 1.97)
SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-MS-FT-1474 is a Reg. Guide 1.97 component.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 3                    Page 20 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
SRO        15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report review of CEP 99-0029 is complete and has been reviewed with the Shift Manager.
[CEP 99-0029 requires one channel of steam flow indication per SG, with channel available, no further action is required.]
SRO        16. Review the following:
* TS 3.7 Determines Table 3.7-1 item 17, 3.7-2 item 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours).
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
SRO        17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS BOP        Reports no additional failure exists SRO        GOES TO Step 19 SRO        19. PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C
                          - END EVENT        #3
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 3                    Event No.: 4                  Page 21 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Time        Position                                  Applicants Action or Behavior 1-AP-10.07 TEAM        Diagnose the failure based on the following:
Alarms:
1K-B8, UPS SYSTEM 1B TROUBLE 1K-D5, CC PP 1B IN LOCAL CONTROL OR OL TRIP 1K-E7, CC PPS DISCH HDR LO PRESS 1B-G5, INST AIR DRYER TROUBLE Indications:
                              #3 EDG Start and Load on 1J 4160 V Bus.
1-CC-P-1B GREEN and AMBER Breaker Indication Lights LIT.
1-AP-10.07 SRO        SRO will hold a Transient Brief and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
Directs the BOP to review ARPs for Lit annunciators, SRO/RO will continue with 1-AP-10.07.
Directs RO/BOP to contact Service Building Operator to check local status of Breaker 15 J8.
Completes Brief and continues with AP-10.07.
Step 1, 1-AP-10.07 SRO        NOTE:
* If both units are affected, local actions should be coordinated.
* The AAC Diesel Generator will automatically start if an undervoltage occurs on Transfer Buses D and F.
* With Degraded Voltage or Undervoltage on 2J Bus, or a loss of Unit 2B DC Bus, Breaker 15J3 will not close automatically, except with a valid Unit 1 SI signal.
* EPIPs may be applicable.
: 1.        CHECK UNIT - BLACKOUT HAS OCCURRED
* Transfer Buses D and F - DEENERGIZED AND
* All Station Service Buses - DEENERGIZED RO            Reports Blackout has not occurred.
SRO        GOES TO Step 39.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                  Page 22 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 39, 1-AP-10.07 SRO        39      CHECK THE FOLLOWING BREAKERS - ANY OPEN:
* 15D1 OR
* 15F1 OR
* 15H8 OR
* 15J8 RO            Reports Breaker 15J8 Open.
Step 40, 1-AP-10.07 SRO        40      CHECK 4160V EMERGENCY BUSES - BOTH ENERGIZED RO            Reports both Emergency Buses Energized.
Step 41, 1-AP-10.07 SRO        41      CHECK SI OR HI HI CLS - NOT ACTUATED RO        Reports SI or HI HI CLS NOT Actuated Step 42, 1-AP-10.07 SRO CAUTION:        To prevent overload of EDG 1, the UV trip of 1-CH-P-1A should NOT be reset if 1-CH-P-1C is running on the normal feeder AND the UV trip of 1-CH-P-1C (Normal) should NOT be reset if 1-CH-P-1A is running.
NOTE: A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading..
NOTE: The CHG pumps powered from the 1H Bus receive an auto-start signal when the 1J Bus is deenergized.
42        INITIATE ATTACHMENT 4 TO ALIGN EMERGENCY BUS LOADS TO PREVENT EDG OVERLOADING SRO            Directs BOP to perform Attachment 4 of 1-AP-10.07.
Note: Attachment 4 actions listed at the end of this section.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                  Page 23 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 43, 1-AP-10.07 SRO        43      GO TO STEP 45 Step 45, 1-AP-10.07 SRO        NOTE: At least one method of communications should be established before commencing local actions.
45      CHECK COMMUNICATIONS CAPABILITY:
* Gaitronics OR
* Station Radios RO            Reports Gaitronics and / or Station Radios Available.
Step 46, 1-AP-10.07 SRO        46      CHECK EDG - HAS REENERGIZED AFFECTED EMERGENCY BUS
* 15H3 - CLOSED OR
* 15J3 - CLOSED RO            Reports 15J3 Breaker closed.
Step 47, 1-AP-10.07 SRO        47      RESTORE EMERGENCY BUS STUB BUS:
a) Put CC PUMP control switch in PTL RO            Places 1-CC-P-1B control switch in PTL.
b) Put RHR PUMP control switch in PTL RO            Checks 1-RH-P-1B in PTL.
c) Locally close Stub Bus feeder breakers on energized Emergency Buses
* 15J9 OR
* 15H9 SRO            Directs RO to contact Service Building Operator to Close 15J9.
RO            Contacts Service Building Operator to Close breaker 15J9 When local report of Breaker 15J9 closed, RO holds Focus Brief to inform the Team, and checks Annunciator 1K-H4 Clear.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 3                  Event No.: 4                  Page 24 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 48, 1-AP-10.07 SRO        CAUTION:
* When the EDG is the only source of power to an Emergency Bus, the associated Component Cooling Pump should NOT be in service if a HI-HI CLS is in progress.
* Restrictions on CC pump operation do NOT apply below RCS temperature of 350&deg;F.
48        CHECK CC PUMPS - AT LEAST ONE RUNNING RO            Reports No CC Pumps running on Unit 1.
SRO            Holds Team brief to discuss the start of 1-CC-P-1A. Since CC system is cross-tied and the CC header is pressurized, throttling the CC pump discharge valve prior to start is unnecessary. Team will concur and the brief closed.
SRO            Direct RO to Start 1-CC-P-1A.
RO            Makes Gaitronics Announcement and Starts 1-CC-P-1A.
Step 49, 1-AP-10.07 SRO        49        PLACE STANDBY CC PUMP IN AUTO-AFTER-STOP SRO            Direct RO to Place 1-CC-P-1B in Auto after Stop.
RO            Places 1-CC-P-1B in AUTO.
Evaluator Note: At Evaluator discretion, the next Event (Event 5) may be initiated at this time.
Step 50, 1-AP-10.07 SRO        50        CHECK RHR - WAS IN SERVICE RO            Reports RHR NOT in service.
SRO            GOES TO Step 52.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                  Event No.: 4                  Page 25 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 52, 1-AP-10.07 SRO        CAUTION:
* If a HI-HI CLS has occurred on Unit 1, 1-FC-P-1A must not be started on EDG 1 if 1-CS-P-1A is running.
* If a HI-HI CLS has occurred on Unit 2, 1-FC-P-1B must not be started on EDG 2 if 2-CS-P-1A is running.
NOTE:
* Power supplies to 1-FC-P-1A (Norm)1H1-2N2A, (Alt)1B1-1-4D, or (Backup) 2H1-2S10B.
* Power supplies to 1-FC-P-1B (Norm) 2H1-2S10B, (Alt)1B1-1-4D, or (Backup)1H1-2N2A.
52      CHECK SFP COOLING - EITHER PUMP RUNNING RO            Reports 1-FC-P-1B Running Step 53, 1-AP-10.07 SRO        53      CHECK INTAKE CANAL LEVEL - STABLE OR INCREASING RO            Reports Intake Canal Level 29 feet and Stable.
Step 54, 1-AP-10.07 SRO        NOTE: If two CHG pump CC pumps or two CHG pump SW pumps are running, one pump should be secured and placed in AUTO.
54      CHECK CHG PUMP AUXILIARIES:
* CHG pump CC pump - RUNNING
* CHG pump SW pump - RUNNING RO            Reports 1-CC-P-2A and 1-SW-P-10A Running.
Step 55, 1-AP-10.07 SRO        55      CHECK SEMI-VITAL BUS - POWER HAS BEEN INTERRUPTED RO            Reports Semi-Vital Bus Power has not been interrupted.
SRO            GOES TO Step 57 Step 57, 1-AP-10.07 SRO        57      CHECK BOTH PRZR PORV BLOCK VALVES - ENERGIZED RO            Reports Both PRZR Block Valves energized
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                    Page 26 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 58, 1-AP-10.07 SRO        58      CHECK CC TO EXCESS LETDOWN HX - NOT TRIPPED
* FI-CC-109 RO/BOP            Reports FI-CC-109 Flow is Approximately 160 gpm and Stable.
Step 59, 1-AP-10.07 SRO        59      CHECK IA SYSTEM ANNUNCIATORS - NOT LIT:
* 1B-E6, IA LO HDR PRESS/IA COMPR 1 TRBL
* 1B-G5, INST AIR DRYER TRBL
* 1B-E5, SA COMPR TRBL
* 1B-F5, CTMT INST AIR COMPR TRBL RO            Reports 1B-E6 and 1B-G5 are LIT.
SRO            Directs BOP to review the ARPs for the lit annunciators.
BOP            Directs Turbine Building Operator to investigate cause for alarms in IA System.
Step 60, 1-AP-10.07 SRO        60      CHECK UNIT CONDITIONS a) PRZR level - STABLE b) PRZR pressure - STABLE c) RCS TAVE - STABLE RO            Reports Parameter normal with no abnormal trends.
Step 61, 1-AP-10.07 SRO        61      CHECK VENTILATION FANS - OPERATING
* Auxiliary BLDG Central
* Safeguards BOP            Reports Auxiliary Building Central and Safeguards fans operating normally
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                    Page 27 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 62, 1-AP-10.07 NOTE: Any MCR Chiller that was operating prior to the loss of power will have tripped and the compressor will not automatically restart. The Chiller must be shutdown and then restarted IAW 0-OP-VS-006, Control Room and Relay Room Ventilation System.
SRO 62      CHECK THE FOLLOWING MCR VENTILATION EQUIPMENT -
OPERATING:
* One Control Room Chiller (Two Control Room Chillers if SI initiated on either unit AND any MCR or ESGR temperature indicator greater than 84&deg;F)
BOP            Reports 1-VS-E-4C and 1-VS-E-4E Running.
SRO
* One Unit 1 Control Room AHU
* One Unit 2 Control Room AHU
* One Unit 1 ESGR AHU
* One Unit 2 ESGR AHU BOP            Reports One Unit 1 and Unit 2 MCR and ESGR AHU operating.
Step 63, 1-AP-10.07 SRO        63      CHECK CRDM FANS - THREE RUNNING BOP            Reports Three CRDM Fans Running Step 64, 1-AP-10.07 SRO        64      CHECK CONTAINMENT AIR RECIRC FANS - THREE RUNNING BOP            Reports three fans running.
Step 65, 1-AP-10.07 SRO        CAUTION:
* If a HI-HI CLS has occurred on Unit 1, 1-FC-P-1A must not be started on EDG 1 if 1-CS-P-1A is running.
* If a HI-HI CLS has occurred on Unit 2, 1-FC-P-1B must not be started on EDG 2 if 2-CS-P-1A is running.
NOTE:
* Power supplies to 1-FC-P-1A (Norm)1H1-2N2A, (Alt)1B1-1-4D, or (Backup) 2H1-2S10B.
* Power supplies to 1-FC-P-1B (Norm) 2H1-2S10B, (Alt)1B1-1-4D, or (Backup)1H1-2N2A.
65      CHECK SFP COOLING - EITHER PUMP RUNNING RO            Reports 1-FC-P-1B Running
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                Page 28 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 66, 1-AP-10.07 SRO        66      CHECK AFW MOVS - BOTH TRAINS ENERGIZED BOP            Reports all AFW MOVs energized.
Step 67, 1-AP-10.07 SRO        67      CHECK BORIC ACID ALIGNMENT:
* One Tank in service
* One BATP in service BOP            Reports 1-CH-P-2A running and aligned to the A BAST.
Step 68, 1-AP-10.07 SRO        68    CHECK CVCS HEAT TRACING PRIMARY AND BACKUP PANELS - ALL ENERGIZED
* Primary panels 2A1, 2A2, and 2A3 - powered from 1H 480V Bus RO            Reports heat tracing panels energized.
Step 69,1-AP-10.07 NOTE: The N-16 and MGPI Radiation Monitors are powered from Breaker 1H1                                    4B2 or 2H1-1-2D-2 depending on the position of throw-over switch 1-EP-TRS-DB-101 located near MCC 1H1-1.
SRO        69      CHECK RADIATION MONITORS - OPERABLE
* No sample pump deenergized
* No flow faults
* No monitors deenergized
* Annunciator 1A-C3, N-16 TROUBLE - NOT LIT
* Annunciator 0-RMA-C5, PROCESS VENT RAD MON TRBL - NOT LIT
* Annunciator 0-RMA-D5, VENT STACK #2 RAD MON TRBL - NOT LIT BOP            Reports sample pumps energized, No flow faults, No monitors deenergized.
Reports Annunciators 1A-C3, RMA-C5, RMA-D5 - not LIT.
Step 70, 1-AP-10.07 NOTE:      The CTMT Particulate and Gas Rad Monitor skids are powered from 1MR1A, Breaker 43, which is supplied from 480V MCC 1C1-2. These monitors are required to comply with Tech Spec 3.1.C.1.
SRO        70    LOCALLY CHECK CTMT PARTICULATE AND GAS RAD MONITOR -
OPERABLE (SKID/ SAMPLE PUMP ENERGIZED) (IF MCC 1C1-2 CONFIRMED TO BE DEENERGIZED, NO NEED TO CHECK LOCALLY)
SRO            Directs BOP to dispatch Aux Building Operator to check local RM skid.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                  Page 29 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 71, 1-AP-10.07 SRO        71. ___ CHECK SW SUPPLY MOVS - ALL ENERGIZED RO            Reports SW MOVS energized.
Step 72, 1-AP-10.07 SRO        72      CHECK TECH SPEC LCOS:
* Tech Spec 3.16 SRO            The SRO will consult Tech Specs 3.16.B.2 and determine the Unit may be operated for 7 days provided the dependable alternate source can be OPERABLE within 8 hours. SRO will consult with the Shift Manager concerning whether the Dependable alternate source can be Operable within 8 hours.
SRO may refer to Tech Spec 3.6.I and determine AFW cross-tie clock is not in effect.
SRO will identify 6/30 clock Tech Spec 3.16, while the alignment of running charging pumps is made using 1-AP-10.07, Attachment 4.
SRO will brief the Team on Tech Spec requirements.
Step 73, 1-AP-10.07 CAUTION:      If any EDG has operated below 570 KW for three days, additional loading will be required to prevent exhaust system souping. Refer to Attachments 7 and 8.
SRO        73    CHECK 4160V EMERGENCY BUS 1H - ENERGIZED FROM OFFSITE POWER
* 15F1 - CLOSED
* 15H8 - CLOSED RO/BOP            Reports 15F1 and 15H8 breakers closed.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                    Page 30 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 74, 1-AP-10.07 CAUTION:
* Shift Supervision should direct the loading of EDG 3 to 1J or 2J Emergency Bus to best support plant recovery.
* If any EDG has operated below 570 KW for three days, additional loading will be required to prevent exhaust system souping. Refer to Attachments 7 and 8.
NOTE:
* The RSS transformer cooling fans, heaters, and load tap changer controls are powered from 1J1-1-3B2 or 2J1-1-4A2 depending on position of the throwover switch near 1-SA-TK-2 in Unit 1 Turbine BLDG basement. The switch shall be aligned to an energized bus.
* Until the throwover switch is aligned to an energized bus, the RSST load tap changers are inoperable. Tech Spec 3.16.B.2 should be reviewed for required actions.
SRO        74    CHECK AC EMERGENCY BUS 1J - ENERGIZED FROM OFFSITE POWER
* 15D1 - CLOSED
* 15J8 - CLOSED RO/BOP            Reports breaker 15D1 closed, breaker 15J8 Open.
Step 74, RNO Do the following:
a) IF 1J Bus energized from EDG 3, THEN do the following:
: 1) Monitor EDG 3 parameters IAW Attachment 8.
SRO            SRO Directs RO/BOP to contact Service Building Operator to monitor #3 EDG using Attachment 8 of 1-AP-10.07.
: 2) Continue efforts to restore normal Emergency Bus power.
: 3) WHEN cause of power loss identified and corrected, THEN initiate 0-AP-10.08, STATION POWER RESTORATION.
Step 75, 1-AP-10.07 SRO        75. ___ CHECK ANY STATION SERVICE BUS - DEENERGIZED:
* 15A1 and 15A2 - OPEN OR
* 15B1 and 15B2 - OPEN OR
* 15C1 and 15C2 - OPEN BOP            Reports All Station Service Buses energized.
SRO        Step 75, RNO IF ALL 480V Station Service Buses are energized, THEN GO TO Step 97.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                  Event No.: 4                  Page 31 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 97, 1-AP-10.07 SRO        97      NOTIFY THE FOLLOWING:
* OMOC
* STA
* Electrical Foreman SRO            Notifies Shift Manager that 1-AP-10.07 complete and request notification to OMOC, STA, and Electrical Foreman be made.
Attachment 4 of 1-AP-10.07 on next page.
END EVENT #4
 
Appendix D                                    Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 3                      Event No.: 4                  Page 32 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Time      Position                                    Applicants Action or Behavior Step 1, Attachment 4, 1-AP-10.07 BOP CAUTION: An EDG can NOT initially be loaded to greater than 1300 KW prior to an SI or HI HI CLS, with the exception of loads that will trip when a HI HI CLS occurs, or loads which are running yet assumed to start on a HI HI CLS.
CAUTION: Total EDG load shall not exceed 2750 KW.
NOTE:
* The purpose of this Attachment is to limit EDG loading so that a subsequent HI HI CLS actuation will not overload the EDG.
* EDG load must be monitored closely during pump operations.
* A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading.
BOP
: 1. IF EDG 1 is the sole source of power to Emergency Bus 1H, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.
Identifies #1 EDG NOT the sole source to 1H Emergency Bus and GOES TO Step 2.
Step 2, Attachment 4, 1-AP-10.07 BOP        NOTE: A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading.
Notifies SRO of 6/30 hour TS 3.16 clock in effect until 1-CH-P-1B running on #3 EDG.
BOP
: 2. IF EDG 3 is the sole source of power to Emergency Bus 1J, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.
: a. Check running or start 1-CH-P-1B or 1-CH-P-1C on Emergency Bus 1J IAW Shift Supervision direction.
BOP            Starts 1-CH-P-1B with concurrence of SRO.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                      Event No.: 4                  Page 33 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 2, Attachment 4, 1-AP-10.07 BOP                b. IF a CHG pump can NOT be started on Emergency Bus 1J, THEN do the following. Otherwise, enter N/A.
Enters N/A for substeps b.1, b.2, and b.3.
: c. Check or place the remaining CHG pump supplied from Emergency Bus 1J in PTL.
Identifies 1-CH-P-1C (Alternate) in PTL.
: d. IF Emergency Bus 1H is supplied by offsite power, and 1-CH-P-1A or 1-CH-P-1C is running, THEN stop CHG pump(s) supplied from Emergency Bus 1H and place in Auto.
RO/BOP            Confer with SRO and secures 1-CH-P-1A and 1-CH-P-1C.
: e. Determine Emergency Bus 1J load limit IAW the following equation, where (x) equals the total of the KW ratings of all RUNNING equipment from the table below.
                                            *___________ + 1300 KW = _________________
(x)                        EDG Load Limit BOP            BOP will write 100 in the (x) blank, and write 1400 in the EDG Load Limit blank.
: f. IF existing EDG load is greater than the limit calculated in Substep e.
above, THEN reduce EDG load to less than or equal to the calculated load.
BOP will identify ~950kW load on #3 EDG.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                  Event No.: 4                    Page 34 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 3. Attachment 4, 1-AP-10.07 BOP        3. Notify Auxiliary Building Operator to increase monitoring of CHG pump lube oil temperature.
BOP contacts the Aux Building Operator to monitor CHG pump lube oil temperature Step 4, Attachment 4, 1-AP-10.07 BOP        4. Increasing monitoring of CHG pump bearing temperatures using the Plant Computer system.
BOP will monitor CHG pump bearing temperatures using the Plant Computer system.
BOP returns the Attachment to the SRO and provides a short brief of Attachment results.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 35 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
Time        Position                                  Applicants Action or Behavior Team        Identify the failure of the Test Button based on the following:
Alarms:
PCS Alarm for MSR Indications:
                                    ~ 9 MW step decrease indicated on MW Videographic Recorder.
0.2 &deg;F increase in RCS Tave Test 1RL 1IL Button on turbine control panel 1RL CLOSED indicating light LIT on turbine control panel 1IL CLOSED indicating light LIT on turbine control panel.
Note: Team may directly enter 1-AP-38.00 (see page 39).
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS NOTE: SRO may directly enter AP-38.00, MAIN STEAM SYSTEM CONTROL MALFUNCTION. See Page 39.
BOP        [1] VERIFY REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL BOP identifies Valve Position Indications are NORMAL.
BOP        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP Identifies no controls need to be placed in Manual.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 36 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
SRO        *3        VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO        Identify that reactor power is less than 100%.
SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
Turbine Valve Position, Step 10 BOP            Reports #1 LP Turbine Left Intercept and Reheat Stop Valves are closed.
CAUTION: If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.
SRO        10. ___ CHECK STEAM SYSTEM CONTROLS - NORMAL
* Steam Dumps / PORVs
* Turbine Controls
* Turbine Valve Positions
* Turbine Monitoring Lights BOP            Reports Turbine Valve positions are abnormal.
SRO            Initiates AP-38.00
 
Appendix D                                  Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                      Event No.: 5                      Page 37 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
Time        Position                                  Applicants Action or Behavior Step 1, 1-AP-38.00 SRO        1  CHECK STEAM DUMP VALVES - CLOSED BOP            Reports Steam Dump Valves closed / normal.
Step 2, 1-AP-38.00 SRO        2    CHECK SG PORVS - CLOSED BOP            Reports SG PORVs closed Step 3, 1-AP-38.00 SRO        3        CHECK THE FOLLOWING CONDITIONS:
* Reactor power - LESS THAN OR EQUAL TO 100%
* Turbine load - NORMAL BOP            Reports reactor power < 100%
RO            Reports Turbine Load NOT Normal SRO        Stabilize Reactor power and Turbine load less than 100% using Attachment 2.
NOTE: No Actions required in Attachment 2 for this event.
Step 4, 1-AP-38.00 NOTE: The power reductions required by Step 4 are intended for failures causing full or partial closure of a control valve, or if valve closure is required for maintenance.
SRO        4        CHECK MAIN TURBINE AND MSR STEAM CONTROL VALVES:
a)        MSR Steam supply MOVs and FCVs - NORMAL BOP            Report MSR MOVs and FCVs normal.
b)        Turbine Governor Valves and Stop Valves - NORMAL BOP            Report Turbine GVs and SVs normal.
c)        Reheat Stop and Intercept Valves - NORMAL BOP                Report Reheat Stop and Intercept Valves ABNORMAL RNO c)    Reduce Reactor power to less or equal to 71% IAW 0-AP-23.00, RAPID LOAD REDUCTION, OR 1-OP-TM-005, UNIT RAMPING OPERATIONS.
SRO        INITIATES 0-AP-23.00 to reduce load to less than 71%.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 38 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
RO        Reactivity control during AP-23.00 Ramp:
146 gallons of Boric Acid needed to reduce power to 71%. 50 gallons added during Emergency Boration, leaving 96 gallons to be added using normal boration at an average rate of 5.8 gpm. Control Bank D rod height at end of ramp 197 Steps.
Gallons of PG to be added to stabilize at end of ramp 1957.
SRO        Completes Brief and continues with AP-23.00.
EVALUATOR NOTE: RO Emergency borates for 25 seconds which corresponds to
                          ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.
SRO        Caution Prior to Step 1:
* Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.
Notes Prior to Step 1:
* Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
* When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
* Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
* The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
* For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.
0-AP-23.00 RO        1. TURN ON ALL PRZR HEATERS
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                Page 39 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
: 2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:
BOP            a) Verify turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.
RO            b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5&deg;F.
SRO/BOP            c) Verify or place turbine in IMP IN or IMP OUT as determined by Shift Supervision The SRO can choose IMP IN or IMP OUT.
BOP            d) Adjust SETTER to desired power level e)  Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute) f)  Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) g) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.
SRO        3. CHECK EMERGENCY BORATION - REQUIRED The team may decide to emergency borate after the ramp has progressed to the point that Tave and Tref are matched (or close).
SRO        Note Prior to Step 4:
* Step 4 or Step 5 may be performed repeatedly to maintain Tave and Tref matched, Flux in band, and control rod position above the LO-LO insertion limit.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 40 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
0-AP-23.00 RO        4. PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:
a) Verify or raise CHG flow to greater than 75 gpm b) Transfer the in-service BATP to FAST c) Open ( )-CH-MOV-( )350 (~25 seconds) d) Monitor EMRG BORATE FLOW
                                        *  ( )-CH-FI-( )110 e)  After required emergency boration, perform the following:
: 1) Close ( )-CH-MOV-( )350
: 2) Transfer the in-service BATP to AUTO
: 3) Restore Charging flow control to normal RO        5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.
SRO        Notes Prior to Step 6:
* If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
* RCS Tave must be maintained less than or equal to 577&deg;F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
* I & C should be contacted to provide assistance with adjusting IRPIs.
RO        6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG RO        *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.
BOP        8. MONITOR STEAM DUMPS FOR PROPER OPERATION
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                Event No.: 5                    Page 41 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
0-AP-23.00 SRO        9. NOTIFY THE FOLLOWING:
* Energy Supply (MOC)
* Polishing Building
* Chemistry
* OMOC SRO        10. EVALUATE THE FOLLOWING:
* EPIP applicability
* VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.
[VPAP-2802 and EPIP are not applicable for this event.]
SRO        11. CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR When reactor power has decreased >15%, then chemistry will be notified.
END EVENT #5
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 42 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
Time        Position                                Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO        1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO        2. Adjust 1-CH-YIC-1113 to desired total gallons RO        3. Adjust 1-CH-FC-1113A to desired flow rate.
RO        4. Place the MAKE-UP MODE SEL switch in the BORATE position.
RO        6. Check proper valve positions.
: 5. Place the MAKE-UP MODE CNTRL switch in the START position RO RO        7. Adjust boration rate using 1-CH-FC-1113A, as necessary.
RO        8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.
a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.
b) Enter N/A for the remaining steps in this Attachment.
Attachment 5 is on the next page RO        9. Check controllers for Primary Grade water and Boric Acid are set correctly.
RO        10. Place the MAKE-UP MODE SEL switch in the AUTO position.
RO        11. Place the MAKE-UP MODE CNTRL switch in the START position.
RO        12. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 3                  Event No.: 5                  Page 43 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
Time        Position                                Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions
: 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
: 2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
: 3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
: 4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
: 5. Place the MAKE-UP MODE CNTRL switch in the START position.
: 6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
: 7. Check proper valve positions.
: 8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position
: 9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
: 10. Check or place the control switches in the AUTO position.
: 11. Check controllers for Primary Grade water and Boric Acid are set correctly.
: 12. Place the MAKE-UP MODE SEL switch in the AUTO position.
: 13. Place the MAKE-UP MODE CNTRL switch in the START position.
: 14. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 6                      Page 44 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
Time        Position                                Applicants Action or Behavior Team      Diagnoses the failure with the following indications:
Alarms:
* RM-Q7 - CTMT PART ALERT/FAILURE
* RM-Q8 - CTMT GAS ALERT/FAILURE
* RM-R8 - CTMT GAS RM-RI-160 HIGH Indications:
* CTMT Sump Level increasing
* 1-DA-P-4A running continuously Unit 2 will perform RM ARPs, but will be unable to perform Auto Action verification.
1-AP-16.00 SRO      Direct initiation of 1-AP-16.00, EXCESSIVE RCS LEAKAGE SRO      Notes Prior to Step 1:
* If SI Accumulators are isolated, 1-AP-16.01, Shutdown LOCA, should be used for guidance.
* RCS average temperature has a direct impact on pressurizer level.
RO      [1] MAINTAIN PRZR LEVEL:
* Isolate Letdown
* Control Charging flow RO closes 1-CH-LCV-1460A and 1-CH-LCV-1460B to isolate letdown. The RO will take manual control of 1-CH-FCV-1122 to stabilize pressurizer level.
SRO      The team will hold a short transient brief which may simply be stated as An RCS Leak is in progress, are there any other higher priorities? (words to the effect).
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 6                  Page 45 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
1-AP-16.00 RO      2. CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING
* PRZR Level
* PRZR Pressure
* RCS Subcooling Identifies all parameters are stable under the control of the operator. Team should identify RCS leak rate less than 50 gpm.
Note: Due to ramp previously in progress and Tave trend, the RCS leakrate will be more difficult to calculate.
RO      3. PLACE THE FOLLOWING COMPONENTS IN OFF:
* CTMT sump pumps
* CTMT vacuum pumps RO will place the Containment Sump and Vacuum Pumps in OFF.
SRO      Note Prior to Step 4:
* Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.
RO      *4. CHECK REACTOR TRIP - REQUIRED
* Leak rate - GREATER THAN 50 GPM OR
* Adequate makeup not being provided by blender RO will identify that the leak rate is less than 50 gpm. Note: this can be complicated by temperature trend associated with ramp (may take more time).
4., RNO GO to Step 7.
Evaluator Note: If the Team Identifies RCS leakage > 50 gpm and manually trips the reactor, notify the Simulator Operator to Initiate Event #8, SBLOCA).
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 6                  Page 46 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
SRO      7    CHECK SECONDARY RADIATION - NORMAL OR STABLE IF THERE IS PRE-EXISTING TUBE LEAK
* Air Ejector Rad Monitor
* SG Blowdown Rad Monitors
* Main Steam Line Rad Monitors
* Secondary sample
* N-16 Rad Monitors Unit 2          Report Unit 1 Air Ejector and Blowdown Rad Monitors - Normal BOP            Reports Main Steam, and N-16 Rad Monitor Normal (using PCS)
SRO      8    CHECK RCS LEAK RATE - LESS THAN 10 GPM RO            Reports leak rate > 10 GPM SRO            Step 8 RNO Do the following:
a)      Initiate unit shutdown IAW the appropriate operating procedure.
b)      Control charging flow and seal injection to maintain PRZR level.
c)      Evaluate EPIP applicability
[TS 3.1.C, RCS Operational Leakage. The following specifications are applicable to RCS operational LEAKAGE whenever Tavg (average RCS temperature) exceeds 200&deg;F (200 degrees Fahrenheit).
: 1. RCS operational LEAKAGE shall be limited to:
: a. No pressure boundary LEAKAGE
: 3. If RCS pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within the limit specified in 3.1.C.1.d, the unit shall be brought to HOT SHUTDOWN within 6 hours and COLD SHUTDOWN within the following 30 hours.]
SRO      9  CHECK UNIT CONDITIONS
* PRZR level - STABLE OR INCREASING
* PRZR pressure - STABLE OR INCREASING
* Tave - STABLE RO          Reports PRZR Level, Pressure and RCS Tave Stable.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 6                Page 47 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
SRO      10 CHECK LETDOWN LEAK - INDICATED BOP
* Annunciator 0-VSP-F4, AUX BLDG SUMP HI LVL - LIT RO
* Annunciator 1B-A3, CTMT SUMP HI LVL - LIT Unit 2
* Aux Bldg radiation - HIGH
* CTMT radiation - HIGH RO/BOP
* Local Report of leak RO
* Leak rate decrease following isolation in Step 1 RO
* Abnormal Letdown flow indication prior to isolation in Step 1 RO
* Non-Regenerative HX tube leak - INDICATED BOP
* CC Surge Tank level - INCREASING Unit 2
* CC Activity - INCREASING All indication checked for leak identification are NO SRO      Goes to Step 12 12 CHECK RCS LEAKRATE WITH LETDOWN SECURED - REDUCED 12 RNO Do the following:
a)  Return letdown to service IAW the following, if desired:
* Normal letdown, IAW Attachment 2 OR
* Excess letdown, IAW 1-OP-CH-006, SHIFTING LETDOWN b) GO TO Step 15.
[TS 3.1.C, RCS Operational Leakage. The following specifications are applicable to RCS operational LEAKAGE whenever Tavg (average RCS temperature) exceeds 200&deg;F (200 degrees Fahrenheit).
: 1. RCS operational LEAKAGE shall be limited to:
: a. No pressure boundary LEAKAGE
: 3.      If RCS pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within the limit specified in 3.1.C.1.d, the unit shall be brought to HOT SHUTDOWN within 6 hours and COLD SHUTDOWN within the following 30 hours.]
 
Appendix D                              Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3              Event No.: 6 Page 48 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
END OF EVENT #6
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 7                  Page 49 of 103 Event
 
== Description:==
Containment particulate and gas RM fail, no Auto Actions.
Cue: Initiated by Event 6.
Time        Position                                Applicants Action or Behavior 1-RM-R8 Actions BOP        NOTE: BOP will be handed Steps 3 and 4 of ARP to verify auto actions of CTMT GAS High alarm.
BOP        3  VERIFY CTMT PURGE SYS - ISOLATED a) CTMT PURGE SUP - CLOSED
* 1-VS-MOV-100A
* 1-VS-MOV-100B
* 1-VS-MOV-100C
* 1-VS-MOV-100D BOP will verify Purge valves closed on the Unit 1 Ventilation Panel by observing RED and GREEN lights extinguished, and GREEN magnet over Shut position indicating light signifying Valve Closed.
b) CTMT PURGE SUP fans - STOPPED
* 1-VS-F-4A
* 1-VS-F-4B BOP will identify Purge Supply Fans secured by observing RED and GREEN indicating lights extinguished.
c) CTMT PURGE BYP valve - CLOSED
* 1-VS-MOV-101 BOP        4  VERIFY CTMT IA SYSTEM ALIGNMENT:
* 1-IA-TV-101A - CLOSED
* 1-IA-TV-101B - CLOSED Identifies 1-IA-TV-101A / B Open by observing position indicating lights on Unit 1 Vertical board RED Light LIT.
Step 4 RNO Manually Align Valves BOP will close the valves by depressing and holding the GREEN indicating light until only the GREEN indicating light is lit.
NOTE: When either 1-IA-TV-101A / B are closed, 1-IA-AOV-103 will open (checked in Step 5 below).
 
Appendix D                                Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 7            Page 50 of 103 Event
 
== Description:==
Containment particulate and gas RM fail, no Auto Actions.
Cue: Initiated by Event 6.
BOP        5  CHECK CTMT IA COMPR OUTSIDE SUCT - OPEN
* 1-IA-AOV-103 BOP will observe 1-IA-AOV-103 OPEN by observing RED position indicating light LIT.
End EVENT #7
 
Appendix D                                  Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                      Page 51 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                                Applicants Action or Behavior Team            Diagnose escalation of RCS Leak by the following:
Alarms:
1C-B8, PRZR LO PRESS 1B-A3, CTMT SUMP HI LVL Indications:
Lowering RCS Pressure PRZR Level decreasing SRO            Direct RO to re-perform Immediate Actions of AP-16.00.
RO      [1] MAINTAIN PRZR LEVEL:
* Isolate Letdown
* Control Charging flow RO checks 1-CH-LCV-1460A and 1-CH-LCV-1460B closed.
The RO will increase flow using 1-CH-FCV-1122 to control PRZR level.
SRO      The team will hold a short transient brief which may simply be stated as An RCS Leak is in progress, are there any other higher priorities? (words to the effect).
1-AP-16.00 SRO      2. VERIFY THE FOLLOWING PARAMETERS - STABLE OR INCREASING
* PRZR Level
* PRZR Pressure
* RCS Subcooling Identifies all parameters are stable under the control of the operator. Team should identify RCS leak rate greater than 50 gpm.
NOTE: SRO may direct RO to manually trip the reactor and safety inject at this point due to degrading plant parameters.
RO      3. PLACE THE FOLLOWING COMPONENTS IN OFF:
* CTMT sump pumps
* CTMT vacuum pumps RO will check the Containment Sump and Vacuum Pumps in OFF.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                      Event No.: 8            Page 52 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
SRO      Note Prior to Step 4:
* Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.
SRO      *4. CHECK REACTOR TRIP - REQUIRED
* Leak rate - GREATER THAN 50 GPM OR
* Adequate makeup not being provided by blender RO will identify that the leak rate is greater than 50 gpm.
SRO      5  ALIGN CHG PUMP SUCTION TO RWST a) Open 1-CH-MOV-1115B and 1-CH-MOV-1115D b) Close 1-CH-MOV-1115C and 1-CH-MOV-1115E RO Evaluator Note: Team may or may not manually align these valves depending on timing.
SRO      6        GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION SRO          Directs RO to trip the reactor, perform E-0, and Manually Safety Inject on Step 4.
 
Appendix D                                Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                    Event No.: 8        Page 53 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                                Applicants Action or Behavior 1-E Reactor Trip or Safety Injection RO      [1] CHECK REACTOR TRIP:
a)  Manually trip reactor Pushes the reactor trip push buttons.
b)  Check the following:
* All Rods On Bottom light - LIT
* Reactor trip and bypass breakers - OPEN
* Neutron flux - DECREASING RO      [2] CHECK TURBINE TRIP:
RO          a)  Manually trip the turbine Pushes the turbine trip push buttons.
b)  Verify all turbine stop valves - CLOSED c)  Isolate reheaters by closing MSR steam supply SOV
* 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)
RO      [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                  Page 54 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
[4] CHECK IF SI INITIATED:
RO            a)  Check if SI is actuated:
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3 SI INITIATED - TRAIN A
* A-F-4 SI INITIATED - TRAIN B RO 4b) Manually initiate SI The RO will manually initiate SI at step 4 by pushing both SI pushbuttons.
After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal, with the exception of the alarms already received. He will also state that containment conditions and the electrical conditions are as you see them (or as reported by the RO/BOP).
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                      Page 55 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
SRO      The team will hold a transition brief. During the brief it will be identified that SI was initiated and the RCS leak has degraded into a LOCA.
SRO/BOP      5. Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained the end of Event 8).
SRO/RO      SRO may direct the RO to perform Attachment 8 of 1-E-0 for Transient AFW Control, or opt to throttle AFW as part of E-0, Step 6.
RO      *6. CHECK RCS AVERAGE TEMPERATURE
* STABLE AT 547&deg;F OR
* TRENDING TO 547&deg;F The team will identify that RCS temperature is decreasing. The team should attribute this to the injection of SI into the RCS and AFW flow to the SGs. It is acceptable for the team to enter the RNO portion of this step and perform the applicable steps (summarized below):
Stop dumping steam Reduce AFW flow to the SGs Close MSTVs if cooldown continues
: 7. CHECK PRZR PORVs AND SPRAY VALVES:
RO            a) PRZR PORVs - CLOSED b) PRZR spray controls
* Demand at Zero (or)
* Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                      Page 56 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
SRO      NOTE: Seal injection flow should be maintained to all RCPs.
RO      *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RCS subcooling may or may not be less than 30 &deg;F at this time.
RNO for the step is to go to step 9.
Critical Task:
CT-1: WOG E-1C: Trip all RCPs so that CETC temperatures do not become superheated when forced circulation in RCS stops; Trip all RCPS within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).
NOTE: If RCP trip Criteria are met prior to reaching this Step, the Continuous Actions Page (CAP) contains these criteria. After this Step is read, this step or the CAP can be used for criteria as long as the Team is performing E-0.
RO      9. CHECK IF SGs ARE NOT FAULTED:
* Check pressures in all SGs a)  STABLE OR INCREASING AND b)  GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 8                  Page 57 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
SRO      10. CHECK IF SG TUBES ARE NOT RUPTURED:
Unit 2
* Condenser air ejector radiation - NORMAL Unit 2
* SG blowdown radiation - NORMAL
* SG MS radiation - NORMAL
* TD AFW pump exhaust radiation - NORMAL
* SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO      RO will use PCS indication for MS and TDAFW Exhaust radiation.
Unit 2 will be used to report Condenser A/E and SG Blowdown radiation trend.
SRO      11 CHECK RCS - INTACT INSIDE CTMT
* CTMT radiation - NORMAL
* CTMT pressure - NORMAL
* CTMT RS sump level - NORMAL RO      Identify CTMT conditions as abnormal SRO      GO TO 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT.
SRO      The team will hold a transition brief. During the brief the SRO will set priorities. The RO and BOP will state the parameters associated with the brief placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified alarms. He will also state that containment conditions and the electrical conditions are as you see them.
The SRO will complete the Brief and continue with E-1.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 8                    Page 58 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                                Applicants Action or Behavior Step 1, 1-E-1 SRO          NOTE: Criteria for FR-Z.1 Entry may be met at any time during performance of 1-E-1. (FR-Z.1 Actions in Section 9).
1  CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO identify 2 CH pumps running.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RO reports actual subcooling.
c) Stop all RCPs RO Stops RCPs if not already tripped.
d) RCS pressure - LESS THAN 1275 PSIG [1475 PSIG]
e) Close CHG pump miniflow recirc valves:
* 1-CH-MOV-1275A
* 1-CH-MOV-1275B
* 1-CH-MOV-1275C RO closes or verifies closed mini-flow recirc valves.
Critical Task:
CT-1: WOG E-1C: Trip all RCPs so that CET temperatures do not become superheated when forced circulation in RCS stops; Trip all RCPs within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).
NOTE: Critical Task copied from E-0 if timing of scenario leads to RCP trip criteria identified on entry to 1-E-1.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                    Page 59 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
1-E-1 SRO      2    CHECK IF SGs ARE NOT FAULTED:
* Check pressures in all SGs:
* STABLE OR INCREASING AND
* GREATER THAN 100 PSIG RO reports SGs are not faulted.
NOTE: SG pressures may be decreasing due to cooldown. RO may report SG pressure as lowering. The SRO will obtain Team concurrence that SG pressure decrease is related to RCS cooldown not a SG fault. The brief is closed.
1-E-1 SRO      *3 CHECK INTACT SG LEVELS:
a) Narrow range level - GREATER THAN 12% [18%]
b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%
1-E-1 SRO      4    CHECK IF SG TUBES ARE NOT RUPTURED:
* Condenser air ejector radiation - NORMAL
* SG blowdown radiation - NORMAL
* SG main steam radiation - NORMAL
* TD AFW pump exhaust radiation - NORMAL
* SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER Unit 2 may be used to report Unit 1 condenser air ejector and blowdown radiation monitor readings.
RO      Report MS and TDAFW RM readings using PCS. Identify SG NR levels NOT increasing in an uncontrolled manner.
1-E-1 CAUTION: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure decreases to less than 2335 psig.
SRO      *5    CHECK PRZR PORVs AND BLOCK VALVES:
a) Power to PRZR PORV block valves - AVAILABLE RO            Report PRZR block valves both available.
b) PRZR PORVs - CLOSED
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                Page 60 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
RO            Report PRZR PORVs closed.
c) PRZR PORV block valves - AT LEAST ONE OPEN RO            Report PRZR block valves both open.
1-E-1 SRO      *6. ___ CHECK IF SI FLOW SHOULD BE REDUCED:
a) RCS subcooling based on CETCs - GREATER THAN 30&deg;F [85&deg;F]
RO          Reports indicated subcooling.
b) Secondary heat sink:
RO
* Total feed flow to INTACT SGs - GREATER THAN 350 GPM [450 GPM]
OR
* Narrow range level in at least one intact SG - GREATER THAN 12% [18%]
RO          Reports SGs have adequate level and AFW flow.
RO          c) RCS pressure - STABLE OR INCREASING RO          Reports RCS pressure decreasing.
SRO          RNO a) OR c) GO TO Step 7.
1-E-1 SRO      *7 CHECK IF HI HI CLS INITIATED:
* CS pump(s) - RUNNING OR
* Any Hi Hi CLS annunciator - LIT NOTE: At this Point CTMT pressure may have increased to the HI and/or Hi-Hi CLS setpoint. The Team should identify that Hi and Hi-Hi CLS do not automatically initiate and take manual action to perform the automatic actions. (FR-Z.1 Actions in Section 9)
When the Team identify that Hi-Hi CLS has not actuated, a transition to FR-Z.1 will be made. When the transition is made Critical Task 2 begins:
CRITICAL TASK:
(Actions for FR-Z.1 will follow 1-E-1, Step 18). Page 77
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                  Page 61 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
1-E-1 SRO      8  CHECK SERVICE WATER AVAILABLE:
a) Check Intake Canal level - BEING MAINTAINED BY CW PUMPS RO          Reports Intake Canal level is 29 feet and Stable.
b) GO TO Step 12 1-E-1 SRO      *12      CHECK IF CS PUMPS CAN BE STOPPED:
a) Check the following:
* RWST level - LESS THAN 3%
AND
* CS Pump amps - FLUCTUATING RO          Reports actual RWST Level.
RNO a) GO TO Step 14. WHEN the following conditions are met, THEN do Steps 12b through 12f.
* RWST level - LESS THAN 3%
AND
* CS Pump amps - FLUCTUATING 1-E-1 SRO      CAUTION: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.
                        *14 CHECK IF LHSI PUMPS SHOULD BE STOPPED:
a) Check RCS pressure:
: 1) Pressure - GREATER THAN 250 PSIG [400 PSIG]
RO          Reports RCS pressure > 250 PSIG [400 PSIG]
: 2) Pressure - STABLE OR INCREASING Reports RCS pressure Lowering.
RNO 2) GO TO Step 15.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                Page 62 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
1-E-1 15 CHECK RCS AND SG PRESSURES:
* Check pressure in all SGs - STABLE OR INCREASING
* Check RCS pressure - STABLE OR DECREASING NOTE: SG pressures may be decreasing due to coodown. RO may report SG pressure as lowering. The SRO will obtain Team concurrence that SG pressure decrease is related to RCS cooldown not a SG fault. The brief is closed 1-E-1 SRO      16 CHECK IF EDGs CAN BE STOPPED:
a) Check AC emergency buses - ENERGIZED BY OFFSITE POWER RO          Reports that H Emergency bus energized by off-site power, and J emergency powered from #3 EDG.
b) Reset both trains of SI if necessary RO RO presses SI reset pushbuttons.
c) Check CTMT pressure - LESS THAN 14 PSIA RO Reports actual containment pressure (pressure will be greater than 14 psia).
RNO c) GO TO Step 17. WHEN pressure less than 14 psia, THEN do Steps 16d and 16e.
1-E-1 SRO      17 CHECK INSTRUMENT AIR AVAILABLE:
a) Check annunciator B-E NOT LIT RO            Reports B-E-6 NOT LIT.
b) Check at least one CTMT IA compressor - RUNNING
* 1-IA-C-4A or 1-IA-C-4B RO            Reports 1-IA-C-4A running.
c) Check 1-IA-TV-100 - OPEN RO                Reports 1-IA-TV-100 position.
NOTE: When BOP performs Attachment 4 of E-0, 1-IA-TV-100 may be closed; SRO/BOP may confer over closure of the valve since Hi-Hi CLS actions are being
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 63 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
manually performed.
1-E-1 SRO      18      INITIATE EVALUATION OF PLANT STATUS:
END OF EVENT 8 END OF SCENARIO
 
Appendix D                                Required Operator Actions                Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8      Page 64 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                              Applicants Action or Behavior Attachment 1 of E-0 1  CHECK FW ISOLATION:
* Feed pump discharge MOVs - CLOSED
* 1-FW-MOV-150A
* 1-FW-MOV-150B
* MFW pumps - TRIPPED
* Feed REG valves - CLOSED
* SG FW bypass flow valves - DEMAND AT ZERO
* SG blowdown TVs - CLOSED Attachment 1 of E-0 2  CHECK CTMT ISOLATION PHASE I:
* Phase I TVs - CLOSED
* 1-CH-MOV-1381 - CLOSED
* 1-SV-TV-102A - CLOSED
* PAM isolation valves - CLOSED
* 1-DA-TV-103A
* 1-DA-TV-103B Attachment 1 of E-0 3  CHECK AFW PUMPS RUNNING:
a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY Attachment 1 of E-0 BOP      4. CHECK SI PUMPS RUNNING:
* CHG pumps - RUNNING
* LHSI pumps - RUNNING
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 8                Page 65 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Attachment 1 of E-0 BOP
: 5. CHECK CHG PUMP AUXILIARIES:
* CHG pump CC pump - RUNNING
* CHG pump SW pump - RUNNING Attachment 1 of E-0 BOP      6. CHECK INTAKE CANAL:
* Level - GREATER THAN 24 FT
* Level - BEING MAINTAINED BY CIRC WATER PUMPS Attachment 1 of E-0
: 7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:
a)  Check if ANY of the following annunciators - HAVE BEEN LIT
* E-F-10 (High Steam Flow SI)
BOP
* B-C-4 (Hi Hi CLS Train A)
* B-C-5 (Hi Hi CLS Train B)
Identifies annunciators not lit and goes to step 8.
Attachment 1 of E-0 BOP
                        *8. CHECK IF CS REQUIRED:
a)  CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                Page 66 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Attachment 1 of E-0 BOP      *10. BLOCK LOW PRZR PRESS SI SIGNAL:
a)    Check PRZR pressure - LESS THAN 2000 psig b)  Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c)  Check Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.
Attachment 1 of E-0 BOP      *11. BLOCK LOW TAVE SI SIGNAL:
Step may not be performed at this time (if Tave is greater than 543&deg;F).
a)  Check RCS Tave - LESS THAN 543&deg;F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c)  Check Permissive Status light F LIT Attachment 1 of E-0 NOTE:
* CHG pumps should be run in the following order of priority: C, B, A.
* Subsequent SI signals may be reset by re-performing Step 12.
BOP
: 12. CHECK SI FLOW:
a)  HHSI to cold legs - FLOW INDICATED
* 1-SI-FI-1961 (NQ)
* 1-SI-FI-1962 (NQ)
* 1-SI-FI-1963 (NQ)
* 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c)  Reset SI.
d) Stop one CHG pump and out in AUTO
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                    Page 67 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Step 12, Attachment 1 of E-0, Continued e)  RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:
: 1) Verify reset or reset SI.
: 2) Stop one LHSI pump and put in AUTO.
: 3) GO TO Step 13.
Attachment 1 of E-0 BOP
: 13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]
Attachment 1 of E-0 BOP
: 14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.
Attachment 1 of E-0 BOP
: 15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next Page of this guide)
Depending on timing, this attachment may have already been completed.
Attachment 1 of E-0 BOP
: 16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Unit 2 Operator will state that Unit 2 is at 100% power (if asked)
Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 8                    Page 68 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                              Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 SRO      NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.
ATTACHMENT 2 of 1-E-0 RO/BOP      1. Check opened or open CHG pump suction from RWST MOVs.
* 1-CH-MOV-1115B
* 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 RO/BOP      2. Check closed or close CHG pump suction from VCT MOVs.
* 1-CH-MOV-1115C
* 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 RO/BOP      3. Check running or start at least two CHG pumps. (listed in preferred order)
* 1-CH-P-1C
* 1-CH-P-1B
* 1-CH-P-1A ATTACHMENT 2 of 1-E-0 RO/BOP      4. Check opened or open HHSI to cold legs MOVs.
* 1-SI-MOV-1867C
* 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 RO/BOP      5. Check closed or close CHG line isolation MOVs.
* 1-CH-MOV-1289A
* 1-CH-MOV-1289B
 
Appendix D                              Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                  Event No.: 8      Page 69 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
ATTACHMENT 2 of 1-E-0 RO/BOP      6. Check closed or close Letdown orifice isolation valves.
* 1-CH-HCV-1200A
* 1-CH-HCV-1200B
* 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 RO/BOP      7. Check opened or open LHSI suction from RWST MOVs.
* 1-SI-MOV-1862A
* 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 RO/BOP      8. Check opened or open LHSI to cold legs MOVs.
* 1-SI-MOV-1864A
* 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 RO/BOP      9. Check running or start at least one LHSI pump.
* 1-SI-P-1A
* 1-SI-P-1B ATTACHMENT 2 of 1-E-0 RO/BOP      10. Check High Head SI flow to cold legs indicated.
* 1-SI-FI-1961
* 1-SI-FI-1962
* 1-SI-FI-1963
* 1-SI-FI-1943 or 1-SI-FI-1943A
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 8                  Page 70 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
ATTACHMENT 2 of 1-E-0 RO/BOP      11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.
* Alternate SI to Cold legs
* Hot leg injection
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 71 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 72 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 73 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
 
Appendix D                                Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                Event No.: 8 Page 74 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Unit 2 will prompt BOP: Chilled Water has been aligned IAW CAUTION prior to Step 1.
 
Appendix D                              Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                    Event No.: 8                    Page 75 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Unit 2 will prompt BOP: MCR Boundary DP is the same as DP indicated on Unit 2 Ventilation Panel.
Unit 2 will prompt BOP: Unit 2 remains operating at 100%
power.
Unit 2 will assume responsibility for the Attachment action from this point.
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 76 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 9                    Page 77 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
Time        Position                                  Applicants Action or Behavior 1-FR-Z.1 Actions CAUTION: If 1-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, is in effect, containment spray systems should be operated as directed by 1-ECA-1.1, instead of Step 1 below.
SRO        1    CHECK IF CS REQUIRED:
a) Check CTMT pressure - HAS INCREASED TO GREATER THAN 23 PSIA b) Check CS pumps - RUNNING                b) IF RWST level greater than 3%,
THEN start CS pumps. IF any CS pump can NOT be started, THEN monitor OSRS pumps for cavitation.
RO            Starts 1-CS-P-1A / 1B                      IF cavitation is indicated, THEN put affected OSRS pump in PTL c) Check CS system valves - OPEN            c) Manually align CS valves.
* 1-CS-MOV-100A
* 1-CS-MOV-100B
* 1-CS-MOV-101A and B
* 1-CS-MOV-101C and D
* 1-CS-MOV-102A and B RO            Opens Valves Listed Above (BOLDED).
d) Stop all RCPs RO            Stops RCPS and acknowledges Loop Low Flow Alarms.
Critical Task:
CT-2: WOG E-0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (red-path) challenge develops to the CSF. Establish CS flow from at least one CS pump before containment pressure exceeds 60 psia AND at least one RS train before RMT.
Evaluator Note: To meet the CT, One Train of CTMT Depressurization must be aligned. One CS pump with either of its associated discharge MOVs open.
1-CS-P-1A Running, with 1-CS-MOV-101A or 1-CS-MOV-101B OPEN. OR 1-CS-P-1B Running, with 1-CS-MOV-101C or 1-CS-MOV-101D OPEN.
CRITICAL TASK:
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 9                      Page 78 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
1-FR-Z.1 Actions SRO        2  CHECK SW FLOW TO RS HXs -                      Align valves as necessary.
GREATER THAN 4750 GPM RO            Checks flow > 4750 GPM following the Opening of the SW Valves Listed below.
a) Check the following valves - OPEN
* 1-SW-MOV-103A, B, C, and D
* 1-SW-MOV-104A, B, C, and D
* 1-SW-MOV-105A, B, C, and D RO            Open the SW MOVs listed above.
1-FR-Z.1 Actions SRO        3  CHECK RS SYSTEMS:
a) Check RWST level -LESS THAN 60%                  a) Do the following:
: 1) Monitor RWST level.
: 2) WHEN RWST level is less than 60%, THEN perform Steps 3b and 3c.
1-FR-Z.1 Actions SRO        4  CHECK INTAKE CANAL LEVEL - GREATER THAN 24 FT RO            Reports Intake Canal Level 29 feet and Stable.
1-FR-Z.1 Actions SRO        5  CHECK CTMT ISOLATION VALVES -
CLOSED IAW ATTACHMENT 1                              IF flow path NOT necessary, THEN close valves BOP            Aligns Valves as necessary.
NOTE: BOP and SRO may confer on leaving 1-IA-TV-100 open.
NOTE: FR-Z.1 Actions located at the end of this section.
1-FR-Z.1 Actions SRO        6. ___ CHECK MSTVs - CLOSED                              Manually close MSTVs.
RO/BOP            Closes MSTVs if not already performed.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 9                  Page 79 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
1-FR-Z.1 Actions CAUTION:
* At least one SG must be maintained available for RCS cooldown.
* If all SGs are faulted, at least 60 gpm [100 gpm] feed flow should be maintained to each SG.
SRO        7. ___ CHECK IF FEED FLOW SHOULD BE ISOLATED TO ANY SG(s):
a) Check pressures in all SGs:                    a) GO TO Step 8
* ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR
* ANY SG COMPLETELY DEPRESSURIZED RO/BOP            Reports SGs NOT Faulted.
1-FR-Z.1 Actions SRO        8  CHECK SERVICE WATER AVAILABLE:
a) Check Intake Canal level - BEING MAINTAINED BY CIRC WATER PUMPS RO/BOP            Reports Intake Canal Level 29 feet and Stable. Being maintained by CW pumps.
b) RETURN TO procedure and step in effect SRO            Returns to 1-E-1, Step In Effect.
 
Appendix D                                Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                Event No.: 9 Page 80 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
Valves Operated for Hi CLS Failure.
Valves Operated for Hi Hi CLS Failure.
Valve BOP/SRO may confer and leave open.
 
Appendix D                                Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 9 Page 81 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
Valves Operated for Hi CLS Failure.
Valves Operated for Hi Hi CLS Failure.
Valve BOP/SRO may confer and leave open.
 
Appendix D                                Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                Event No.: 9 Page 82 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
Section Not Performed for this Scenario.
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 83 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 84 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 85 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 3                                  Page 86 of 103 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:
Recall IC -263 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.
Open the monitor window and add the following points to it:
* asp_ao_off
* set sphhcntprs_k1 = 60
* iadryer_reset
    *    ??
Enter the following MALFUNCTIONS:
Trigger Malfunction            Delay    Ramp        Trigger  Value    Final      Type (Auto or Manual)
RC0801 TAVE TAYLOR MATH                10        0          1      0          -1          MAN UNIT FAILURE HI/LOW MS0801 SG A STM FLOW                    10        30          3      0          -1          MAN TRNSMTR MS-FT-475 FAILURE EL4902 BKR 15J8 SPURIOUS TRIP          10        0          5    FALSE      TRUE          MAN RC04 RCS LEAK NONISOLABLE              10        0          9      0        3.5          MAN (0 - 1200 GPM)
RM0202 PROCESS RAD                      10        0          9      0        0.1          MAN MONITOR RI-RMS-159 FAILURE RM0201 PROCESS RAD                      10        0          9      0        0.1          MAN MONITOR RI-RMS-160 FAILURE CA03 Disable IA-TV-101A Auto            0        0          9    FALSE      TRUE          MAN Closure CA06 Disable IA-TV-101B Auto            0        0          9    FALSE      TRUE          MAN Closure RC0101 RCS COLD LEG A PIPE              10      600          11      0          .6          MAN RUPTURE RS0901 TRN A HI CLS FAILS TO            0        0          30    FALSE      TRUE        ACTIVE ACTIVATE RS0902 TRN B HI CLS FAILS TO            0        0          30    FALSE      TRUE        ACTIVE ACTIVATE
 
Appendix D                              Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3                        Page 87 of 103 SIMULATOR OPERATORS GUIDE Enter the following Remote Functions:
Override                            Set Condition                      Trigger AC_SMS_MODE                                  OFF                              30 Enter the following Override:
Override                            Set Condition                      Trigger TEST_IRL_IIL EHC                          ON, 10 Sec TD                          7 TEST 1RL 1IL CLS_ACT_TRA                                  OFF                              30 CLS_ACT_TRB                                  OFF                              30 TRIGGER                  TYPE                                  DESCRIPTION 1                    MAN            TAVE TAYLOR MATH UNIT FAILURE LOW 3                    MAN            SG A STM FLOW TRNSMTR MS-FT-475 FAILURE 5                    MAN            BKR 15J8 SPURIOUS TRIP 7                    MAN            IRL/ILL TEST PUSHBUTTON FAILURE RCS LEAK NONISOLABLE (35 GPM) with AUTO ACTIONS RM-MAN 9                                  159/160 FAILURE 11                    MAN            LBLOCA WITH HI and HI HI CLS FAILED
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 3                                Page 88 of 103 SIMULATOR OPERATORS GUIDE Verify the following control room setup:
Place the simulator in RUN and verify normal 100% power operation indications.
Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:
Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).
Verify Ovation System operating.
Reset ICCMs.
Verify Component Switch Flags.
Verify Brass Caps properly placed.
Verify SG PORVs set for 1035 psig.
Verify Rod Control Group Step Counters indicate properly.
Verify Ovation CRT display.
Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)
Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:
AP-53.00            AP-16.00            AP-23.00                    1-OPT-RX-007 (3)
E-0                                    E-1 (2)
OP-CH-007                                MOL OP-RX-010 OP-ZZ-002 Verify Reactivity Placard is current.
Verify ALL PINK MAGNETS are accounted for.
 
Appendix D                            Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3                                Page 89 of 103 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.
Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.
If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.
In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.
Assign operating positions.
Ask for and answer questions.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 3                                Page 90 of 103 SIMULATOR OPERATORS GUIDE Conduct shift turnover:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
Shift orders are to maintain 100% power on Unit #1.
The last shift performed two 35 gallon alt dilutions followed by a manual makeup for training.
A BAST at 8.0 W/%.
When the team has accepted the shift, proceed to the Session Conduct Section.
 
Appendix D                                  Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 3                              Page 91 of 103 SIMULATOR OPERATORS GUIDE Session Conduct:
* Ensure conditions in Simulator Set-up are established.
* Ensure Trigger 30 is active prior to team entering the simulator.
* Verify Exam Security has been established and ASP_AO_OFF = True.
EVENT 1          Deleted.
EVENT 2          Failure Median Tave Low, 0-AP-53.00.
When cued by examiner, implement Trigger #1.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of Median Tave. The individual(s) contacted will also acknowledge entry into AP-53.00.
* If contacted, will take responsibility for writing the CR.
* If asked, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
STA:
* If contacted, will acknowledge the failure of Median Tave.
* If asked, the STA will report that upon review of CEP 99-0029, Median Tave is NOT listed in CEP 99-0029.
* If asked, the STA will review VPAP-2802 and TRM Section 3.3 and report that the results of the review have been discussed with Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
 
Appendix D                              Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3                            Page 92 of 103 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:
* If contacted, will acknowledge instrumentation failure and commence investigation of the failure.
Unit 2 Operator:
* If contacted, will acknowledge the failure.
Role play as other individuals as needed.
 
Appendix D                                  Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 3                              Page 93 of 103 SIMULATOR OPERATORS GUIDE EVENT 3          Failure of Steam Flow Channel Low, A SG. 0-AP-53.00.
When cued by examiner, implement Trigger #3.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of 1-MS-FT-1474. The individual(s) contacted will also acknowledge any TS LCOs.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into 72 hour clock to place the channel in trip.
* If contacted, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
STA:
* If contacted, will acknowledge the failure of 1-MS-FT-1474. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
* If contacted, will take responsibility for writing the CR.
* If asked, 1-MS-FT-1474 is a RG 1.97 variable
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
* When directed, STA review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
Field Operators:
* Will perform actions as directed.
I&C:
* If notified by MCR to place the channel in trip, state that you will review the procedure and notify the Shift Manager when ready to brief.
 
Appendix D                            Required Operator Actions  Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3    Page 94 of 103 SIMULATOR OPERATORS GUIDE Maintenance/ Work Week Coordinator:
* If contacted, will notify I&C of the failure.
Unit 2:
* If contacted, will acknowledge the channel failure.
Role-play as other individuals as needed.
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 3                                Page 95 of 103 SIMULATOR OPERATORS GUIDE EVENT 4          1J 4160V emergency bus off-site power supply breaker trips. 1-AP-10.07.
When the Evaluator is ready, Implement Trigger #5 for the failure. Evaluator may go to next event (event #5) when 1-CC-P-1B is placed in Auto.
Operations Supervisor/Management:
* If contacted, will acknowledge the loss of 1J 4160 V bus, and the start and load of #3 EDG.
* If contacted, will inform OM on Call and Electrical Foreman.
STA:
* If contacted, will acknowledge the loss of 1J 4160V bus and the start and load of #3 EDG.
* After directed, the STA will report that VPAP-2802 has been reviewed and discussed with the Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
Maintenance/ Work Week Coordinator:
* If contacted, will acknowledge the failure and commence investigations.
Field Operators:
* If contacted, will check status of 15J8 breaker and find an individual in the area that reports he bumped the cabinet while cleaning and heard a loud noise. 1-CC-P-1B must have been returned to Auto before this report is made.
* If asked, the condensate polishing building operator will report current polishing building DP (read from simulator screen).
* When Directed, to check status of IA compressors (1B-E6 ARP), CA6 1-IA-C-1 IA Local Panel, the local panel will have an Alarm light lit. Depress U1_IAC1_SET button to clear alarm.
 
Appendix D                            Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3                              Page 96 of 103 SIMULATOR OPERATORS GUIDE
* When Directed, to check status of IA Dryer (1B-E5 ARP), the dryer will be bypassed, use IADRYER_RESET on monitor to reset the dryer.
* When contacted, to close 15J9 breaker, EL11, Unit 1 - 4160 Breakers, 15J9, scroll to bottom of pop-up box, double click on SW_15J9_RF, select close, INSERT.
* When contacted, RM-159/160 Particulate and Gas RM skid is normal.
* When contacted, concerning monitoring of #3 EDG parameters, follow instructions.
Unit 2:
* If contacted, acknowledge start and load of #3 EDG on Unit 1.
Role-play as other individuals as needed.
 
Appendix D                            Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                              Page 97 of 103 SIMULATOR OPERATORS GUIDE EVENT 5        Test Button failure, 1RL/1IL close, 0-AP-23.00 ramp to 71%.
When 1-CC-P-1B in Auto and examiner ready, implement Trigger #7.
Operations Supervisor/Management:
* If contacted, will acknowledge closure of 1RL/1IL. Also acknowledge the entry into AP-53.00/AP-38.00 for the failure.
* If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC (Lead Evaluator), the Shift Manager will direct a 1%/minute ramp rate.
* If contacted, will take responsibility for writing the CR.
Unit 2 Operator:
* If notified, acknowledge the failure and impending ramp of Unit 1.
STA:
* If contacted, will acknowledge the closure of 1RL/1IL, and entry into AP-53.00/AP-38.00.
* If contacted, will take responsibility for writing the WR and CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
* The STA will acknowledge the Reactivity Plan reported by the RO.
* If contacted, STA review of VPAP-2802 complete and reviewed with Shift Manager.
 
Appendix D                          Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                Scenario No.: 3                            Page 98 of 103 SIMULATOR OPERATORS GUIDE Field Operators:
* If contacted, as the Turbine Building Operator to walkdown the Turbine during the ramp, acknowledge the direction.
* If contacted, as the polishing building operator, acknowledge the direction to monitor polisher DP.
* If contacted, as Turbine Building operator, the 1RL/1IL valves are closed, no external abnormalities noted.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 99 of 103 SIMULATOR OPERATORS GUIDE EVENTS 6      RCS Leak 35 gpm. 1-AP-16.00.
Note: It would be preferable to wait until power is <80% to implement this failure to allow for ramp stabilization prior to creating RCS leak; this will allow the team to assess leakrate with more precision.
When the Evaluator is ready, implement Trigger # 9. If the Team manually trips the reactor, the Evaluator may prompt initiation of Event #8.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will acknowledge entry into AP-16.00.
* If contacted, will acknowledge Unit shutdown imminent due to excessive RCS leakage.
* If contacted, will acknowledge EPIPs require evaluation.
STA:
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
* When Notified, acknowledge that EPIPs require evaluation.
* If contacted, will enter the control room and and prepare for the transient brief (items are reported as you see them or previously reported).
Unit Two:
* When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 100 of 103 SIMULATOR OPERATORS GUIDE
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO/BOP.
* If asked, blowdown and air ejector RM readings are [as indicated at the time].
* When required, assist Unit by acknowledging Fire Panel Alarms.
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
Field Operators:
* If contacted, field operators will perform valve manipulations as required:
Health Physics:
* If contacted, will acknowledge the leak of RCS coolant into containment.
Maintenance/Work Week Coordinator:
* If contacted, will acknowledge the failure.
Maintenance/Work Week Coordinator:
* If contacted, will acknowledge the failure.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 101 of 103 SIMULATOR OPERATORS GUIDE EVENT 7        Particulate and gas RM fail, No Auto Actions.
Implemented with Trigger #9.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of the automatic actions on RM-160 High alarm.
* If contacted, will take responsibility for writing the WR and CR.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
* If directed, perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
Field Operators:
* If directed, field operators will perform local manipulations as required.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 102 of 103 SIMULATOR OPERATORS GUIDE EVENT 8        SBLOCA, 1-AP-16.00, 1-E-0.
When the Evaluator is ready, actuate Trigger #11. Prompt the Evaluator when RCS Subcooling reaches 35 &deg;F and decreasing so that start time for CT-1 is monitored.
Operations Supervisor/Management:
* If contacted, will acknowledge the reactor trip and Entry into E-0.
* If contacted, will take responsibility for writing the WR and CR.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
STA
* Enter MCR when called and standby to monitor CSFSTs.
* When entry conditions for Containment Orange Path identified, circle the appropriate Path and show to the SRO.
Field Operators:
* If directed, field operators will perform local manipulations as required.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 103 of 103 SIMULATOR OPERATORS GUIDE EVENT 9        Hi and HI-CLS Failure, FR-Z.1.
Implemented by ACTIVE Triggers.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of Hi and Hi-Hi CLS.
STA:
* When the Team identifies containment pressure has exceeded 23 psia, use CSFSTs to mark flowpath to FR-Z.1, ORANGE path and present to SRO.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
* When BOP performs Attachment 3 of E-0, MCR Boundary DP readings are the same as the indication on Unit 2 Ventilation Panel. Unit 2 has initiated 0-AP-50.00. Unit 2 remains at 100% power. Assume responsibility for E-0, Attachment 3, monitoring of SFP.
* If asked, Unit 2 RWST cross-ties are open.
Field Operators:
* If directed, field operators will perform local manipulations as required.
Role play as other individuals as needed.
 
Appendix D                                              Scenario Outline                                        Form ES-D-1 NRC EXAM - SCENARIO #4 Facility: Surry Power Station                      Scenario No.: 4                            Op-Test No.: 2014-001 Examiners: ____________________________ Operators:                                  _____________________________
Initial Conditions: Time in Core Life - Middle of Life; Core Cycle - Cycle 26 Unit 1 and 2 operating at 100%. All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* 1-CC-P-1D tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4)
RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
* Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
* A BAST at 8.0 W/%.
* PSA is Green.
Event            Malf.        Event                                                Event No.            No.          Type*                                              Description 1                  N/A                          Deleted 2                RC4802,            I - RO        1-RC-PT-1445 fails high, PRZR Pressure channel fail high. AP-31.00,
                  +1 Deg          TS - SRO        Increasing or Decreasing RCS Pressure.
3                MS1305,          I - BOP        Steam Pressure Channel III, B SG fails High. 0-AP-53.00, Loss of Vital
                  +1 Deg          TS-SRO          Instrumentation/Controls.
CH2101, 4                +1 Deg            I - RO      Failure of VCT Level Channel LT-115 High.
CC0302 5                CC0802          C - BOP        Overcurrent on B CC pump with breaker mechanically stuck closed SW_15J9_        TS - SRO        causing the trip of Stub Bus Supply breaker.
RF, TRIP C - RO 6                                TS - SRO RD1236          R - RO /      Dropped Rod Control Bank C, Group 1; AP-1.00, Rod Control SRO        Malfunction, AP-23.00, Rapid Load Reduction.
N - BOP 7                RC MOV                          RC Loop C Tc MOV disc falls into flow stream, Valid First-Out 595, 30%          M - All      received, No Auto or Manual Reactor Trip. 1-FR-S.1, Response to Nuclear Generation/ATWS.
RD17 SI1502, 8                40% Deg                          LOCA outside of Containment in Unit 1 Valve Pit Area.
SI1603            M - All SI1606 SI2402 9                SI2405                          SI Relay SI2A fails to Actuate, SI Relay SI5A Fails to Actuate; 1-SI-P-1A CC1801                          not auto start; MOV-1115D, CH-MOV-115C, CH-MOV1289A, CV-TV-C - BOP 150A, and CH-TV-1204A fail to re-position on SI. 1-CC-P-1A Auto Start Disabled.
*          (N)ormal,    (R)eactivity,      (I)nstrument,    (C)omponent,      (M)ajor
 
Appendix D                              Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #4 Event #1:  Deleted.
Event #2:  1-RC-PT-1445 Fails High. (I - RO, TS-SRO)
The RO will respond to the alarms and indications received by performing the Immediate Actions of AP-53.00, Loss of Vital Instrumentations/controls; or 1-AP-31.00, Increasing or Decreasing RCS pressure. RCS pressure is expected to lower to less than 2205 psig for a short time period resulting in a Tech Spec consultation.
Verifiable Actions:
: 1) RO will place control switch for 1-RC-PCV-1456 in close.
: 2) BOP may place Rod Control in manual to stop rod motion caused by the reactivity inserted by the pressure coefficient.
: 3) RO will close 1-RC-MOV-1535 due to Technical Specification requirements.
Technical Specifications:
: 1) The SRO will consult Tech Specs, TS Section 3.1.A.6, and determine that 1-RC-PCV-1456 is Inoperable but capable of being manually cycled, and enter a one hour clock to close the block valve for the PORV. The block valve will remain energized.
: 2) Further consultation will find Tech Spec 3.12.F.1 to restore RCS pressure >2205 psig in 2 hours or reduce Thermal Power to less than 5% in the next 6 hours. The Core Operating Limits Report (COLR, DRP-21) provides the reference for 2205 psig RCS pressure.
Technical Requirements Manual/R.G. 1.97
: 1) No TRM or R.G. 1.97 requirements apply.
Event #3:  Steam Pressure Channel III Fails High on B steam line causing B steam flow increase and B FRV to open. (I - BOP, TS - SRO)
The BOP will respond to the alarms and indication received by placing the B FRV in manual and restoring B SG NR level to program IAW 1-AP-53.00, Loss of Vital Instrumentation/Controls. The Abnormal Procedure will require the Controlling Steam Flow channel to be swapped to Channel IV so that the B FRV can be restored to Auto.
Verifiable Actions:
: 1) BOP will place the B FRV in manual and restore B SG NR level to program.
: 2) RO will shift controlling channel.
Technical Specifications The SRO should consult Tech Specs and determine the following:
 
Appendix D                            Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #4
: 1) Tech Specs Section 3.7, Table 3.7-1, Item 17, Low steam generator water level with steam/feedwater flow mismatch, Operator Action 6. With the number of Operable channels on less than the total number of channels, Power Operation may proceed provided the channel is placed in the trip condition in 72 hours, the channel may be bypassed for 12 hours for surveillance; if these requirements are not met, the Unit must be placed in Hot Shutdown within 6 hours.
: 2) Tech Spec 3.7, Table 3.7-2, Item 1.c., High differential pressure between any steam line and the steam header, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours; the channels may be bypassed for 12 hours for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours and reduce RCS temperature and pressure to less than 350&deg;F/450 psig in the following 12 hours.
: 3) Tech Spec 3.7, Table 3.7-2, Item 1.e.1 and 1.e.3, High Steam line flow in 2/3 steam lines coincident with low Tavg or low line pressure, Operator Action
: 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours; the channels may be bypassed for 12 hours for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours and reduce RCS temperature and pressure to less than 350&deg;F/450 psig in the following 12 hours.
: 4) Tech Spec Table 3.7-3, item 2a, Steam Line Isolation. Refers to Tech Spec Table 3.7-2, Item 1.e. See Above.
: 5) Tech Spec Table 3.7-6, Item 16, SG Pressure, 2 per SG are required. This condition is met.
Technical Requirements Manual/R.G. 1.97:
: 1) The TRM Section 3.3 2, Appendix R Instrumentation, Table 3.3.2-1, Steam Generator Pressure 1-MS-PI-1485 is a Primary indicator. One of the three listed transmitters must be Functional to meet the requirement. Two of the three are Functional. No TRM requirements for this failure. (The TRM review is normally performed by the STA in consultation with the Shift Manager; if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).
RG-1.97
: 1) RG-1.97 variables, Steam Generator pressure is an A-02 variable, 2 channels per SG are required, table refers to Tech Spec Table 3.7-6. (The RG 1.97 review is normally performed by the STA in consultation with the Shift Manager; if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).
Event #4:  VCT Level Transmitter LT-115 Fails High. (I - RO)
The RO is expected to diagnose this failure based upon alarms and indications received.
The RO will perform the Immediate Action Steps of 0-AP-53.00, Loss of Vital Instrumentation/Controls and place the VCT divert valve, 1-CH-LCV-1115A, in the NORM position to stop divert of Letdown flow to the PDTT. The Team will continue through the abnormal procedure.
 
Appendix D                            Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #4 Verifiable Actions:
: 1) RO will place the control switch for 1-CH-LT-1115A in the NORM position to stop letdown diversion to the PDTT.
Technical Specifications:
: 1) There are no Tech Spec or TRM actions required for this failure.
Technical Requirements Manual:
: 1) None for this failure.
Reg. Guide 1.97:
: 1) RG 1.97 requirements: 1-CH-LI-1115 is a D-29 variable, Category 2. 1 channel is required. Required Action C from Attachment 2; restore the required channel to functional status and use alternate indication to accomplish this function, if possible (VCT level channel 1-CH-LI-1112 functional and meets this requirement). Completion Time 60 days if no alternate indication available OR on or before the next planned outage if an alternate indication is available. (The RG 1.97 review is normally performed by the STA in consultation with the Shift Manager, if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).
Event #5:  Overcurrent of the B CC pump with the Breaker Stuck closed, resulting in the trip of the stub bus breaker 15J9 on overcurrent. (C - BOP, TS-SRO)
The BOP is expected to diagnose this failure based on alarms and indications received.
The BOP will place the B CC pump in PTL.
Verifiable Actions:
: 1) BOP will place the control switch for 1-CC-P-1B in PTL.
: 2) BOP will start 1-CC-P-1A.
Technical Specifications:
: 1) The SRO will consult Tech Specs 3.13.A.2 and 3.13.B, and determine that the minimum Operable CC pumps requirement is not met. For 2 Unit operation 3 CC pumps must be operable, and TS 3.13.B cannot be met, the SRO should identify a TS 3.01 6 hour clock to HSD, and a 30 hour clock to CSD.
: 2) Consult Tech Spec 3.5.A.1 and determine the Minimum Operable RHR pumps requirement is not met. This requires, IAW TS 3.5.B, that a 14 day clock be entered to restore A RHR pump to an Operable condition.
 
Appendix D                              Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #4 Technical Requirements Manual
: 1) IAW IAW TRM 3.7.9.A additional 72 hour and 14 day clocks are in effect to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status. Normally an STA function in consult with Shift Manager, recommend use of follow up question.
Event #6:  Dropped Control Rod, M-4, Control Bank C, Group 1. (C - RO, R - RO, TS - SRO, R
          - SRO, N - BOP)
The RO is expected to diagnose this failure based on alarms and indications received and place Rod Control in manual to stop outward rod motion IAW 0-AP-1.00, Rod Control Malfunction.
The Team will continue in AP-1.00 to the point where 0-AP-23.00, Rapid Load Reduction will be used to reduce reactor power to 70-74% to meet the TS requirement to be <75%
of Rated Power within 1 hour.
Verifiable Actions:
: 1) RO will place rod control in manual.
: 2) BOP will perform actions of Annunciator Response Procedure 1G-F8, Bank D WITHDRAWAL to realign group step counters.
Technical Specifications:
: 1) The SRO will determine that the dropped control rod is Inoperable since it is misaligned from its Bank > +/- 12 steps. IAW Tech Spec 3.12.C.3, power must be reduced to < 75% Rated Power within 1 hour, and the High Neutron Flux trip setpoint shall be reduced to  85% of Rated Power within the next 4 hours.
: 2) Shutdown margin must be determined to be satisfactory within 1 hour and every 12 hours thereafter.
: 3) Hot channel factors are shown to be within limits of TS 3.12.B.1 in 72 hours and it shall be demonstrated that the value of Fxy(Z) used in the Constant Axial Offset Analysis is still valid.
: 4) Reevaluation of each accident analysis of Table 3.12-1 is performed within 5 days, to confirm the previous analysis of these accidents remain valid.
: 5) If, except for operation at THERMAL POWER < 50% or for physics and control rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2%, then:
: a. Within 2 hours, either the hot channel factors shall be determined and the power level adjusted to meet the requirement of Specification 3.12.B.1, or
 
Appendix D                              Scenario Outline                                  Form ES-D-1 NRC EXAM - SCENARIO #4
: b. The power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours.
: 6) If the QUADRANT POWER TILT exceeds 10%, the power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours.
Event #7:  Tcold Loop stop disc detaches and drops into the flowstream, Valid First-Out indication, No automatic or manual reactor trip, FR-S.1. (M - ALL)
This Event begins the Major Accident sequence. The RO will identify a First-Out alarm is received, the alarm is valid (Low Flow Condition in C RCS Loop), the reactor has not automatically tripped, attempt a manual reactor trip, and then perform the Immediate Action of 1-FR-S.1, Response to Nuclear Power Generation/ATWS.
The reactor trip breakers will be opened locally two (2) minutes after the Team directs an Operator to perform this action (based upon time critical operator action time requirement for locally tripping the reactor trip breakers).
The Team will complete 1-FR-S.1, transition to 1-E-0, Reactor Trip or Safety Injection to perform the Immediate Operator Actions, Transition to 1-ES-0.1, Reactor Trip Response, and perform a brief.
Verifiable Actions:
: 1)    RO will attempt to trip the reactor using both reactor trip pushbuttons.
: 2)    RO will check or place rods control in automatic.
: 3)    RO will manually trip the turbine.
: 4)    RO verifies control rods inserting at >48 steps per minute.
: 5)    When rod speed lowers to < 48 steps per minute; RO places rod control in manual and inserts rods.
Critical Task:
CT-1: DRP-049 E-12, Insert negative reactivity into the core by at least one of the following methods before completing the Immediate Action Steps of FR-S.1.
Insert Control Rods in auto or manual within 30 seconds of the onset of the ATWS event.
Event #8:  LOCA Outside of Containment. (M - ALL)
The Team will be alerted to this condition based upon alarms and indications received, return to 1-E-0, and manually Safety Inject.
The RO and SRO continue with E-0 while the BOP performs Attachments 1, 2, and 3 of E-0. The Team will transition from 1-E-0 to 1-ECA-1.2, LOCA Outside Containment. In 1-ECA-1.2, the LOCA will be isolated by closing 1-SI-MOV-1890C, common LHSI pump discharge to RCS Cold Legs. The Team will transition to 1-E-1, Loss of Reactor or Secondary Coolant.
 
Appendix D                                  Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #4 Verifiable Actions:
: 1) RO will manually initiate SI.
: 2) During performance of 1-E-0 Attachments the BOP will identify and correct the following items: 1-SI-P-1A not auto start, 1-CH-MOV-1115D not auto open, 1-CH-MOV-1115C not auto close, 1-CH-MOV-1289A not auto close, 10CV-TV-150A and 1-CH-TV-1204A not auto close.
Critical Task:
CT-2: Critical Task: E 1.2. Trip all RCPs within 5 minutes of reaching RCP Trip Criteria. (WOG E-1-C).
CT-3: WOG ECA-1.2A, Isolate the LOCA outside containment before transition out of ECA-1.2, or cavitation of any LHSI pump. SPS- Isolate LOCA outside containment before transition out of ECA-1.2 (PSA).
Post Scenario Classification:
Follow-up Classification: Site Area Emergency, FS-1.1.
The Scenario can be terminated upon 1-E-1 entry or Lead Evaluator Cue.
 
Appendix D                                                Scenario Outline                                        Form ES-D-1 NRC EXAM - SCENARIO #4 Initial Conditions: IC #1 100%, MOL - Cycle 26. The unit has been at 100% power for > 30 days Pre-load malfunctions: (Trigger 30s) o SI2402, SI RELAY SI2A FAILS TO ACTUATE o SI2405, SI RELAY SI5A FAILS TO ACTUATE o AAC_SMS_MODE, OFF, AAC DG LOCAL MODE SWITCH POSITION o CC1801, DISABLE CCP1A AUTO START o SW_25J10_RF, 1-CC-P-1D CONTROL SWITCH, PTL Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:
Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:
AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
1-CC-P-1D id tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
Turnover:
Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. . IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* 1-CC-P-1D, D CC pump tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
* Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
* A BAST at 8.0 W/%.
* PSA id Green.
Event      Malf. #s      Severity                            Instructor Notes and Required Feedback 1              N/A            N/A        Deleted.
2            RC4802,        +1 Deg        1-RC-PT-1445 fails high, PRZR Pressure channel fail high. AP-31.00, Increasing or Decreasing RCS Pressure.
3            MS1305,        +1 Deg        Steam Pressure Channel III, B SG fails High. 0-AP-53.00, Loss of Vital Instrumentation/Controls.
4            CH2101,        +1 Deg        Failure of VCT Level Channel LT-115 High.
CC0302          TRUE 5            CC0802                        Overcurrent on B CC pump with breaker mechanically stuck closed causing the TRUE          trip of Stub Bus Supply breaker.
SW_15J9_
RF            TRIP 6            RD1236                        Dropped Rod Control Bank C, Group 1; AP-1.00, Rod Control Malfunction, AP-TRUE        23.00, Rapid Load Reduction.
: 7.          RC MOV 30%
RC Loop C Tc MOV disc falls into flow stream, Valid First-Out received, No Auto 595                        or Manual Reactor Trip. 1-FR-S.1, Response to Nuclear Generation/ATWS.
TRUE RD17 SI1502,        40% Deg 8          SI1603            TRUE          LOCA outside of Containment in Unit 1 Valve Pit Area.
SI1606            TRUE
 
Appendix D                                Scenario Outline                                      Form ES-D-1 NRC EXAM - SCENARIO #4 9      SI2402              SI Relay SI2A fails to Actuate, SI Relay SI5A Fails to Actuate;1-SI-P-1A not auto SI2405      C - BOP  start, CH-MOV-1115D, CH-MOV-115C, CH-MOV1289A, CV-TV-150A, and CH-TV-1204A fail to re-position of SI.
Scenario Objectives:
A. Deleted.
B. Given a failure of 1-RC-PT-1445 in the high direction respond IAW AP-53.00/AP-31.00 to regain control of RCS pressure.
C. Given the failure of Steam Pressure Channel III, B SG fails High repons IAW 0-AP-53.00, Loss of Vital Instrumentation/Controls.
D. Given the failure of VCT level 1-CH-LI-1115 high, respond IAW AP-53.00 to secure the divert of letdown flow to the PDTT.
E. Given the loss of the 1J stub bus, respond IAW 1K-H4 to restore CC flow to normal on Unit 1.
F. Given a dropped rod, respond IAW AP-1.00 and AP-23.00 to ramp the Unit to 70-74%.
G. Given a valid reactor trip signal with no automatic reactor trip respond IAW FR-S.1 to shutdown the reactor.
H. Given a LOCA outside of Containment respond IAW E-0 and ECA-1.2 to isolate the RCS leak path.
I. Given various component failing to reposition utilize E-0 Attachments to identify and place the components in the correct position.
 
SHIFT TURNOVER INFORMATION OPERATING PLAN:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* 1-CC-P-1D is tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
Shift orders are to maintain 100% power on Unit #1.
The last shift performed two 35 gallon dilutions followed by a manual makeup for training.
A BAST at 8.0 W/%.
PSA is Green.
 
Appendix D                              Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                    Event No.: 1          Page 11 of 98 Event
 
== Description:==
Perform 1-OP-RP-001. Section 5.2, Preparation for Channel II Testing.
Cue: When team ready.
Time        Position                              Applicants Action or Behavior EVENT 1 - Deleted
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 4                    Event No.: 2                    Page 12 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
Note:  An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.
The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.
A facility representative will be present for consultation with the Evaluation Team, as needed.
Time        Position                                  Applicants Action or Behavior RO        Diagnoses the event using the following:
Alarms:
1C-F8, PRZR HI PRESS 1D-H4, PRZR SFTY VV PWR RELIEF VV OPEN Indications:
1-RC-PCV-1456, PRZR PORV, RED Open Lights LIT.
RCS Pressure Decreasing.
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS Note: SRO may directly enter 1-AP-31.00, Increasing or Decreasing RCS Pressure, Page 14.
RO        [1] Check REDUNDANT INSTRUMENT CHANNEL(S) INDICATION - NORMAL Identifies RCS Pressure decreasing using 1-RC-PI-1444 or RCS Wide Range Pressure Indicated on A / B ICCM Display.
RO        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-RC-PV-1456 control switch in Close. Verifies 1-RC-PCV-1456 closes by GREEN Light LIT, RED Light off.
RO/BOP            During pressure transient, the Rod Control Switch may be placed in MANUAL due to Rods stepping OUT due to pressure coefficient.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 2                    Page 13 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00 SRO      *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO          Identify that reactor power is less than 100%.
SRO      Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO      *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
* PRZR Pressure Control, Step 5 RO      The RO will identify that 1-RC-PI-1445 failed high.
NOTE: RCS pressure decrease will cause a slight decrease in RCS Tave due to negative reactivity from the moderator pressure coefficient.
SRO      5        CHECK PRZR SPRAY VALVE CONTROLLERS - NORMAL RO          RO identifies PRZR Spray Valves controllers normal.
SRO      6  GO TO ( )-AP-31.00, INCREASING OR DECREASING RCS PRESSURE SRO announces transition to AP-31.00.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 2                    Page 14 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior 1-AP-31.00 SRO      [ 1 ] ___ CHECK PRZR PORVS - CLOSED RO      Identifies 1-RC-PCV-1456 closed.
1-AP-31.00 Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-31.00 1-AP-31.00 CAUTION: A Safety Injection may occur if the unit is not tripped prior to RCS pressure decreasing below 2100 psig.
SRO      2    CHECK RCS PRESSURE - DECREASING RO      Identifies RCS Pressure rising following PORV Closure.
2 RNO IF RCS pressure is stable or increasing following PORV closure, THEN GO TO Step 10.
Note: If the RO responds to Step as conditions were prior to PORV closure, this flow path is incorrect and a follow-up may be required.
1-AP-31.00 SRO      10 CHECK RCS PRESSURE - STABILIZING AT OR TRENDING TO 2235 PSIG RO      Identifies RCS pressure trending to 2235 psig.
1-AP-31.00 SRO      11. GO TO STEP 17
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 2                    Page 15 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
1-AP-31.00 SRO      17 CHECK MASTER CONTROLLER                                  GO TO Step 19
                              - IN MANUAL RO      Identifies Master Pressure Controller in Auto 1-AP-31.00 SRO 19 CHECK PRZR PORVS - EITHER INOPERABLE
* 1-RC-PCV-1455C
* 1-RC-PCV-1456 RO      Identifies 1-RC-PCV-1456 Inoperable.
1-AP-31.00 20 CLOSE BLOCK VALVE FOR INOPERABLE PORV SRO
* 1-RC-MOV-1535 if 1-RC-PCV-1456 inoperable RO      Places 1-RC-MOV 1535 control switch in close. Monitors MOV until GREEN indicating light LIT and RED Light out.
1-AP-31.00 SRO      21 CHECK PRZR PORVS - EITHER                                  GO TO Step 23 INCAPABLE OF BEING MANUALLY CYCLED
* 1-RC-PCV-1455C
* 1-RC-PCV-1456 RO      States Both PORVs are capable of being manually cycled.
1-AP-31.00 SRO      23 NOTIFY THE FOLLOWING:
* OM on call
* STA
* I&C Notifies Shift Manager of the Event and requests notifications be made.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 2                    Page 16 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
1-AP-31.00 SRO      24 REFER TO TECH SPECS:
* 3.1.A.5
* 3.1.A.6
* 3.1.C
* 3.12.F
: 1) The SRO will consult Tech Specs, TS Section 3.1.A.6, and determine that 1-RC-PCV-1456 is Inoperable but capable of being manually cycled, and enter a one hour clock to close the block valve for the PORV. The block valve will remain energized.
: 2) Further consultation will find Tech Spec 3.12.F.1 to restore RCS pressure >2205 psig in 2 hours or reduce Thermal Power to less than 5% in the next 6 hours. The Core Operating Limits Report (COLR, DRP-21) provides the reference for 2205 psig RCS pressure.
NOTE: Following closure of block valve the 1 hour Tech Spec clock clears. RCS pressure decreases to < 2205 psig during the transient; once the PORV has been closed, pressure recovers quickly and goes above 2205 psig.
SRO updates the Team concerning the identified items in Tech Specs and updates the Shift manager.
1-AP-31.00 SRO      25 REVIEW APPLICABILITY:
* VPAP-2802
* EAL Matrix SU6.1 SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.
1-AP-31.00 SRO      26        RESTORE PRESSURE CONTROL SYSTEM(S) TO NORMAL END EVENT 2
 
Appendix D                                  Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 3                  Page 17 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior 0-AP-53.00 BOP        Diagnoses failure 1-MS-PT-1485 with the following indications/alarms:
Alarms:
* 1H-E6 STM GEN 1B FW >< STM FLOW
* 1F-C8 STM GEN 1B CH 3 FW < STM FLOW
* 1H-G6 STM GEN 1B LVL ERROR.
Indications:
* Step increase in 1B SG Steam Flow indication CH-III
* Increasing level on B SG.
0-AP-53.00 SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS 0-AP-53.00 BOP        [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL BOP identifies Channel IV indication for steam flow/Steam Pressure is NORMAL 0-AP-53.00 BOP        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and lowers demand (FF < SF) to restore level to program
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 3                    Page 18 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00.
0-AP-53.00 SRO        *3        VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO        Identify that reactor power is less than 100%.
Note:    Based on the feed flow > steam flow mismatch during initial stage of the Event, Calorimetric power may exceed 100% during restoration of B SG NR level to program.
0-AP-53.00 SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
0-AP-53.00 SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
SG Pressure, Step 7 BOP            States B SG Pressure affected.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 3                    Page 19 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.
SRO        7. CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS -
NORMAL
* Steam Pressure
* Steam Flow
* Feed Flow
* Steam Generator Level BOP        Determines CH III Steam pressure instrumentation for B SG is NOT normal.
Step 7. RNO IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level Control system has failed, THEN do the following:
a)  Place the associated Feed Reg Valve in MANUAL.
BOP        Verifies B SG MFRV controller, 1-FW-FCV-1488, in manual b) Control SG level at program level (44%, a band will be given).
BOP        Verifies B SG NR level is returning to program level.
c) Select the redundant channel for affected SG(s)
RO        Selects Channel IV Steam Flow for B SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV).
d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.
BOP        Places B SG FRV controller, 1-FW-FCV-1488, in automatic control
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 3                    Page 20 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        Step 7. RNO (Continued)
Perform follow-up actions:
a)  Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.
b) Refer to the following Tech Spec 3.7 items:
* Table 3.7-1, 12 and 17
* Table 3.7-2, 1.c, 1.e, and 3.a
* Table 3.7-3, 2.a, and 3.a
: 1) Tech Specs Section 3.7, Table 3.7-1, Item 17, Low steam generator water level with steam/feedwater flow mismatch, Operator Action 6. With the number of Operable channels one less than the total number of channels, Power Operation may proceed provided the channel is placed in the trip condition in 72 hours, the channel may be bypassed for 12 hours for surveillance; if these requirements are not met, the Unit must be placed in Hot Shutdown within 6 hours.
: 2) Tech Spec 3.7, Table 3.7-2, Item 1.c., High differential pressure between any steam line and the steam header, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours; the channels may be bypassed for 12 hours for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours and reduce RCS temperature and pressure to less than 350&deg;F/450 psig in the following 12 hours.
: 3) Tech Spec 3.7, Table 3.7-2, Item 1.e.1 and 1.e.3, High Steam line flow in 2/3 steam lines coincident with low Tavg or low line pressure, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours; the channels may be bypassed for 12 hours for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours and reduce RCS temperature and pressure to less than 350&deg;F/450 psig in the following 12 hours.
: 4) Tech Spec Table 3.7-3, item 2a, Steam Line Isolation. Refers to Tech Spec Table 3.7-2, Item 1.e. See Above
: 5) Tech Spec Table 3.7-6, Item 16, SG Pressure, 2 per SG are required. This condition is met (2 of 3 channels still Operable).
c)  Refer to Attachment 1.
d) IF no other instrumentation failure exists, THEN GO TO Step 13.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 3                    Page 21 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        13. CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001.
SRO/RO reviews OPT-RX-001, Attachment 4, and determines Calorimetric is NOT impacted and OPT-RX-007 will NOT need to be performed.
0-AP-53.00 SRO        14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 16 if not Reg. Guide 1.97)
SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-MS-PT-1485 is a Reg. Guide 1.97 component.
0-AP-53.00 SRO        15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
[CEP 99-0029 requires two channels of Steam Pressure indication per steam generator, refers to Tech Spec 3.7, Table 6, Item 16, 2 required per SG.]
0-AP-53.00 SRO        16. Review the following:
* TS 3.7 Determines Table 3.7-1 item 17, 3.7-2 item 1.c. and 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours). Also TS-3.7, Table 6, item 16, two SG Pressure Indicators per SG.
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
[VPAP-2802 and TRM Section 3.3 are not impacted by this failure.]
 
Appendix D                                Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 3 Page 22 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS BOP        Reports no additional failure exists SRO        GOES TO Step 19 0-AP-53.00 SRO        19. PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C END EVENT #3
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 4                    Event No.: 4                    Page 23 of 98 Event
 
== Description:==
Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.
Cue: When initiated by Team Time        Position                                  Applicants Action or Behavior Diagnoses failure 1-CH-LT-1115 with the following indications/alarms:
BOP Alarms:
* 1D-G1 VCT HI - LO LVL Indications:
* 1-CH-LCV-1115A Amber Divert light LIT.
* Decreasing VCT level on channel 1-CH-LI-1112.
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS RO        [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL RO identifies Channel LI-1112 VCT Level indication is NORMAL.
RO        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION RO places the control switch for 1-CH-LCV-1115A in NORM position to close the VCT Divert Valve. Monitors to ensure amber light extinguishes and VCT level stabilizes.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00.
SRO        Note: Discusses with RO control of VCT level and monitoring of channel 1-CH-LT-1112 to ensure that VCT level will not drop to the point where the CH pumps could air bind. The SRO will set a band for manual makeup to the VCT and a minimum VCT level where the manual swap to the RWST will be required.
 
Appendix D                                    Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 4                    Event No.: 4                  Page 24 of 98 Event
 
== Description:==
Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.
Cue: When initiated by Team SRO        *3        VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO        Identify that reactor power is less than 100%.
SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
VCT Level, Step 12e RO SRO        12 e)      VCT level Instrumentation - NORMAL RO            States 1-CH-LT-1115, VCT Level Channel affected.
SRO        Refer to Attachment 6 Attachment 6, 0-AP-53.00 SRO            If ( )-CH-LT-( )115 fails high, ( )-CH-LCV-( )115A will open. Manual control of the blender will be required. Automatic swap-over of the CHG pump suction from the VCT to the RWST will not function.
: a. VCT High level divert of ( )-CH-LCV-( )115A to PDT at 85%
: b. VCT High level alarm at 82%
: c. Auto makeup to VCT stop at 34%
: d. Auto makeup to VCT start at 27%
: e. VCT Low level alarm at 24%
: f. CHG pump suction swap over to the RWST at 13% (2/2)
SRO            Note: Discusses with RO control of VCT level and monitoring of channel 1-CH-LT-1112 to ensure that VCT level will not drop to the point where the CH pumps could air bind. The SRO will set a band for manual makeup to the VCT and a minimum VCT level where the manual swap to the RWST will be required.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 4                  Event No.: 4                Page 25 of 98 Event
 
== Description:==
Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.
Cue: When initiated by Team SRO        13 CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001 SRO/RO            SRO/RO determines that OPT-RX-001, Attachment 4, is NOT impacted and OPT-RX-007 will NOT need to be performed.
: 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 SRO              VARIABLE (Go to Step 16 if not Reg. Guide 1.97)
The STA will report that 1-CH-LI 1115 is a Reg. Guide 1.97 component.
SRO        15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
[CEP 99-0029 requires 1 channel of VCT level indication. 1-CH-LT-1112 may be used as an alternate indication. Restore 1-CH-LT-1115 before the next outage.]
SRO        16. Review the following:
* TS 3.7
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO            SRO will consult Tech Specs and find no items affected.
SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
[VPAP-2802 and TRM Section 3.3 are not impacted by this failure.]
0-AP-53.00 SRO        17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS BOP        Reports no additional failure exists SRO        GOES TO Step 19
 
Appendix D                                Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                Event No.: 4 Page 26 of 98 Event
 
== Description:==
Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.
Cue: When initiated by Team
: 19. PROVIDE NOTIFICATIONS AS NECESSARY:
SRO
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C END EVENT #4
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                    Page 27 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior TEAM        Diagnose the failure using the following:
Alarms:
1K-D5, CC PP 1B IN LOCAL CONTROL OR OL TRIP 1K-E7, CC PPS DISCH HDR LO PRESS 1K-H4, 4KV EMERG BUS STUB BUS TIE BKR TRIP Indications:
Breaker 15J9, 1J Stub Bus Breaker, indicates Open on PCS Breaker 15J10, 1-CC-P-1B breaker indication RED and GREEN Light OFF.
1-CC-P-1B amps indication at 0. 1-CC-P-1A not running.
Note: ARP Steps start on Page 30.
Note: If the Team opts to trip the reactor, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-AP-10.07 SRO SRO will hold a Transient Brief and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
Directs the BOP to review ARPs for Lit annunciators, SRO/RO will continue with 1-AP-10.07.
Directs RO/BOP to contact Auxiliary Building Operator to check status of 1-CC-P-1A and 1-CC-P-1B. Direct Service Building Operator to check status of 1-CC-P-1B breaker, BKR 15J10, and the 1J stub bus breaker, 15J9.
Completes Brief and continues with AP-10.07.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                      Event No.: 5                  Page 28 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
Step 1, 1-AP-10.07 SRO      NOTE:
* If both units are affected, local actions should be coordinated.
* The AAC Diesel Generator will automatically start if an undervoltage occurs on Transfer Buses D and F.
* With Degraded Voltage or Undervoltage on 2J Bus, or a loss of Unit 2B DC Bus, Breaker 15J3 will not close automatically, except with a valid Unit 1 SI signal.
* EPIPs may be applicable.
: 1. CHECK UNIT - BLACKOUT HAS OCCURRED
* Transfer Buses D and F - DEENERGIZED AND
* All Station Service Buses - DEENERGIZED RO          Reports Blackout has not occurred.
SRO      GOES TO Step 39.
Step 39, 1-AP-10.07 SRO      39 CHECK THE FOLLOWING BREAKERS - ANY OPEN:
* 15D1 OR
* 15F1 OR
* 15H8 OR
* 15J8 RO          Reports Breakers Closed.
39 RNO      IF all 480V Emergency Buses energized, THEN GO TO Step 75.
SRO      Goes to Step 75.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                  Event No.: 5                  Page 29 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
Step 75, 1-AP-10.07 SRO      75 CHECK ANY STATION SERVICE BUS - DEENERGIZED:
* 15A1 and 15A2 - OPEN OR
* 15B1 and 15B2 - OPEN OR
* 15C1 and 15C2 - OPEN RO      Reports breakers 15A2 / 15B2 / 15C2 closed.
SRO      75 RNO      IF ALL 480V Station Service Buses are energized, THEN GO TO Step 97.
SRO          Goes to Step 97.
Step 97, 1-AP-10.07 SRO      97 NOTIFY THE FOLLOWING:
* OMOC
* STA
* Electrical Foreman ARP 1K-D5 BOP      1  CHECK 1-CC-P-1B IN LOCAL CONTROL DUE TO PLANT EVOLUTION 1-CC-P-1B not in Local due to Plant Evolution.
No Plant evolution in progress.
IF 1-CC-P-1B tripped due to leak or rupture, THEN do the following:
No leak or rupture indicated.
IF leak or rupture NOT present, THEN GO TO Step 3.
Go to Step 3
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                      Page 30 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
ARP 1K-D5 BOP      3. VERIFY STANDBY CC PP - STARTED
* 1-CC-P-1A No, 1-CC-P-1A not running Consults SRO concerning Manual start of 1-CC-P-1A.
Announces and Starts 1-CC-P-1A.
ARP 1K-D5 BOP      4 CHECK 1-CC-P-1B - TRIPPED DUE TO UNDERVOLTAGE ON THE 1J EMERGENCY BUS Do the following:
a) IF CC pump NOT tripped, THEN do the following:
b) Locally check breaker 15J10.
c) Locally check 1-CC-P-1B.
BOP          When local status of 1-CC-P-1B received, Focus Brief to inform Team that 1-CC-P-1B normal; 1-CC-P-1B breaker is closed, breaker 15J10 closed with an overcurrent trip flag, breaker 15 J9, stub bus breaker, is open with an overcurrent trip flag.
d) IF unable to restore 1-CC-P-1B, THEN do the following:
: 1) Initiate a Condition Report.
: 2) Review Tech Spec 3.13.
: 3) GO TO Step 7.
ARP 1K-D5 BOP      7  VERIFY CC SYSTEM PARAMETERS - NORMAL
* CC Surge Tank Level - STABLE
* CC Pump amps - STABLE
* AUX BLDG and CTMT Sump levels - NORMAL Review parameters, identify no trends exist, report parameters as normal.
ARP 1K-D5 BOP      8  PROVIDE NOTIFICATIONS:
* OMOC
* STA Inform SRO to Notify OMOC and STA.
Move to next ARP.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                    Page 31 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
ARP 1K-E7 BOP      1  VERIFY CC HEADER PRESSURE - LESS THAN 90 PSIG
* PI-CC-100, CC PP DISCH PRESS Reports PI-CC-100 indicates approximately 100 psig.
Step 1 RNO Do the following:
a) Increase surveillance of CC parameters.
b) Initiate a Work Request.
c) GO TO Step 18.
ARP 1K-E7 BOP      18      NOTIFY SHIFT SUPERVISION Notifies SRO, ARP 1K-E7 complete, a CR is required.
Moves to 1K-H4 ARP ARP 1K-H4 BOP      1  VERIFY ALARM - LOSS OF EMERGENCY BUS
* Bus 1H Undervolt - 15H8 TRIPPED OR
* Bus 1J Undervolt - 15J8 TRIPPED Identifies 1H and 1J not tripped Step 1 RNO Do the following:
a) Check for loss of Stub Bus loads:
* CC Pump
* RHR Pump Identifies Stub bus loads have been lost.
Step 1 RNO b) IF Stub Bus loads lost, THEN do the following:
: 1) Start standby pumps IAW Shift Supervision direction.
: 2) Locally check stub bus tie breaker cubicles in ESGR.
: 3) IF Stub Bus Breaker Cubicle Relays (Type IAC) orange drop - IN, THEN GO TO Step 4.
Based on Focus Brief - Goes to Step 4.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                      Page 32 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
ARP 1K-H4 BOP      4        CHECK RHR AND CC - RESTORED AS NECESSARY Identifies 1-CC-P-1A running.
ARP 1K-H4 BOP      5    PROVIDE NOTIFICATIONS AS NECESSARY:
* OMOC
* Electrical Foreman
* Control Operations
* Shift Supervision Notifies SRO that in addition to previous individuals notified, the Electrical Forman needs to be notified ARP 1K-H4 BOP      6    SUBMIT A CONDITION REPORT Notifies SRO that a CR is required.
ARP 1K-H4 BOP      7  REVIEW TECH SPECS Notifies SRO to Review Tech Specs SRO      The SRO will consult Tech Specs 3.13.A.2 and 3.13.B, and determine that the minimum Operable CC pumps requirement is not met. For 2 Unit operation, 3 CC pumps must be operable, and TS 3.13.B cannot be met, the SRO should identify a TS 3.01, 6 hour clock to HSD, and a 30 hour clock to CSD.
Consult Tech Spec 3.5.A.1 and determine the Minimum Operable RHR pumps requirement is not met. This requires, IAW TS 3.5.B, that a 14 day clock be entered to restore A RHR pump to an Operable condition.
[TRM Table 3.7.9-1; IAW TRM 3.7.9.A, additional 72 hour and 14 day clocks are in effect to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.]
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                  Page 33 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
SRO          Directs STA to review Tech Specs and TRM.
STA          Acknowledge direction to review Tech Specs and TRM. STA will report TRM has been reviewed and discussed with the Shift Manager.
SRO      Contacts the Shift Manager to provide an update on Plant Status, Tech Spec Clocks entered, and request notification of the OMOC and Electrical Foreman.
END EVENT #5
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 6                  Page 34 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior Team      Diagnoses the dropped rod with the following indications/alarms:
Alarms:
* 1G-B5, COMPUTER PRINTOUT ROD CONT SYS.
* 1G-C4, UPPER ION CHAMBER DEVIATION OR AUTO DEFEAT <50%.
* 1G-D4, LOWER ION CHAMBER DEVIATION OR AUTO DEFEAT <50%.
* 1G-E4, NIS PWR RNF CH AVG FLUX DEVIATION.
* 1C-B8 - PRZR LO PRESS
* 1G-H1 - NIS DROPPED ROD FLUX DECREASE > 5% PER 2 SEC
* 1G-H2 - RPI ROD BOTTOM <20 STEPS
* 1G-F8, ROD BANK D WITHDRAWAL.
Indications:
RO
* Outward Rod Motion.
* RCS Temperature and Pressure decrease.
* Flux Variations (radial).
* CERPI indication that Control Rod M-4 is at 0 steps.
In accordance with the immediate actions of 1-AP-1.00 (Rod Control System Malfunction) the RO will place Control Rods in MANUAL to stop the outward rod motion.
RCS pressure <2205 psig places the unit in a 2 hour clock iaw TS. 3.12.F.1 (and COLR) - it is expected that the SRO will track this clock (entry/exit times).
0-AP-1.00 SRO        Enters 0-AP-1.00 (Rod Control System Malfunction).
SRO        CAUTION prior to Step 1:
* If Tave decreases below 530 &deg;F, 1-E-0, Reactor Trip or Safety Injection, must be implemented.
RO        [1] CHECK FOR EITHER OF THE FOLLOWING:
* Continuous rod withdrawal
* Continuous rod insertion RO will note that there was a continuous rod withdrawal.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                    Page 35 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
RO/BOP      [2] STOP ROD MOTION
: a. Put ROD CONT MODE SEL switch in MANUAL
: b. Verify rod motion - STOPPED RO will place control rods in MANUAL and note that Rods stopped moving.
0-AP-1.00 SRO        The team will hold a transient brief. During the brief the dropped rod will be discussed.
The RO and BOP will report out critical parameters, as per placard on Main Control Room Bench Board.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
0-AP-1.00 RO
: 3. CHECK ROD MOTION - DUE TO INSTRUMENTATION FAILURE
* First Stage Impulse Pressure
* Tave/Tref
* Nuclear Instrumentation RO will note that an instrumentation failure did not exist. The team will transition to the RNO for Step 3.
0-AP-1.00 RO
: 3. RNO If rod motion due to a dropped rod, THEN GO TO Step 6.
RO will note that dropped rod caused the rod motion.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                    Page 36 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
0-AP-1.00 RO
: 6. CHECK IF ANY ROD DROPPED:
* Annunciator ( )G-H2, RPI ROD BOTTOM  20 STEPS - LIT OR
* Annunciator ( )G-H1, NIS DROPPED ROD FLUX DECREASE  5%
PER 2 SEC - LIT OR
* Rod Bottom Lights - ANY LIT OR
* Any Rod On Bottom light - LIT OR
* Indication of a partially dropped rod in the core The RO will note that they have multiple indications of a dropped rod in the core.
0-AP-1.00 RO
: 7. CHECK REACTOR STATUS PRIOR TO FAILURE - CRITICAL 0-AP-1.00 RO        8. CHECK ONLY ONE ROD AFFECTED 0-AP-1.00 RO
: 9. CHECK REACTOR POWER - GREATER THAN 25%
0-AP-1.00 BOP/RO
: 10. CHECK UNIT CONDITIONS - STABLE 0-AP-1.00 RO
: 11. PLACE ROD CONTROL IN MANUAL 0-AP-1.00 RO/BOP
: 12. CHECK POWER RANGE NIs - ANY DROPPED ROD SIGNAL PRESENT 0-AP-1.00 BOP
: 13. RESET NIS DROPPED ROD SIGNAL IAW ATTACHMENT 4 Note: Attachment 4 of AP-1.00 is located on Page 40.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 4                    Event No.: 6                      Page 37 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
0-AP-1.00 RO
: 14. CHECK ANNUNCIATOR 1G-F8, ROD BANK D WITHDRAWAL - NOT LIT If alarm is LIT, then the RNO will direct the team to initiate Attachment 5 - This attachment follows attachment 4 at the end of this event.
Note: This may not be lit if the ROBOP quickly placed rods in MANUAL when withdrawing or ARP 1G-F8, Bank D Withdrawal, has been completed.
0-AP-1.00 SRO Note prior to Step 15:
* Quadrant power tilt may cause unit ramp requirements to be more restrictive.
0-AP-1.00 SRO
: 15. VERIFY QUADRANT POWER TILT RATIO
* Initiate Attachment 6, QUADRANT POWER TILT CALCULATION
* Review Technical Specification 3.12.B.6 SRO will direct the STA to perform the QPTR in accordance with Attachment 6 and review TS 3.12.
Summary of applicable Tech Specs are found following Step 18.
0-AP-1.00 SRO        Notes prior to Step 16:
* Checking that the unit is operating between Hot Zero Power and Hot Full Power, that there is only one fully dropped (less than 10 steps) control rod, and that all other rods are above the rod insertion limit, checks that adequate SDM exists.
* SDM must be re-verified using 1-OP-RX-001 every 12 hours after the control rod was dropped until the Reactor is shutdown or the rod is declared operable.
0-AP-1.00 SRO
: 16. VERIFY SHUTDOWN MARGIN (WITHIN ONE HOUR)
* The fully dropped rod (less than 10 steps) is the only inoperable rod AND
* All other rods are greater than the Rod Insertion Limit 0-AP-1.00 SRO
: 17. MAKE NARRATIVE LOG ENTRY THAT SDM IS MET
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 6                    Page 38 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
SRO        Caution prior to Step 18:
* Loop T is the most accurate measure of Reactor power with a mis-aligned rod, and must be monitored during the ramp and used as a basis for stabilizing power.
RO        18. CHECK REACTOR POWER - LESS THAN OR EQUAL TO 75%
Step 18 RNO actions:
Do the following:
: a. Reduce Reactor Power to between 70% - 74% within one hour.
: b. Reduce NIS High Flux trip setpoints to less than or equal to 85% within the following four hours.
: c. WHEN Reactor Power has been reduced, THEN GO TO Step 19.
The team will enter AP-23.00 to reduce reactor power.
Note: 0-AP-23.00, Rapid Load Reduction, actions start on page 42.
Evaluators Note: Go to EVENT 7 when the Examiner has seen a sufficient change in power level during the ramp in AP-23.00.
SRO        Applicable Tech Specs for Dropped Rod:
3.12.B.6:
If, except for operation at THERMAL POWER < 50% or for physics and control rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2%, then:
: c. Within 2 hours, either the hot channel factors shall be determined and the power level adjusted to meet the requirement of Specification 3.12.B.1, or
: d. The power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours.
: e. If the QUADRANT POWER TILT exceeds 10%, the power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 6                    Page 39 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
Applicable Tech Specs for Dropped Rod: (Continued) 3.12.C.3:
Startup and POWER OPERATION may continue with one control rod assembly inoperable provided that within one hour either:
: a. The control rod assembly is restored to OPERABLE status, as defined in Specification 3.12.C.1 and 2, or
: b. the shutdown margin requirement of Specification 3.12.A.3.c is satisfied.
: c. POWER OPERATION may then continue provided that:
: 1) either:
a) power shall be reduced to less than 75% of RATED POWER within one (1) hour, and the High Neutron Flux trip setpoint shall be reduced to less than or equal to 85% of RATED POWER within the next four (4) hours, or b) the remainder of the control rod assemblies in the group with the inoperable control rod assembly are aligned to within 12 steps of the inoperable rod within one (1) hour while maintaining the control rod assembly sequence and insertion limits specified in the CORE OPERATING LIMITS REPORT; the THERMAL POWER level shall be restricted pursuant to Specification 3.12.A during subsequent operation.
: 2) the shutdown margin requirement of Specification 3.12.A.3.c is determined to be met within one hour and at least once per 12 hours thereafter.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                Page 40 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
BOP        ATTACHMENT 4 of AP-1.00 - RESETTING NIS DROPPED ROD SIGNALS Perform the following for each NI with a dropped rod status light lit.
: 1. N41 RESET a)  Place the Power Range Test Switch in RESET.
b)  Check the Dropped Rod Status Light on N41 - NOT LIT.
c)  Return the Power Range Test Switch to NORMAL.
: 2. N42 RESET a)  Place the Power Range Test Switch in RESET.
b)  Check the Dropped Rod Status Light on N42 - NOT LIT.
c)  Return the Power Range Test Switch to NORMAL.
3    N43 RESET a)  Place the Power Range Test Switch in RESET.
b)  Check the Dropped Rod Status Light on N43 - NOT LIT.
c)  Return the Power Range Test Switch to NORMAL.
: 4. N44 RESET a)  Place the Power Range Test Switch in RESET.
b)  Check the Dropped Rod Status Light on N44- NOT LIT.
c)  Return the Power Range Test Switch to NORMAL.
: 5. Check annunciator ( )G-H1, NIS DROPPED ROD FLUX DECREASE >5% PER SEC - NOT LIT
: 6. Check annunciator ( )G-F8, ROD BANK D WITHDRAWAL - NOT LIT
: 7. IF ( )G-F8, ROD BANK D WITHDRAWAL is LIT, THEN initiate Attachment 5.
 
Appendix D                              Required Operator Actions              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 6      Page 41 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
BOP        ATTACHMENT 5 of AP-1.00 - RESPONSE TO ROD BANK D WITHDRAWAL
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 6                    Page 42 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
Time        Position                                  Applicants Action or Behavior 0-AP-23.00 TEAM        0-AP-23.00 (RAPID LOAD REDUCTION) Actions SRO      The team will hold a transient brief. During the brief, the upcoming ramp will be discussed.
The RO and BOP will report out critical parameters, as per placard on Main Control Room Bench Board. It is expected that the RO will discuss reactivity parameters associated with the ramp from the pre-planned ramp plans taking in account the conditions presented by the dropped rod.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
The following reactivity plan will be discussed for a ramp to 75%:
* Gallons of boric acid required as per plan - 146 gallons, Rate of 5.8 gpm.
* D control bank end at 197 steps, 1957 gallons PG to stabilize.
* Subtracted from the boration will be the equivalent boron added from the dropped rod - 9.5 gallons for each degree of Tave decrease - this should be about 42 gallons based on a 4.4&deg; temp decrease. This will be subtracted from the initial 146 gallons - therefore, approximately 104 gallons of boric acid are required to be added.
EVALUATOR NOTE: RO Emergency borates for 25 seconds which corresponds to
                        ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.
SRO      Caution Prior to Step 1:
* Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.
Notes Prior to Step 1:
* Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
* When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
* Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
* The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
* For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                  Page 43 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
0-AP-23.00 RO      1. TURN ON ALL PRZR HEATERS
: 2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:
BOP            a) Check turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.
RO            b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5&deg;F.
SRO/BOP          c) Check or place turbine in IMP IN as determined by Shift Supervision The SRO can choose IMP IN or IMP OUT.
d) Adjust SETTER to desired power level BOP e)  Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute) f)  Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) g) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.
SRO      3. CHECK EMERGENCY BORATION - REQUIRED The team may decide to emergency borate after the ramp has progressed to the point that Tave and Tref are matched (or close).
SRO      Note Prior to Step 4:
* Step 4 or Step 5 may be performed repeatedly to maintain Tave and Tref matched, Flux in band, and control rod position above the LO-LO insertion limit.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                    Page 44 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
0-AP-23.00 RO      4. PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:
a) Check or raise CHG flow to greater than 75 gpm b) Transfer the in-service BATP to FAST c) Open ( )-CH-MOV-( )350 d) Monitor EMRG BORATE FLOW
                                        *  ( )-CH-FI-( )110 e)    After required emergency boration, perform the following:
: 1) Close ( )-CH-MOV-( )350
: 2) Transfer the in-service BATP to AUTO
: 3) Restore Charging flow control to normal NOTE: RO Emergency borates for 25 seconds which corresponds to ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.
RO      5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.
SRO      Notes Prior to Step 6:
* If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
* RCS Tave must be maintained less than or equal to 577&deg;F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
* I & C should be contacted to provide assistance with adjusting IRPIs.
RO      6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                    Event No.: 6                Page 45 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
RO      *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.
BOP      8. MONITOR STEAM DUMPS FOR PROPER OPERATION 0-AP-23.00 SRO      9. NOTIFY THE FOLLOWING:
* Energy Supply (MOC)
* Polishing Building
* Chemistry
* OMOC SRO      10. EVALUATE THE FOLLOWING:
* EPIP applicability
* VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.
[VPAP-2802 and EPIP are not applicable for this event.]
SRO      11. CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR When reactor power has decreased >15%, then chemistry will be notified.
END EVENT #6
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                    Event No.: 6                  Page 46 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
Time        Position                              Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO      1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO      2. Adjust 1-CH-YIC-1113 to desired total gallons RO      3. Adjust 1-CH-FC-1113A to desired flow rate.
RO      4. Place the MAKE-UP MOD SEL switch in the BORATE position.
RO      5. Place the MAKE MODE CNTRL switch in the START position.
RO      6. Check proper valve positions.
RO      7. Adjust boration rate using 1-CH-FC-1113A, as necessary.
RO      8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.
a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.
b) Enter N/A for the remaining steps in this Attachment.
Attachment 5 is on the next page RO      9. Check controllers for Primary Grade water and Boric Acid are set correctly.
RO      10. Place the MAKE-UP MODE SEL switch in the AUTO position.
RO      11. Place the MAKE-UP MODE CNTRL switch in the START position.
RO      12. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                  Page 47 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
Time        Position                              Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions
: 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
: 2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
: 3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
: 4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
: 5. Place the MAKE-UP MODE CNTRL switch in the START position.
: 6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
: 7. Check proper valve positions.
: 8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position
: 9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
: 10. Check or place the control switches in the AUTO position.
: 11. Check controllers for Primary Grade water and Boric Acid are set correctly.
: 12. Place the MAKE-UP MODE SEL switch in the AUTO position.
: 13. Place the MAKE-UP MODE CNTRL switch in the START position.
: 14. Notify Shift Supervision of blender status.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 7                  Page 48 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
Time        Position                                  Applicants Action or Behavior Team      Diagnose the failure based on the following:
Alarms:
1E-B10, LOSS OF COOL FLOW PWR > P8, RED 1E-A3, RC LOOP 1C LO FLOW CH 1 1E-B3, RC LOOP 1C LO FLOW CH 2 1E-C3, RC LOOP 1C LO FLOW CH 3 Indications:
Low flow indication on C loop, CH-1, CH-2, CH-3 Reactor - Critical RO            Attempt to Trip the Reactor by pressing BB-1 and BB-2 Reactor Trip Pushbuttons.
GO TO FR-S.1 Critical Task: CT-1: DRP-049 E-12, Insert negative reactivity into the core by at least one of the following methods before completing the Immediate Action Steps of FR-S.1. Insert Control Rods in auto or manual within 30 seconds of the onset of the ATWS event.
Critical Step Start Time: ________________
1-FR-S.1 CAUTION: RCPs should not be tripped with Reactor power greater than 5%.
RO      [ 1]          VERIFY REACTOR TRIP:                Verify or place control rods in Auto.
a) Manually trip Reactor b) Check the following:
* All Rods On Bottom light - LIT
* Reactor Trip and Bypass Breakers -
OPEN
* Neutron Flux - DECREASING RO Identifies Reactor NOT Tripped, Performs RNO Action 1-FR-S.1 RO      [2]      MANUALLY TRIP THE TURBINE:
RO presses Both Turbine Trip Pushbuttons, Simultaneously.
* Verify all turbine stop valves - CLOSED
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 49 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-FR-S.1 RO      [3]      VERIFY CONTROL RODS - INSERTING IN AUTO AT GREATER THAN 48 STEPS /
MINUTE Critical Task Stop Time: ____________________
RO/BOP                Manually insert control rods.
When Rod Speed lowers, places Rods in MANUAL, and inserts Rods.
4    VERIFY AFW PUMPS RUNNING:
SRO a) MD AFW pumps - RUNNING BOP b) TD AFW pump - RUNNING IF NECESSARY BOP BOP check MD / TD AFW Pumps Running.
SRO 1-FR-S.1 SRO      5    INITIATE EMERGENCY BORATION OF RCS:
a) Verify CHG flow - GREATER THAN 75 GPM RO            Check CHG FLOW > 75 gpm.
b) Align boration path:
SRO                1) Put BATP in FAST RO            Places 1-CH-P-2A, A BAST Recirc Pump, in FAST.
SRO                2) Open 1-CH-MOV-1350 RO            Places control switch 1-CH-MOV-1350 in OPEN.
SRO                3) Verify emergency borate flow RO            Checks Flow on 1-CH-FI-1110 rises to 110 gpm.
SRO            c) Check PRZR pressure - LESS THAN 2335 PSIG RO            Checks RCS Pressure < 2335 psig using RCS NR or WR Pressure.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 50 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-FR-S.1 SRO      *6 CHECK IF SI INITIATED:                          GO TO Step 8 RO
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3
* A-F-4 Identifies SI NOT initiated, SRO GOES TO STEP 8.
1-FR-S.1 SRO      8          CHECK IF THE FOLLOWING TRIPS HAVE OCCURRED:
RO                  a) Reactor trip b) Turbine trip SRO            Directs BOP to contact Service Building Operator to locally open Unit 1 Reactor Trip Breakers.
NOTE: Two (2) Minutes will elapse from the time an Operator is dispatched to open the Reactor Trip breakers until the Simulator Operator Opens the breakers.
Based on Time Critical Operator Action.
1-FR-S.1 NOTE: If adverse CTMT conditions have been exceeded, the Gamma-Metrics Excore Neutron Monitor system (Source and Wide Ranges) should be used to monitor neutron flux for the duration of the event.
                        *9 CHECK REACTOR - SUBCRITICAL SRO a) Check power range channels - LESS THAN 5% [Gamma-Metrics Wide Range Power - LESS THAN 5%]
RO            Identifies Reactor Power < 5%.
b) Check Intermediate range channels - NEGATIVE STARTUP RATE [Gamma-Metrics Wide Range Power - DECREASING]
RO            Identifies negative SUR on IR Channels.
SRO            c) GO TO Step 18
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 51 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-FR-S.1 CAUTION:        Boration should be continued to obtain adequate shutdown margin during subsequent actions.
SRO      18 RETURN TO PROCEDURE AND STEP IN EFFECT SRO Announces Transition to E-0.
SRO            Directs Reactor Operator to perform E-0 Immediate Actions Steps.
1-E Reactor Trip or Safety Injection RO      [1] CHECK REACTOR TRIP:
a)  Manually trip reactor Pushes the reactor trip push buttons.
b)  Check the following:
* All Rods On Bottom light - LIT
* Reactor trip and bypass breakers - OPEN
* Neutron flux - DECREASING RO      [2] CHECK TURBINE TRIP:
RO            a)  Manually trip the turbine Pushes the turbine trip push buttons.
b)  Verify all turbine stop valves - CLOSED c)  Isolate reheaters by closing MSR steam supply SOV
* 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)
Identifies that Output Breakers did open RO      [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                    Page 52 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
[4] CHECK IF SI INITIATED:
RO            a)  Check if SI is actuated:
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3 SI INITIATED - TRAIN A
* A-F-4 SI INITIATED - TRAIN B RO      RO will determine that SI has NOT occurred and perform step 4a RNO actions:
4a RNO Check if SI is required or imminent as indicated by any of the following:
* Low PRZR pressure
* High CTMT pressure
* High steamline differential pressure
* High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.
RO reports Immediate Actions of E-0 are complete, SI not in service or required, and recommends transition to ES-0.1.
After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.
SRO      SRO will lead a brief using the brief checklist.
The RO will provide critical parameters using the Brief placard.
The BOP will provide critical parameters using the brief placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
The SRO will direct the BOP to perform ES-0.1, Transient AFW Control, Attachment 5 of ES-0.1, while the RO and SRO continue with ES-0.1.
Note: Attachment 5 of ES-0.1 is located at the End of this Section.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 53 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-ES-0.1 NOTE: Team may elect to secure the C RCP.
NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM SRO      GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.
                        *1 CHECK RCS TEMPERATURE CONTROL RO            a) Check RCPS - ANY RUNNING Reports all three RCPs running, C with abnormally low flow.
b) Monitor RCS Average Temperature
: 1) STABLE AT 547&deg;F OR RO            2) TRENDING TO 547&deg;F Reports RCS temperature stable at 547 &deg;F.
1-ES-0.1 SRO      2    CHECK FW STATUS:
a) Check RCS Average temperatures - LESS THAN 554&deg;F RO            Identifies RCS Temperature < 554 &deg;F b) Check Feed REG valves - CLOSED RO            Identifies all FRVs closed.
c) Close SG FW isolation MOVs
* 1-FW-MOV-154A
* 1-FW-MOV-154B
* 1-FW-MOV-154C RO/BOP          Close 1-FW-MOV-154 A / B / C d) Check AFW pumps - RUNNING
* Motor Driven AFW pumps
* TD AFW pump
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 54 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
BOP            Identifies MD / TD AFW pump running.
e) Check total AFW flow - GREATER THAN 540 GPM (350 GPM W/O RCPs)
BOP            Identifies AFW flow > 540 GPM (IAW band given by SRO) f) Check emergency buses - BOTH ENERGIZED RO            Identifies emergency buses energized.
g) Control feed flow to maintain narrow range level between 22% and 50%
BOP            Acknowledges direction to control AFW flow to obtain band.
1-ES-0.1 SRO      3        CHECK CHARGING IN SERVICE RO            Provides CH flow value and trend to SRO.
Note: If not already implemented, go to Event #8.
1-ES-0.1 SRO      4    CHECK CC SYSTEM STATUS:
a) Check SW to CC HXs - IN SERVICE RO            Identifies two (2) CC headers flowing to CC HXs.
b) Check CC pumps - AT LEAST ONE RUNNING RO            Identifies 1-CC-P-1A running.
1-ES-0.1 SRO      5    CHECK PRZR LEVEL CONTROL:
a) Check PRZR level - GREATER THAN 15%
RO            Reports PRZR level and trend to SRO.
b) Check letdown - IN SERVICE RO            Reports Letdown flow and trend to SRO.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 55 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
Time        Position                                Applicants Action or Behavior ES-0.1, Attachment 5 BOP      1    Maintain minimum AFW flow of 540 gpm with RCP(s) in service until one SG Narrow Range level is greater than 12%.
ES-0.1, Attachment 5 BOP      2    Maintain minimum AFW flow of 350 gpm with NO RCPs running, until one SG Narrow Range level is greater than 12%.
Throttles AFW to band provided by SRO.
ES-0.1, Attachment 5 NOTE: AFW to idle loop(s) (RCP secured), should be throttled to prevent depressurization of the SG and subsequent Header / Line SI. AFW flow between approximately 60 gpm and 100 gpm should be adequate to prevent a Header / Line SI.
BOP      3    When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50% by throttling AFW Isolation MOVs:
* SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
* SG B, 1-FW-MOV-151C and 1-FW-MOV-151D
* SG C, 1-FW-MOV-151A and 1-FW-MOV-151B ES-0.1, Attachment 5 BOP      4. Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves:
Emergency Bus H deenergized:  1-FW-141  1-FW-156  1-FW-171 Emergency Bus J deenergized:  1-FW-140  1-FW-155  1-FW-170 Identifies Bus H and J not deenergized.
End EVENT #7
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                  Event No.: 8                      Page 56 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
Time        Position                              Applicants Action or Behavior Team      Identify Failure based on the following:
Alarms:
1B-F3, SFGDS AREA SUMP HI LEVEL 1C-B-8, PRZR LO PRESS 1C-D8, PRZR LO LEVEL 1D-E5, CHG PP TO REGEN HX HI-LO FLOW RMA-D6, VENT STACK #2PART ALERT/HI RMA-D7, VENT STACK #2 NORM RNG GAS ALERT/HI Indications:
Lowering PRZR Level Rising CH flow NOTE: SRO may direct manual safety injection and return to E-0 due to degrading plant conditions.
1-AP-16.00 SRO      Direct RO to perform the Immediate Actions of 1-AP-16.00.
1-AP-16.00 RO      NOTE:
* If SI Accumulators are isolated, 1-AP-16.01, SHUTDOWN LOCA, should be used for guidance.
* RCS average temperature has a direct impact on pressurizer level.
[1]      MAINTAIN PRZR LEVEL:
* Isolate Letdown Closes 1-CH-LCV-1460 A / B
* Control Charging flow Takes Manual control of 1-CH-FCV-1122 and raises CH Flow.
RO          Reports that CH flow at maximum value and PZR level decreasing.
SRO          Direct RO to Re-perform the Immediate Action Steps of E-0, and Safety Inject on Step 4.
1-E-0 RO      [1]      CHECK REACTOR TRIP:
1-E-0
 
Appendix D                              Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                    Event No.: 8                      Page 57 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
RO      [2]      CHECK TURBINE TRIP:
1-E-0
[3]      CHECK BOTH AC EMERGENCY BUSES - ENERGIZED 1-E-0 RO      [4]      CHECK IF SI INITIATED:
a) Check if SI is actuated:
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3
* A-F-4 b) Manually initiate SI Report SI has been initiated, SI flow to the core, 1-E-0 Immediate Actions with SI complete.
1-E-0 SRO      Will Check off the Immediate Action Steps of 1-E-0.
SRO will conduct a commensurate Brief. Ensure the Team agrees that a LOCA outside of containment is in progress. Poll the Team as to any higher priority than continuing actions for a LOCA outside of containment.
SRO closes the brief.
Directs BOP to perform Attachments 1, 2, and 3 of 1-E-0. Attachment 1, 2, and 3 located in Event 9.
Continues with 1-E-0 with RO.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                  Event No.: 8                    Page 58 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
Time        Position                                Applicants Action or Behavior 1-E-0 RO      Identify RCS Subcooling < 30 &deg;F and SI flow indicated to all three loops.
SRO      Using 1-E-0 Continuous Actions Page:
: 1. RCP TRIP CRITERIA Trip all RCPs if BOTH conditions listed below occur:
: a. Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS
: b. RCS Subcooling - LESS THAN 30&deg;F [85&deg;F]
RO          Checks RCP Trip Criteria exist.
SRO          Directs RO to Trip all RCPs.
: 2. MINIFLOW RECIRC CRITERIA
: a. CLOSED - When RCS pressure is less than 1275 psig [1475 psig] AND RCP Trip Criteria are met (RCPs OFF).
RO          Identifies Criteria are met.
SRO          Direct RO to close mini-flow recirc valves.
CT-2: Critical Task: E 1.2. Trip all RCPs within 5 minutes of reaching RCP Trip Criteria. (WOG E-1-C).
CT-2: Start Time: _________.        CT-2: Stop Time: _________.
Note: Examiner will be notified by Simulator Operator when RCS Subcooling reaches 35&deg;F and Lowering for CT-2 Monitoring.
SRO      *6. CHECK RCS AVERAGE TEMPERATURE
* STABLE AT 547&deg;F OR
* TRENDING TO 547&deg;F
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 8                    Page 59 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
SRO      7. CHECK PRZR PORVs AND SPRAY VALVES:
a) PRZR PORVs - CLOSED b) PRZR spray controls
* Demand at Zero (or)
* Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN NOTE: Seal injection flow should be maintained to all RCPs.
SRO      *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO      Two or three Charging pumps will be running and flowing to the RCS.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RCS subcooling will be less than 30 &deg;F c) Stop all RCPs d) RCS pressure - LESS THAN 1275 psig [1475 PSIG]
e) Close CHG pump miniflow recirc valves:
* 1-CH-MOV-1275A
* 1-CH-MOV-1275B
* 1-CH-MOV-1275C Mini-flow recirc valves closed.
SRO      9. CHECK IF SGs ARE NOT FAULTED:
* Check pressures in all SGs a)  STABLE OR INCREASING AND b)  GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.
 
Appendix D                                Required Operator Actions                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 8  Page 60 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
SRO      10. CHECK IF SG TUBES ARE NOT RUPTURED:
* Condenser air ejector radiation - NORMAL
* SG blowdown radiation - NORMAL
* SG MS radiation - NORMAL
* TD AFW pump exhaust radiation - NORMAL
* SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER 11 CHECK RCS - INTACT INSIDE CTMT SRO
* CTMT radiation - NORMAL
* CTMT pressure - NORMAL
* CTMT RS sump level - NORMAL Reports RCS intact in side CTMT.
RO SRO      12 CHECK RCS - HAS BEEN MAINTAINED INTACT OUTSIDE CTMT a) Radiation Monitors - NORMAL
* MGPI vent-vent
* Auxiliary Building Control Area RO          Reports MGPI Vent-Vent in Alarm b) Sump annunciators - NOT LIT
* VSP-F-4
* B-D-1
* B-D-2
* B-F-3 Step 12 RNO Determine cause of abnormal conditions.
IF the cause is a loss of RCS inventory outside CTMT, THEN GO TO 1-ECA-1.2, LOCA OUTSIDE CONTAINMENT.
RO          Reports conditions caused by LOCA outside CTMT SRO          Transitions to ECA-1.2.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 8                        Page 61 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
Time        Position                                Applicants Action or Behavior 1-ECA-1.2 SRO          Performs a commensurate brief. Ensures Team assessment confirms event in progress is a LOCA outside CTMT. Polls Team concerning any abnormal condition that needs to be addresses of a higher priority than isolating the LOCA outside CTMT. When any issues are addressed, SRO closes brief and continues with ECA-1.2.
1-ECA-1.2 CAUTION: Depending on break location, higher than normal dose levels should be expected in the Auxiliary Building and the Safeguards after a LOCA outside CTMT.
SRO      1    VERIFY PROPER VALVE ALIGNMENT:
a) Locally unlock and close the following breakers:
* 1H1-2N 8A for 1-SI-MOV-1890A
* 1J1-2E 8B for 1-SI-MOV-1890B
* 1H1-2N 9A for 1-SI-MOV-1890C Directs the BOP to contact the Shift Manager/Desk SRO and have an operator briefed and dispatched to remove tags and close the breakers for 1-SI-MOV-1890 A / B / C.
NOTE: Booth will time compress this action when SM/Desk SRO contacted.
b) LHSI to hot legs - CLOSED
* 1-SI-MOV-1890A
* 1-SI-MOV-1890B When Valves Energized, the valves indicate closed.
c) SI accumulator test valves - CLOSED
* HCV-SI-1850A
* HCV-SI-1850B
* HCV-SI-1850C
* HCV-SI-1850D
* HCV-SI-1850E
* HCV-SI-1850F When Checked, Valves Indicate closed.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                  Event No.: 8                    Page 62 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
1-ECA-1.2 NOTE: The SRO is expected to have a Focus Brief prior to this step. The SRO will bring the BOP into the discussion concerning the expected response of the RCS SRO          when 1-SI-MOV-1890C is closed. If closure of this valves isolates the RCS break, RCS pressure and LHSI flow is expected to increase. If the break remains isolated, RCS pressure and LHSI flow will remain the same or decrease. The SRO will complete the brief and continue ECA-1.2.
2  TRY TO IDENTIFY AND ISOLATE BREAK:
a) Close LHSI to cold legs RO
* 1-SI-MOV-1890C Team          Shortly after closure of 1-SI-MOV-1890C, the Team should identify that RCS pressure and LHSI flow is increasing.
Critical Task:
CT-3: WOG ECA-1.2A, Isolate the LOCA outside containment before transition out of ECA-1.2, or cavitation of any LHSI pump. SPS- Isolate LOCA outside SRO      containment before transition out of ECA-1.2 (PSA).
RO          b) Check RCS pressure - INCREASING RO will identify RCS increasing.
c) Place LHSI pumps in PTL RO          Places LHSI pumps in PTL.
SRO          d) Close LHSI pump suctions from RWST
* 1-SI-MOV-1862A
* 1-SI-MOV-1862B Closes 1-SI-MOV-1862A / B.
e) GO TO 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT SRO Transitions to 1-E-1.
CRITICAL TASK STOP TIME ____________________
END EVENT 8                        END of Scenario 4
 
Appendix D                                Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                Event No.: 9          Page 63 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
Time        Position                              Applicants Action or Behavior ATTACHMENT 1 OF E-0 BOP      1. CHECK FW ISOLATION:
* Feed pump discharge MOVs - CLOSED
* 1-FW-MOV-150A
* 1-FW-MOV-150B
* MFW pumps - TRIPPED
* Feed REG valves - CLOSED
* SG FW bypass flow valves - DEMAND AT ZERO
* SG blowdown TVs - CLOSED BOP      2. CHECK CTMT ISOLATION PHASE I:
* Phase I TVs - CLOSED Identifies 1-CV-TV-150A, 1-CH-TV-1204A OPEN, Closes valves
* 1-CH-MOV-1381 - CLOSED
* 1-SV-TV-102A - CLOSED
* PAM isolation valves - CLOSED
* 1-DA-TV-103A
* 1-DA-TV-103B BOP      3. CHECK AFW PUMPS RUNNING:
a)  MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY
 
Appendix D                                Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 9            Page 64 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
Attachment 1 of E-0 BOP      4. CHECK SI PUMPS RUNNING:
* CHG pumps - RUNNING
* LHSI pumps - RUNNING Manually Starts 1-SI-P-1A.
BOP      5. CHECK CHG PUMP AUXILIARIES:
* CHG pump CC pump - RUNNING
* CHG pump SW pump - RUNNING
: 6. CHECK INTAKE CANAL:
BOP
* Level - GREATER THAN 24 FT
* Level - BEING MAINTAINED BY CIRC WATER PUMPS
: 7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:
a)  Check if ANY of the following annunciators - HAVE BEEN LIT
* E-F-10 (High Steam Flow SI)
* B-C-4 (Hi Hi CLS Train A)
BOP
* B-C-5 (Hi Hi CLS Train B)
Identifies annunciators not lit and goes to step 8.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 9                Page 65 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
BOP      *8 CHECK IF CS REQUIRED:
a)  CTMT pressure - HAS EXCEEDED 23 PSIA 8, a) RNO          Do the following:
: 1) IF CTMT pressure has exceeded 17.7 psia, THEN check or align the following valves:
Identifies CTMT pressure remains at normal pressure
: 2) GO TO Step 10.
Attachment 1 of E-0 BOP      *10. BLOCK LOW PRZR PRESS SI SIGNAL:
a)    Check PRZR pressure - LESS THAN 2000 psig b)    Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c)    Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.
BOP      *11. BLOCK LOW TAVE SI SIGNAL:
Step may not be performed at this time (if Tave is greater than 543&deg;F).
a)  Check RCS Tave - LESS THAN 543&deg;F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c)  Verify Permissive Status light F LIT
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 9                Page 66 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
NOTE:
* CHG pumps should be run in the following order of priority: C, B, A.
* Subsequent SI signals may be reset by re-performing Step 12.
BOP      12. CHECK SI FLOW:
a)  HHSI to cold legs - FLOW INDICATED
* 1-SI-FI-1961 (NQ)
* 1-SI-FI-1962 (NQ)
* 1-SI-FI-1963 (NQ)
* 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c)  Reset SI.
d) Stop one CHG pump and out in AUTO Attachment 1 of E-0 e)  RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:
: 1) Verify reset or reset SI.
: 2) Stop one LHSI pump and put in AUTO.
BOP      13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]
BOP      14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.
BOP      15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next Page of this guide)
Depending on timing, this attachment may have already been completed.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 9                      Page 67 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
BOP      16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2.
Unit 2 Operator will state that Unit 2 is at 100% power (if asked)
Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 9                    Page 68 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
Time        Position                              Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 BOP      NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.
ATTACHMENT 2 of 1-E-0 BOP      1. Check opened or open CHG pump suction from RWST MOVs.
* 1-CH-MOV-1115B
* 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 BOP      2. Check closed or close CHG pump suction from VCT MOVs.
* 1-CH-MOV-1115C
* 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 BOP      3. Check running or start at least two CHG pumps. (listed in preferred order)
* 1-CH-P-1C
* 1-CH-P-1B
* 1-CH-P-1A ATTACHMENT 2 of 1-E-0 BOP      4. Check opened or open HHSI to cold legs MOVs.
* 1-SI-MOV-1867C
* 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 BOP      5  Check closed or close CHG line isolation MOVs.
* 1-CH-MOV-1289A
* 1-CH-MOV-1289B
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 9                    Page 69 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
ATTACHMENT 2 of 1-E-0 BOP      6. Check closed or close Letdown orifice isolation valves.
* 1-CH-HCV-1200A
* 1-CH-HCV-1200B
* 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 BOP      7. Check opened or open LHSI suction from RWST MOVs.
* 1-SI-MOV-1862A
* 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 BOP      8. Check opened or open LHSI to cold legs MOVs.
* 1-SI-MOV-1864A
* 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 BOP      9. Check running or start at least one LHSI pump.
* 1-SI-P-1A
* 1-SI-P-1B ATTACHMENT 2 of 1-E-0 BOP      10. Check High Head SI flow to cold legs indicated.
* 1-SI-FI-1961
* 1-SI-FI-1962
* 1-SI-FI-1963
* 1-SI-FI-1943 or 1-SI-FI-1943A ATTACHMENT 2 of 1-E-0 BOP      11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.
* Alternate SI to Cold legs
* Hot leg injection End of Event 9 -. End of Scenario 4
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 70 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 71 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 72 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 73 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 9                      Page 74 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
Unit 2 will prompt BOP: MCR Boundary DP is the same as DP indicated on Unit 2 Ventilation Panel.
Unit 2 will prompt BOP: Unit 2 remains operating at 100%
power.
Unit 2 will assume responsibility for the Attachment action from this point.
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 75 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 76 of 98 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 77 of 98 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                                  Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                                Page 78 of 98 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:
Recall IC -264 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.
Ensure the Delta T Selector Switch is in the Channel II Position.
Ensure PRZR Level Recorder on Channel II.
Open the monitor window and add the following points to it:
* asp_ao_off
* CC_579 set at 0.38 Enter the following MALFUNCTIONS:
Trigger Malfunction                Delay    Ramp        Trigger  Value  Final      Type (Auto or Manual)
RC4802 PRZR PRESS CONT                    10        10            1    0        1          MAN XMTR FAILURE (445)
MS1305 SG B STM PRESSURE                  10        0            3    0        1          MAN TRNSMTR MS-PT-485 FAILURE CH2101 VCT LEVEL                          10        0            5    0        1          MAN TRANMITTER LT-1115 FAILS CC0302 CC PUMP 1-CC-P-1B                  10        0            7  FALSE    TRUE          MAN OVERCURRENT TRIP CC0802 CC-P-1B BKR 15J10                    0        0            7  FALSE    TRUE          MAN MECHANICALLY STUCK CLOSED RD1236 DROPPED RCCA, M-4,                  10        0            9  FALSE    TRUE          MAN CONTROL BANK C RD17 ATWS, WITH MANUAL RX                  0        0          11  FALSE    TRUE          MAN TRIP PB DEFEATED SI1502 SI COLD LEG HDR LEAK                10        0          13    0        40          MAN UPSTRM MOV-SI-890C SI1603 FAIL CHECK VALVES SI-              10        0          13  FALSE    TRUE          MAN 85 SI1606 FAIL CHECK VALVE SI-                10        0          13  FALSE    TRUE          MAN 243 LOOP C (LHSI)
SI2402 SI RELAY SI2A FAILS TO              0        0          30  FALSE    TRUE          MAN ACTUATE SI2405 SI RELAY SI5A FAILS TO              0        0          30  FALSE    TRUE          MAN ACTUATE CC1801 DISABLE CCP1A AUTO                  0        0          30  FALSE    TRUE          MAN START Enter the following Remote Functions:
 
Appendix D                        Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1              Scenario No.: 4                            Page 79 of 98 SIMULATOR OPERATORS GUIDE Remotes                            Set Condition                          Trigger SW_15J9_RF 4KV Stub                      TRIP, 20 Sec TD                            7 Bus BKR 15J9 Control Switch RCMOV595 RC-MOV-                  100 to 30, 0 Ramp, 10 Sec TD                    11 595 C Loop Cold Leg Isol SIMOV890A_BKR SI-                            CLOSED                                21 MOV-1890A LHSI To HOT Legs SIMOV890B_BKR SI-                            CLOSED                                22 MOV-1890B LHSI To HOT Legs SIMOV890C_BKR SI-                            CLOSED                                23 MOV-1890C LHSI To Cold Legs RX_RTA_OPEN                                TRUE                                16 RX_RTB_OPEN                                TRUE                                17 AAC_SMS_MODE OFF                                OFF                                30 AAC DG LOCAL MODE SWITCH POSITION EL12, SW_25J10_RF, Bkr                          PTL                                30 25J10 Control Switch, 1-CC-P-1D TRIGGER                  TYPE                                DESCRIPTION 1                  MAN      Przr Press Cont Xmtr Failure (445) Fails High 3                  MAN      SG B Stm Pressure Trnsmtr MS-FT-485 FAILS High 5                  MAN      VCT Level Transmitter LT-1115 Fails High OVERCURRENT Trip 1-CC-P-1B, BREAKER Stuck Closed, 15J9 7                  MAN Breaker Trips Open
 
Appendix D                    Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1            Scenario No.: 4                                Page 80 of 98 SIMULATOR OPERATORS GUIDE TRIGGER              TYPE                            DESCRIPTION 9                  MAN      Dropped RCCA, M-4, Control Bank C 11                  MAN      RC-MOV-595 C Loop Cold Leg Isol Disc Falls Into Flow Stream 11                  MAN      ATWS, WITH MANUAL RX TRIP PB DEFEATED SI Cold Leg HDR Leak Upstrm MOV-SI-890C, With Check Valves 13                  MAN Stuck Open
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                                    Page 81 of 98 SIMULATOR OPERATORS GUIDE Verify the following control room setup:
Place the simulator in RUN and verify normal 100% power operation indications.
Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:
Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).
Verify Ovation System operating.
Reset ICCMs.
Verify Component Switch Flags.
Verify Brass Caps properly placed.
Verify SG PORVs set for 1035 psig.
Verify Rod Control Group Step Counters indicate properly.
Verify Ovation CRT display.
Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)
Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:
AP-53.00            AP-1.00            AP-23.00                    AP-16.00 E-0                  ECA-1.2            1-OPT-RX-001                  AP-1.00, Att 6 (3)
OP-CH-007                                Reactivity Sheet OP-ZZ-002 Verify Reactivity Placard is current.
Verify ALL PINK MAGNETS are accounted for.
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                                  Page 82 of 98 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.
Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.
If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.
In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.
Assign operating positions.
Ask for and answer questions.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                                    Page 83 of 98 SIMULATOR OPERATORS GUIDE Conduct shift turnover:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* 1-CC-P-1D is tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
Shift orders are to maintain 100% power on Unit #1.
The last shift performed two 35 gallon dilutions followed by a manual makeup for training.
A BAST at 8.0 W/%.
PSA is Green.
When the team has accepted the shift, proceed to the Session Conduct Section.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 4                                Page 84 of 98 SIMULATOR OPERATORS GUIDE Session Conduct:
* Ensure conditions in Simulator Set-up are established.
* Ensure Trigger 30 is active prior to team entering the simulator.
* Verify Exam Security has been established and ASP_AO_OFF = True.
EVENT 1          Deleted EVENT 2          1-RC-PT-1145 Fails High, 1-AP-31.00/0-AP-53.00 When cued by examiner, implement Trigger #1.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of 1-RC-PT-1445. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00/AP-31.00.
* If contacted, acknowledge review of VPAP-2802 and EPIP SU6.1 review required.
* If contacted, will take responsibility for writing the CR.
STA:
* If contacted, will acknowledge the failure of 1-RC-PT-1445. The individual(s) contacted will also acknowledge (but not confirm/deny) any TS LCOs.
* If asked, the STA will review VPAP-2802, TRM Section 3.3, and SU6.1 review complete and discussed with Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Field Operators:
No feedback required for this failure.
 
Appendix D                              Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                              Page 85 of 98 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:
* If contacted, will acknowledge instrumentation failure and commence investigations.
Unit 2 Operator:
If Contacted, acknowledge the failure of 1-RC-PT-1445.
Role play as other individuals as needed.
 
Appendix D                                  Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                              Page 86 of 98 SIMULATOR OPERATORS GUIDE EVENT 3          Steam Pressure Fails High, B SG. 0-AP-53.00.
When cued by examiner, implement Trigger #3.
Operations Supervisor/Management:
* If contacted, will acknowledge that Failure of 1MS-PT-1485, Channel III, B SG, Steam Pressure. The individual(s) contacted will also acknowledge any TS LCOs.
* If asked, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into AP-53.00.
STA:
* If contacted, will acknowledge the Failure of 1MS-PT-1485, Channel III, B SG, Steam Pressure. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
* When asked, STA reports the failed channel is a RG 1.97 variable.
* When asked, SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
* When contacted, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Field Operators:
No feedback required.
 
Appendix D                            Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                            Page 87 of 98 SIMULATOR OPERATORS GUIDE Maintenance/ Work Week Coordinator:
* If contacted, will have I&C brief on placing the failed channel in trip.
Unit 2:
* If contacted, will acknowledge Failure of 1-MS-PT-1485, Channel III, B SG, Steam Pressure.
Role-play as other individuals as needed.
 
Appendix D                                Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                              Page 88 of 98 SIMULATOR OPERATORS GUIDE EVENT 4          Failure of VCT Level Channel LT-1115 High. 0-AP-53.00.
When Evaluator ready: Implement Trigger #5.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of 1-CH-LT-1115 high.
STA:
* If contacted, will acknowledge the failure of 1-CH-LT-1115 high.
* If asked, The STA will report that the failed channel is a Reg. Guide 1.97 variable.
* If asked, SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
* After directed, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Maintenance/ Work Week Coordinator:
* If contacted, will acknowledge the failure and commence investigations.
Field Operators: (Wait 4 minutes from time of direction to report).
* If contacted, to check the status of 1-CH-LT-1115 locally, report no obvious abnormal condition with the transmitter.
Unit 2:
* If contacted, will acknowledge the failure of 1-CVH-LT-1115 high.
Role-play as other individuals as needed.
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 4                                  Page 89 of 98 SIMULATOR OPERATORS GUIDE EVENT 5          Overcurrent trip 1-CC-P-1B with breaker stuck Shut, 15J9 trip open.
When cued by examiner, implement Trigger #7. If the Team decides to trip the reactor on this event, consult the examiner and actuate Trigger #11 when first Reactor Trip button pressed.
Operations Supervisor/Management:
* If contacted, will acknowledge the fault on of 1-CC-P-1B, the failure of the breaker to open, and the trip of breaker 15J9. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into ARP.
Unit 2 Operator:
* If asked: 1-CC-P-1C is running, and CC cross-ties are open.
STA:
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will acknowledge any TS information.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
* If asked, The STA will report that TRM review is complete and TRM requirements have been discussed with the Shift Manager.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                                Page 90 of 98 SIMULATOR OPERATORS GUIDE Field Operator:
* When contacted, report that 15J10 breaker for 1-CC-P-1B has a timed overcurrent drop on A phase. 1-CC-P-1A breaker, 15H10, has no abnormalities.
* When contacted, report that 15J9 breaker has a timed overcurrent drop on all three phases.
* If contacted, report as Aux Bldg Operator that there are no abnormalities locally with 1-CC-P-1A and 1-CC-P-1B.
Role play as other individuals as needed.
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                                Page 91 of 98 SIMULATOR OPERATORS GUIDE EVENT 6                Dropped Rod C Bank Group 1. 1-AP-1.00, 0-AP-23.00.
When Examiner ready, Actuate Trigger #9.
Operations Supervisor/Management:
* If contacted, will acknowledge the dropped rod and the need to ramp at 1%/minute to 70 - 74%
power.
* If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC, the Shift Manager will direct a 1%/minute ramp rate.
* If contacted, will take responsibility for writing the WR and CR.
STA:
* If asked, the STA will perform a shutdown margin calculation.
* If asked, the STA will perform a QPTR. See AP-1.00, Attachment 6, attached.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
* If asked, the STA will acknowledge the need to borate and use rods (will acknowledge the team review of pre-planned reactivity plans and OP-RX-010, if performed). If asked to perform the OP-RX-010 review, the STA will state that he is not able to at this time.
* When contacted, SRO directs STA to review VPAP-2802. The STA reports that review is complete and has been discussed with the Shift Manager.
Unit Two:
* If contacted, all conditions on U2 are normal.
Field Operators:
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 4                                  Page 92 of 98 SIMULATOR OPERATORS GUIDE
* If contacted, Will perform actions as directed (i.e., may be asked to read bank overlap counter-RD 2).
I&C:
* If requested by MCR to reset the bank overlap - use RD2 drawing to set as requested.
Maintenance/Work Week Coordinator:
* If contacted, will acknowledge the failure and commence investigations.
Role play as other individuals as needed.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 4                                  Page 93 of 98 SIMULATOR OPERATORS GUIDE EVENT 7          RC Loop C disc falls, Valid First-Out, FR-S.1 When Evaluator has seen a sufficient change in power, Actuate Trigger #11.
Operations Supervisor/Management:
* If contacted, will acknowledge the reactor trip failure and entry into FR-S.1, E-0, and ES-0.1.
* If contacted, will acknowledge direction for local opening of reactor trip breakers. After two (2) minutes, use Trigger 16 (A RT breaker) and Trigger 17 (B RT breaker).
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, SRO requests that tags be cleared and breakers closed for 1-SI-MOV-1890A / B /
C, use Triggers 21, 22, and 23 to perform close the breakers for the MOVs.
Field Operators:
* If directed, field operators will acknowledge direction for local opening of reactor trip breakers.
After two (2) minutes, use Trigger 16 (A RT breaker) and Trigger 17 (B RT breaker).
* If contacted, SRO requests that tags be cleared and breakers closed for 1-SI-MOV-1890A / B /
C, use Triggers 21, 22, and 23 to perform close the breakers for the MOVs.
Role play as other individuals as needed.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                                Page 94 of 98 SIMULATOR OPERATORS GUIDE EVENT 8          LOCA Outside Containment Upstream 1-SI-MOV-1890C.
When Evaluator is ready, implement Trigger # 13.
When RCS Subcooling reaches 35&deg;F and lowering, notify the Lead Examiner, for monitoring CT-2.
1-SI-MOV-1890A / B/ C can be energized when directed using Triggers 21, 22, and 23. 2 minutes to transit to valve, when directed; wait 1 minute between Triggers to energize MOV.
Operations Supervisor/Management:
* If contacted, will acknowledge the reactor trip failure, completion of FR-S.1, completion of E-0 Immediate Actions, and transition to ES-0.1.
* If contacted, will take responsibility for writing the WR and CR.
Unit 2 Operator:
* If directed to respond to radiation alarms on the radiation alarm panel, silence the alarms when and report the alarm to the Unit 1 SRO.
* When FP alarms occur, acknowledge alarms.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
* When contacted by BOP, Chilled Water has been throttled IAW the Caution prior to Step 10 of Attachment 3. MCR boundary D/P indicates the same value as Unit 2 ventilation panel D/P gauges. Unit 2 will assume responsibility for Attachment 3 when last page is reached (SFP monitoring).
* When directed, to read Unit 1 A/E, Blowdown, Main Steam and TDAFW radiation, report as pre-event, no trend.
Field Operators: Perform with a two minute delay to transit to the valve breaker; 1 minute between Triggers to energize MOVs.
* If directed, field operators will remove tags and close breakers for 1-SI-MOV-1890A / B / C.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 4                                Page 95 of 98 SIMULATOR OPERATORS GUIDE Role play as other individuals as needed.
EVENT 9          BOP Failures.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
* When directed, to read Unit 1 A/E, Blowdown, Main Steam and TDAFW radiation, report as pre-event, no trend.
Field Operators: Role play as necessary to support the Teams actions.
The scenario will end upon entering 1-E-1 or at the lead examiners discretion
 
Appendix D                                      Scenario Outline                                    Form ES-D-1 NRC EXAM - SCENARIO #1 Facility: Surry Power Station              Scenario No.: 1                        Op-Test No.: 2014-001 Examiners: ____________________________ Operators:                        _____________________________
Initial Conditions: Unit 1 and 2 at 100% power; MOL.
* A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Turnover:  The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Event            Malf. Event                                        Event No.            No.      Type*                                      Description 1                RCMOV_5      N BOP      Test Cycle Pressurizer PORV, Block Valve breaker will trip when re-35_BKR,      N SRO      opened Open        TS SRO 2                RC4903,      I RO        PRZR Level Transmitter Fails Low, requiring IAs of AP-53.00 to control
                  -.2 DEG                  CH flow.
TS SRO 3                FW1803,      I BOP      Feed Flow Channel fails high requiring manual FRV control, IAs of AP-
                  +1 DEG                  53.00 TS SRO 4                SD0201      C BOP      Loss of High Pressure Drain, AP-18.00 5                            R RO R SRO      Ramp to 75% power IAW AP-23.00 N - BOP C RO 6                RC2402      C SRO      Steam Generator Tube Leak B SG at approximately 74 gpm. AP-16.00, E0.
Auto Actions of Air Ejector Hi Rad do not function, BOP manually aligns.
AS02,        C - BOP    A/E RM Annunciator Response Procedure.
AS05 RC5601                  Reactor Coolant Pumps trip on electrical power swap to Reserve Station RC5602                  Service Transformers (30 seconds after reactor trip).
RC5603 7                RC2402,      M - All    SGTL B SG escalates to Design Basis rate (800 gpm) in ES-0.1. AP-79%, 710                16.00, Manual SI, E-0, E-3.
gpm, 60 sec ramp 8                PCV455C      M - All    PZR PORV 1-RC-1455C will not open when switch placed in open - Go
_OPEN,                  to ECA-3.3 OFF
 
Appendix D                                  Scenario Outline                                    Form ES-D-1 NRC EXAM - SCENARIO #1 9          SI2409      C BOP          BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-SI2505                    100A/B not close.
*      (N)ormal,  (R)eactivity, (I)nstrument,  (C)omponent,    (M)ajor Event 1: PT-18.6 I, PZR Block Valve Stroke Test. (N- BOP/SRO)
The Team will pre-brief this evolution prior to entering the Simulator. Upon entry of the Team to the Simulator, the Scenario brief will be given, Questions answered, and the Team allowed ~ 5 minutes to become acclimated to the Simulator Environment.
When the BOP closes 1-RC-MOV-1535, 1-RC-PCV-1456 block valve, and attempts to re-open 1-RC-MOV-1535, a series of triggers actuate to trip the power supply breaker to 1-RC-MOV 1535.
Verifiable Action(s):
: 1) BOP will close 1-RC-MOV-1535 and time the stroke.
: 2) RO/BOP will place the 1-RC-MOV-1456 PORV control switch in the close position following Tech Spec review.
Technical Specifications:
The SRO will review Tech Specs (3.1.A.6.d) and determine a one (1) hour clock exists to place 1-RC-PCV-1456 in manual (switch to close); and a 72 hour clock to return the block valve to an OPERABLE status, or be in HSD in 6 hours and RCS temperature <350&deg;F within the next 6 hours.
This Event sets up entry into ECA-3.3, SGTR without Pressure Control; Major Event later in the Scenario.
Event 2: PRZR level Upper Channel Fails Low (-.2 DEG) PRZR level on selected Upper Channel fails to ~34%. (I - RO, TS - SRO). ARP 1C-D8, PRZR LO Level.
The RO will diagnose the failure based on CH to Regen HX Hi/Low flow alarm (Annunciator 1D-E5) or identification of CH flow increasing and PZR level Channel III decreasing.
Verifiable Actions(s):
: 1) The RO will place CH flow in Manual and control PRZR level at setpoint IAW AP-53.00, Loss of Vital Instrumentation/Controls.
: 2) BOP will select an operable channel on the pressurizer level recorder.
: 3) The RO will defeat the failed channel IAW AP-53.00, and return CH flow to automatic when normal PRZR level restored.
Technical Specifications:
: 1) The SRO will Review Tech Specs and determine a 72 hour clock to place the Failed Channel in trip (TS 3.7, Table 3.7-1, item 9 (Pressurizer High Water Level), Operator Action 7. With the number of OPERABLE Channels less than the Total number of channels; place the failed channel in trip in 72 hours, allowable to bypass the channel for up to 12 hours for surveillance, if requirements not met reduce power to less than P-7 (10%) within the next 6 hours.
 
Appendix D                                Scenario Outline                            Form ES-D-1 NRC EXAM - SCENARIO #1
: 2) TS-Table 3.7-6, item 14, Pressurizer Level, 2 Channels required, condition met.
(Referred by check of CEP 99-0029, RG 1.97).
TRM Actions:
: 1) TRM section 3.3.2, Table 3.3.2-1, Pressurizer Level Channel 1-RC-LI-1461.
Condition A applies, Implement a Fire Watch in cable vault and tunnel and the emergency switchgear room of the affected Unit (Unit 1) IAW TRM Section 5.2 (Hourly) within 14 days and restore the failed channel in 60 days. (Usually an STA Function to identify, may be performed as a follow-up).
Reg. Guide 1.97:
: 1) CEP-99-0029, Reg. Guide 1.97 Operability/Functionality, Reportability and Alternate Indications, Attachment 1, Post Accident Monitoring Equipment, A-13 variable, 2 channels required, Condition is met. Refers to TS Table 3.7-6. (Usually an STA Function to identify - could be covered as a follow-up).
Event 3: Feed Flow Channel III, B SG fails high. (I - BOP, TS - SRO)
BOP will diagnose the failure based upon alarms and indications received and take the Immediate Actions of AP-53.00. The Team will implement AP-53.00, Loss of Vital Instrumentation/Controls and shift SGWLC input to Channel IV for B SG. The BOP will restore B SG NR level to program.
Verifiable Action(s):
: 1) BOP will place the B FRV in manual and regain control of B SG NR level.
: 2) RO will defeat the failed channel.
: 3) BOP will return the B FRV to automatic.
Technical Specifications:
Tech Spec Table 3.7-1
: 1) Item 17, Low steam generator water level with steam flow/feedwater flow mismatch, Operator Action 6.
: 2) With the number of OPERABLE Channels less than the TOTAL number of channels, operation may continue if the failed channel is placed in trip in 72 hours, the channel may be bypassed for 12 hours for surveillance, if conditions not satisfied in the time permitted, be in Hot Shutdown within 6 hours.
Technical Requirements Manual. Reg. Guide 1.97:
: 1) The TRM Section 3.3, Appendix R Instrumentation unaffected; and RG 1.97 requires one channel of Feed Flow indication per steam generator and no further actions are required are by this failure.
 
Appendix D                                  Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #1 Event #4: Loss of the HP Heater Drain Pump (1-SD-P-1A) (C - BOP)
The BOP will diagnose the failure based upon alarms and indication received. The Team will initiate AP-18.00, Loss of HP Heater Drain Pump/ Network 90 failure Verifiable Actions:
: 1) The BOP will place the tripped High Pressure Drain pump control switch in PTL.
: 2) Reduce Turbine Load as necessary to maintain reactor power less than 100% using the valve position limiter or using Turbine Manual (approximately 50 MW reduction required).
Event 5: Power Reduction to less than 75% power using AP-23.00, Rapid Load Reduction. (R - RO, R - SRO, N - BOP)
The SRO will lead a Team Brief where the reactivity plan will be discussed to reduce reactor power to less than 75% power in order to restore the Polishing Building to service. The RO and SRO will be credited with a Reactivity Manipulation and the BOP with a Normal Evolution.
Verifiable Action(s):
: 1) RO will manipulate control rods to control delta flux and/or Tave.
: 2) RO will manipulate CVCS controls to Emergency Borate.
: 3) RO will manipulate CVCS control to establish a normal boration to assist in Tave control.
: 4) BOP will manipulate Turbine Controls to establish power reduction.
Event #6: Steam Generator Tube Leak B Steam Generator. Failure of Auto actions of A/E RM. Trip of all RCPs on electrical transfer to RSSTs. (C - RO, C - BOP)
When the Evaluation Team is satisfied with the Reactivity manipulation, the event will be triggered. A SGTL of approximately 74 gpm will initiate requiring the RO to perform the actions of 1-AP-16.00 to quantify the leakrate. The A/E RM will go into High alarm due to the primary to secondary leakage; the BOP will manually align A/E discharge to containment IAW A/E RM ARP. When the RCS leakrate is identified as greater than 50 gpm, the RO will trip the reactor and perform the Immediate Actions of 1-E-0.
Verifiable Actions:
: 1) RO will isolate LD flow and place charging flow in manual to quantify leakrate.
: 2) BOP will respond to failure of auto actions on A.E RM High alarm by swapping A/E discharge to containment.
 
Appendix D                                  Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #1 Event #7: SGTR in B SG, approximately 710 gpm. (M - ALL)
When the evaluation Team is ready, a SGTR in the B SG will be implemented. The RO will re-assess RCS leakage in response to alarms and indications received. The RO will determine that RCS leakage exceeds the capacity of a single CH pump, and the Team will return to E-0 and manually initiate SI.
The SRO will perform a commensurate brief and continue with E-0. While the RO and SRO continue with E-0, the BOP will be directed to perform E-0 Attachments 1 through 3.
Verifiable Actions:
: 1) RO will increase CH flow in manual per Immediate Action Steps of 1-AP-16.00, Excessive RCS Leakage to determine if RCS leakage is greater than the capacity of a single CH pump.
: 2) RO re-perform High Level Steps of E-0, and manually Safety Inject on Step 4 of 1-E-0.
: 3) BOP will perform actions of Attachments 1 through 3 of E-0. BOP Failures in E-0 Attachments: 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not auto close, 1-VS-MOD-103A not auto close, 1-MS-TV-109 and 1-DA-TV-100A/B will not auto close (Listed as Event 9).
Critical Task:
: 1)  SPS E G: LHSI pumps will not undergo significant degradation while operating under very low flow conditions during the onset of a SBLOCA (implicit in SBLOCA analysis). Operators will secure one LHSI pump as directed by Emergency Operating Procedures to prevent pump damage while on recirculation. Secure one LHSI pump within 30 minutes of initiation of SI (KOA). NOTE: If the BOP Fails to Start 1-SI-P-1B, Critical Task becomes Not Applicable.
: 2)    WOG E-3 -- A:      Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs. Example: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs (KOA).
KOA: For the design basis tube rupture, isolate the ruptured SG from the atmosphere/Turbine building within 30 minutes. Note: The 30 minute criteria in the CT is ONLY for the design basis tube rupture.
Event #8: SGTR with Loss of Pressure control. (M - All)
The Team continues through the EOP progression E-0 to E-3.
After the Team has completed the rapid cooldown of E-3 and moves to the Depressurization steps, the Team will be presented with the inability to depressurize the RCS (No RCPs - No Spray available), 1 PZR PORV inoperable, and the last Pzr PORV not responding to placing the control switch in Open. This will require the Team to Transition to ECA-3.3, SGTR without Pressure Control.
When ECA-3.3 is entered, it is expected that the ruptured SG level will be > 73% NR leading to Team moving to Step 6, Check If SI Can Be Terminated.
 
Appendix D                              Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #1 Verifiable Actions:
: 1) RO will isolate AFW flow to the Ruptured SG.
: 2) BOP will reset SI and secure A CH pump and one of the running LHSI pumps.
(Discretionary CT - within 30 minutes).
: 3) RO will manipulate steam dump controls for rapid cooldown.
: 4) RO/BOP will block SI signals when conditions established.
: 5) RO will manipulate SI/CVCS control to terminate SI, establish CH flow, and restore letdown flow.
Classification:
Follow-up Classification question for SGTR: Alert FA-1.1.
The Scenario is terminated at Lead Evaluator discretion or at Step 11 of ECA-3.3, Check If CS Should Be Stopped (CH and LD flow have been re-established).
 
Appendix D                                        Scenario Outline                                    Form ES-D-1 NRC EXAM - SCENARIO #1 Initial Conditions: Unit 1 and 2 Operating at 100%.
Turnover: The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Pre-load malfunctions: (Trigger 30s) o SI2409 SI RELAY CI1A FAILS TO ACTUATE o SI2505 SI RELAY SI5B FAILS TO ACTUATE o AS02 DISABLE SV-TV-102 OPEN o AS05 DISABLE SV-TV-103 CLOSE o AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:
o    AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
Turnover:
Unit 1 and 2 at 100% power; MOL.
A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon dilutions followed by a manual makeup for training.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Turnover: Team will perform PT-18.6I, PZR Block Valve Stroke Test. The performance of this procedure has been analyzed based on the current plant configurations and the PRA indicates green.
Event      Malf. #s    Severity                        Instructor Notes and Required Feedback 1          RCMOV_53      Open        Test Cycle Pressurizer PORV, Block Valve breaker will trip when re-opened.
5_BKR, 2          RC4903,      -.2 DEG      PRZR Level Transmitter Fails Low, requiring IAs of AP-53.00 to control CH flow. 0-AP-53.00.
3          FW1803,      +1 DEG      Feed Flow Channel fails high requiring manual FRV control, IAs of AP-53.00 4          SD0201        True        Loss of High Pressure Drain, AP-18.00 5          N/A          N/A Ramp to 75% power IAW AP-23.00
 
Appendix D                                Scenario Outline                                  Form ES-D-1 NRC EXAM - SCENARIO #1 6      RC2402      8%        Steam Generator Tube Leak B SG at approximately 74 gpm. AP-16.00, E0.
AS02,                Auto Actions of Air Ejector Rad Mon on High alarm do not function, BOP manually AS05                  aligns. A/E RM Annunciator Response Procedure.
RC5601 RC5602                Reactor Coolant Pumps trip on electrical power swap to Reserve Station Service RC5603      TRUE      Transformers (30 seconds after reactor trip).
: 7. RC2402      88%, 60  SGTL B SG escalates to Design Basis rate (710 gpm) in AP-24.01. AP-16.00, sec ramp  Manual SI, E-0, E-3.
Failure of Auto Air Ejector to re-align on A/E RM High Alarm.
AS02/03 8      PCV455C    OFF      PZR PORV 1-RC-1455C will not open when switch placed in open - Go to ECA-
_OPEN,                3.3 PCV455C    ON
_CLOSE 9      SI409      TRUE      BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.
SI2505 Scenario Objectives:
A. Given a failure of 1-RC-MOV-1535 to re-open during performance of 1-PT-18.6I, PZR Block Valve Stroke Test, Implement the Applicable Tech Spec LCO.
B. Given a pressurizer level channel deviation, respond IAW 0-AP-53.00 to the failure.
C. Given a High Failure of SG Feed Flow Channel II on B SG, take action IAW 0-AP-53.00 to control SG level, and apply the applicable Tech Spec LCOs for the failure.
D. Given a trip of the running High Pressure Drain pump, ramp the Unit 1 <75% IAW 1-AP-18.00 and 0-AP-23.00.
E. Given a SG Tube Leak, respond IAW 1-AP-16.00 to quantify the leak rate, trip Unit 1, and perform the Immediate Action Steps of 1-E-0, Reactor Trip or Safety Injection.
F. Given a Design Basis SG Tube Rupture, respond IAW 1-E-0, and 1-E-3, Steam Generator Tube Rupture.
G. Given the Failure of 1-RC-PCV-1445C to open to depressurize the RCS, transition to 1-ECA-3.3, Steam Generator Tube Rupture without Pressurizer Pressure Control.
H. Given SI relay failures, manually align components IAW E-0, Attachment 1, 2, and 3.
 
SHIFT TURNOVER INFORMATION OPERATING PLAN:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance. Expected to be returned to services in 3 days. Per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
The last shift performed two 35 gallon dilutions followed by a manual makeup for training. A BAST concentration is 8.0 w/%.
Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, PZR Block Valve Stroke Test. Performance of this procedure has been authorized and has been PSA analyzed for current plant conditions.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                    Event No.: 1                    Page 10 of 92 Event
 
== Description:==
Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.
Cue: By Examiner.
Note:  An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.
The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.
A facility representative will be present for consultation with the Evaluation Team, as needed.
Time        Position                                  Applicants Action or Behavior 1-PT-18.6I SRO/BOP        NOTE - Team will pre-brief this evolution prior to entering the simulator. Initial Conditions and Precautions and Limitations will be completed before entering the simulator.
BOP        Verify closed or close PRZR PORV 1-RC-PCV-1456.
Verify key switch for PRZR PORV 1-RC-PCV-1456 OVPRESS BOP Mitigating System is in DISABLE.
Verify PRZR PORV Block Valve 1-RC-MOV-1535 is open.
BOP Stroke PRZR PORV Block Valve 1-RC-MOV-1535 through one complete cycle, timing valve movement in each direction. Time from signal initiation to complete valve travel.
BOP Valve closes and fails to reopen.
SRO Refer to Technical Specification 3.1.A.6 for required action
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 1                      Page 11 of 92 Event
 
== Description:==
Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.
Cue: By Examiner.
SRO        Refer to Technical Specification 3.1.A.6 for required actions.
With one block valve inoperable, within 1 hour either restore the block valve to operable status or place the associated PORV in manual. In addition, restore the block valve to operable status in the next 72 hours or, be in at least HSD within the next 6 hours and reduce RCS temperature to < 350&deg;F within the following 6 hours.
BOP        Places 1-RC-PCV-1456 in CLOSE.
SRO        Start 72 Hour Clock to repair Block Valve.
SRO        Direct RO/BOP to notify Service Building Operator to check status of 1H1-2S 6A breaker for 1-RC-MOV-1535.
RO/BOP        Contact Service Building Operator to check status of 1-RC-MOV-1535 Breaker.
RO/BOP        When notified by field operator that 1H1-2S 6A. Breaker is tripped, report information to the Team using a Focus Brief.
SRO        Notify Shift Manager of Block Valve failure and suspension of PT performance.
Request Electrical Maintenance support to investigate breaker trip.
SRO        Exit 1 hour clock to place 1-RC-PCV-1456 in manual.
SRO        Perform brief to update Team on Technical Specification requirements. Brief driven by brief card and placards.
END of Event #1.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 2                    Page 12 of 92 Event
 
== Description:==
PRZR Level Transmitter Fails Low, 0-AP-53.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior RO      Diagnoses failure of 1-RC-LI-1461 with the following indications/alarms:
Alarms:
* 1C-D8 PRZR LO LEVEL Indications:
* CH Flow rises on 1-CH-FI-1122A to ~109 gpm
* PRZR Level on 1-RC-LI-1461 lowers to 34%
In accordance with the immediate actions of AP-53.00 the RO will take manual control of pressurizer level control by placing 1-CH-FV-1122 in manual and lowering charging flow to maintain program level (per AP-53.00).
SRO      Enters 0-AP-53.00, Loss of Vital Instrumentation / Controls.
RO      [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL Checks 1-RC-LI-1459, Pressurizer Level Channel 1, and 1-RC-LI-1460, Pressurizer Level Channel 2 are NORMAL.
RO      [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-CH-FV-1122 in manual and raises charging flow.
SRO      Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.
SRO will provide a band for control of PRZR level with CH flow in MANUAL.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
Step 3, AP-53.00 RO      VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO will identify that reactor power is less than 100% using PCS Display of Core Thermal Power.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 2                        Page 13 of 92 Event
 
== Description:==
PRZR Level Transmitter Fails Low, 0-AP-53.00.
Cue: By Examiner.
SRO      Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO      *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
* PRZR Level Control, Step 11.
RO      The RO will identify that 1-RC-LI-1461 has failed.
Step 11, AP-53.00 SRO      11. CHECK PRZR LEVEL CONTROL CHANNELS - NORMAL RO          Responds NO, 1-RC-LI-1461 Abnormal.
SRO      11 a) RNO 1) Place either of the following in MANUAL:
* 1-CH-FC-1122C, CHG FLOW CNTRL, OR
* 1-CH-LC-1459G, PRZR LEVEL CNTRL RO          Responds 1-CH-FC-1122 in MANUAL SRO      11 a) RNO 2) Control PRZR Level at Program Level.
RO          Responds Maintain PRZR Level at program +/- band set by SRO SRO      11 a) RNO 3) Move PRZR Level - CH SEL switch to Defeat the failed channel.
RO/BOP          Transfers CH SEL switch to 1 / 2 Position.
SRO      11 a) RNO 4) Check or place recorder 1-RC-LR-1459 on an operable channel.
BOP          Checks or adjusts PRZR Level Recorder to 1-RC-LI-1459 or 1-RC-LI-1460.
SRO      11a) RNO 5) Refer to Tech Spec 3.7-1, Item 9 and Table 3.7-6, Item 13.
TS 3.7, Table 3.7-1, item 9; Operator Action 7. Number of Operable channels one less than Total number of channels: Place Inoperable channel in trip within 72 hours, allowed to bypass channel for 12 hours for surveillance, If conditions not met within allowed time, reduce power to less than P-7 in the next 6 hours.
TS Table 3.7-6m Item 13: Required Number of channels to meet function = 2.
11 a) RNO 6) Refer to Attachment 3.
SRO hands Attachment 3, Pressurizer Level Control diagram to RO/BOP for SRO review.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 2                    Page 14 of 92 Event
 
== Description:==
PRZR Level Transmitter Fails Low, 0-AP-53.00.
Cue: By Examiner.
Step 11, AP-53.00, Continued:
SRO      Step 11 b) Check Pressurizer Heaters - Energized.
RO          Checks Required Pressurizer Heaters energized, and reports that Pressurizer heaters are energized.
SRO      Step 11 c) Check Letdown - IN SERVICE.
RO          Reports Letdown in service.
SRO      Step 11 d) Check PRZR level control - IN AUTOMATIC.
RO          Reports pressurizer level control in MANUAL.
SRO      Step 11 d) RNO When pressurizer level restored to program level, un-saturate 1-CH-LC-1459G, PRZR LEVEL CNTRL. Place 1-CH-FCV-1122 in automatic.
RO          Acknowledges direction and notifies SRO when pressurizer level returned to AUTOMATIC.
Step 13, AP-53.00 SRO      SRO recalls NOTE 2 Prior to Step 4 and goes to Step 13 of AP-53.00.
SRO      Step 13 Check Calorimetric - Functional IAW 1-OPT-RX-001, Attachment 4.
RO/BOP      Checks Calorimetric unaffected by this failure, and reports to the SRO.
Step 14, AP-53.00 SRO          CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-RC-LI-1461 is a Reg. Guide 1.97 component.
STEP 15, AP-53.00 SRO          REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that the Reg. Guide 1.97 Review is complete and has been reviewed with the Shift Manager.
[CEP 99-0029 requires two channels of pressurizer level indication and refers to TS Table 3.7-6.]
 
Appendix D                                Required Operator Actions                                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 2                          Page 15 of 92 Event
 
== Description:==
PRZR Level Transmitter Fails Low, 0-AP-53.00.
Cue: By Examiner.
STEP 16, AP-53.00 SRO      Review the following:
* TS 3.7
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO determines that TS Table 3.7.1, Item 9 is applicable (72-hours to place the channel in trip). SRO determines that 3.1.A.5 is not applicable since pressurizer heaters did not de-energize and that Table 3.7-6 item 1 is Not Applicable.
SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
[TRM Section 3.3, Condition A, requires a Fire Watch be established in the Cable Vault and Tunnel and Emergency Switchgear Room of the affected Unit within 14 days, and restore the instrument to Functional status in 60 days. Hourly Fire Watch Requirement established in TRM Section 5.2. NO VPAP-2802 requirement for this failure.]
Step 17, AP-53.00 SRO            CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS The team will identify that no new additional failures exist (i.e., all failures have already been addressed), proceed to the RNO section, and this will direct the team to Step 19.
Step 19, AP-53.00 SRO      PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C END EVENT 2
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                    Event No.: 3                    Page 16 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
Time        Position                                  Applicants Action or Behavior BOP        Diagnoses failure FT-1487 with the following indications/alarms:
Alarms:
* 1H-E6 STM GEN 1B FW >< STM FLOW
* 1F-D8 STM GEN 1B CH 3 FW < STM FLOW
* 1H-G6 STM GEN 1B LVL ERROR.
Indications:
* Step increase in 1B SG Feed Flow indication CH-3
* decrease in 1B SG Feed Flow indication CH-4
* decreasing level on B SG.
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS Step 1, AP-53.00 BOP        [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL BOP identifies Channel IV indication for feed flow is NORMAL.
Step 2, AP-53.00 BOP        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and increases demand (FF >
SF) to restore level to program using Channel IV indication.
SRO        Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.
SRO will provide a band for control of B SG level with B FRV in MANUAL.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                  Event No.: 3                      Page 17 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
Step 3, AP-53.00 SRO
* VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO              Checks Reactor Power < 100% using PCS Calorimetric. Due to restoration of FF on 1B SG, power increase may be noted. As required, the SRO may direct the BOP to reduce turbine load to prevent exceeding 100% Calorimetric power.
Note: 0-AP-53.00, Attachment 7 Actions are contained at the end of this section starting on page 20.
Step 4, AP-53.00, Notes SRO        NOTE: When the affected instrument/controller malfunction has been addressed by this procedure, recovery actions may continue at Step 13.
Step 4, AP-53.00 SRO        DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
RO/BOP            Identifies 1B SG Feed Flow affected.
SRO              Goes to Step 7.
Step 7, AP-53.00 SRO        CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.
SRO        CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS - NORMAL
* Steam Pressure
* Steam Flow
* Feed Flow
* Steam Generator Level BOP        Determines CH III Feed flow instrumentation for B SG is NOT normal.
Step 7. RNO, AP-53.00 IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level Control system has failed, THEN do the following:
BOP              a) Place the associated Feed Reg Valve in MANUAL.
BOP        Verifies B SG MFRV controller, 1-FW-FCV-1488, in manual BOP              b) Control SG level at program level (44%, a band will be given).
BOP        Verifies B SG NR level is returning to program level.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                      Event No.: 3                  Page 18 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
RO              c) Select the redundant channel for affected SG(s)
RO        Selects Channel IV Feed Flow for B SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV)
BOP              d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.
BOP        Places B SG FRV controller, 1-FW-FCV-1488, in automatic control.
Step 6, RNO, AP-53.00 (Continued)
SRO        Perform follow-up actions:
a)  Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.
If asked the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
b) Refer to the following Tech Spec 3.7 items:
SRO
* Table 3.7-1, 12 and 17
* Table 3.7-2, 1.c, 1.e, and 3.a
* Table 3.7-3, 2.a, and 3.a
* Table 3.7-6, 15 and 16 Determines Table 3.7-1 item 17, is applicable (place channel in trip w/in 72 hours).
SRO c)  Refer to Attachment 1.
d) IF no other instrumentation failure exists, THEN GO TO Step 13.
Step 13, AP-53.00 SRO        13. Review OPT-RX-001, Rx Power Calorimetric using PCS computer program, Attachment 4, to determine operability of calorimetric and need to perform OPT-RX-007, Shift Average Power Calculation.
RO            Determines that OPT-RX-001 is NOT impacted and OPT-RX-007 will NOT need to be performed.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                  Event No.: 3                    Page 19 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
Step 13, RNO, AP-53.00 SRO            a) Initiate ( )-OPT-RX-007, SHIFT AVERAGE POWER CALCULATION, as necessary.
Note: The Team will determine that the Calorimetric Program is functional based on a recent change to 1-OPT-RX-001, Calorimetric, Attachment 4.
Step 14, AP-53.00 SRO        14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 14 if not Reg. Guide 1.97)
SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-FW-FT-1487 is a Reg. Guide 1.97 component.
Step 15, AP-53.00 SRO        15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 requirements have been reviewed with the Shift Manager.
[Reg. Guide 1.97 requires one channel of Feed Flow indication per steam generator and no further actions are required.]
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                  Event No.: 3                  Page 20 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
SRO        16 REVIEW THE FOLLOWING:
* Tech Spec 3.7
* VPAP-2802, NOTIFICATIONS AND REPORTS
* TRM SECTION 3.3, INSTRUMENTATION SRO            Directs STA to perform Review of Tech Spec 3.7, VPAP-2802, and TRM Section 3.3.
STA            The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
[VPAP-2802 - no requirement associated with the failure, No TRM requirements for this failure].
SRO        17. CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS Goes to Step 19 SRO        19. PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C END OF EVENT 3 0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 1    IF a rise in Reactor Power is caused by secondary transient, THEN GO TO Step 2.
IF a rise in Reactor Power is caused by primary transient, THEN GO TO Step 6.
NOTE: During secondary transient conditions, the most reliable indications of Reactor Power are Core T and Power Range NI. These indications should be used as the basis for Reactor Power until stable conditions have been reestablished.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 3                      Page 21 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 2  Mitigate a rise in Reactor Power caused by secondary transients by lowering steam demand or Turbine load as follows:
a) Reduce the Turbine Setter by an appropriate amount.
b) Place the Load Rate Selector thumbwheel to 1% / min.
c) Depress the GO pushbutton.
3  IF Turbine load can NOT be reduced using Operator Auto, THEN lower Turbine load using the Valve Position Limiter.
4  IF Turbine load still can NOT be reduced, THEN do the following.
a) Push the Turbine Manual pushbutton.
b) Check Turbine controls in Manual.
c) Depress the GV down pushbutton to reduce GV position.
NOTE: The CALCALC 10 minute Average Power will lag actual Reactor Power following a transient, and may continue to rise even after core thermal power has been reduced to less than 100%.
5  Check Reactor Power reduced to less than 100%.
* Power Range NI power.
* Core T power
* CALCALC Instantaneous power (if reliable)
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 3                      Page 22 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 6  Mitigate a rise in Reactor Power caused by primary transients as follows. Enter N/A for Steps 6 through 9 if NOT applicable.
a) Place the Rod Control Selector switch in Manual.
b) Insert control rods.
NOTE: The CALCALC 10 minute Average Power will lag actual Reactor Power following a transient, and may continue to raise even after core thermal power has been reduced to less than 100%.
7  Check Reactor Power reduces to less than 100%.
* Power Range NI power.
* Core T power
* CALCALC Instantaneous power (if reliable) 8  IF necessary, THEN initiate a normal boration to control  Flux.
: 9. WHEN Tave and Tref are within 1&deg;F, THEN place control rods in Auto.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 1                  Event No.: 4                  Page 23 of 92 Event
 
== Description:==
Loss of High Pressure Drain Pump, 1-AP-18.00.
Cue: By Evaluator BOP        Diagnose the trip of the High Pressure Drain Pump, 1-SD-P-1A based on the following indications:
* 1K-D4 4 KV BKR AUTO TRIP
* 1H-F3 CN POLISHING SYS TRBL
* 1H-D3 CN POLISHING BYPASS AOV OPEN
* 1J-B4 HP HTR DR RCVR TK HI LVL
* 1H-G5/6/7 SG 1A/1B/1C LVL ERROR Step 1, AP-18.00 SRO        Enter 1-AP-18.00 CHECK HP HEATER DRAIN PUMP STATUS:
SRO            a)  Check HP Heater Drain Pump - TRIPPED OR NOT PROVIDING SUFFICIENT FLOW BOP              Reports that 1-SD-P-1, HP Heater Drain pumps tripped.
SRO            b) Place pump control Switch in PTL BOP            Places 1-SD-P-1A control switch in PTL Step 2, 1-AP-18.00 SRO        CHECK REACTOR POWER - GREATER THAN OR EQUAL TO 75%
RO/BOP            Reports reactor power at 100%
Step 3, AP-18.00 SRO        START THIRD CONDENSATE PUMP AS REQUIRED BY PLANT CONDITIONS BOP            Starts 1-CN-P-1A and verifies Proper Operation.
Step 4, AP-18.00 SRO        NOTE: With unit at 100% power, Turbine load should be decreased approximately 50 MW.
REDUCE TURBINE LOAD AS NECESSARY TO MAINTAIN LOOP Ts -
LESS THAN 100%
* Use Valve Position Limiter OR
* Reduce Turbine load using Turbine Manual BOP            Using Guidance of NOTE preceding the Step, Turbine load will be reduced.
 
Appendix D                                  Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 1                Event No.: 4                  Page 24 of 92 Event
 
== Description:==
Loss of High Pressure Drain Pump, 1-AP-18.00.
Cue: By Evaluator Step 5, 1-AP-18.00 SRO        NOTE: Ramping to 75% allows the Condensate Polishing Building to be placed fully in service.
COMMENCE RAMP TO 75% POWER IAW 0-AP-23.00, RAPID LOAD REDUCTION Step 6, 1-AP-18.00 SRO
* USE CONTROL RODS AND CHEMICAL SHIM TO MAINTAIN FLUX IN BAND Step 7, 1-AP-18.00 SRO        MONITOR MAIN FEED REG VALVE RESPONSE - MAINTAINING SG LEVEL IN BAND BOP            Acknowledges Step direction.
SRO            Initiate AP-23.00, Rapid Load Reduction END EVENT #4
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                    Event No.: 5                    Page 25 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior AP-23.00, Rapid Load Reduction SRO      The team will hold a transient brief. During the brief the upcoming ramp will be discussed.
The RO and BOP will report critical parameters, as per placard on Main Control Room Bench Board. It is expected that the RO will discuss reactivity parameters associated with the ramp from the pre-planned ramp plan.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
The following reactivity plan will be discussed for a ramp to 75%:
* Gallons of boric acid required as per plan - 146 gallons
* D control bank end at 197 steps
* 5.8 gpm Boric Acid Flow, average rate during ramp.
* 1957 gallon PG required to stabilize at 75% power.
* The Team will discuss duration of Emergency Borate at start of Ramp, and remaining boron to be added via normal boration flowpath.
NOTE: RO Emergency borates for 25 seconds which corresponds to ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.
Step 1, 0-AP-23.00 SRO      Caution Prior to Step 1:
* Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.
Notes Prior to Step 1:
* Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
* When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
* Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
* The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
* For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                    Event No.: 5                      Page 26 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Step 1, 0-AP-23.00 RO      TURN ON ALL PRZR HEATERS.
Step 2 0-AP-23.00 INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:
BOP          a) Check turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter. If turbine is on limiter; reduce setter an appropriate amount, set load rate thumbwheel to 2% (or higher), press GO.
When Turbine limiter light OFF, press HOLD button.
RO          b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5&deg;F.
BOP          c) Check or place turbine in IMP IN or IMP OUT as determined by Shift Supervision The SRO chooses IMP IN.
BOP          d) Adjust SETTER to desired power level BOP          e)  Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute)
BOP          f)  Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button)
BOP          g) Reduce Turbine Valve Position Limiter as load decreases Periodically reduce the limiter setpoint during the ramp.
Step 3, 0-AP-23.00 SRO          CHECK EMERGENCY BORATION - REQUIRED RO          Reports Emergency Boration required.
Step 4, 0-AP-23.00 SRO      NOTE: Step 4 or Step 5 may be performed repeatedly to maintain Tref and Tave matched,  Flux in band, and control rod position above the LO-LO insertion limit.
RO      Acknowledges NOTE.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                    Event No.: 5                  Page 27 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Step 4, 0-AP-23.00 SRO      PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:
RO          a) Check or raise CHG flow to greater than 75 gpm RO          b) Transfer the in-service BATP to FAST RO          c) Open 1-CH-MOV-1350 for required time (~25 seconds)
RO          d) Monitor EMRG BORATE FLOW
                                      * ( )-CH-FI-( )110 e)  After required emergency boration, perform the following:
RO                1) Close 1-CH-MOV-1350 RO                2) Transfer the in-service BATP to AUTO
: 3) Restore Charging flow control to normal.
Step 5, 0-AP-23.00 RO          ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.
Step 6, 0-AP-23.00, NOTES SRO      NOTES:
* If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
* RCS Tave must be maintained less than or equal to 577&deg;F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
* I & C should be contacted to provide assistance with adjusting IRPIs.
Step 6, 0-AP-23.00 RO/BOP          CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG Step 7, 0-AP-23.00 RO
* CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                Event No.: 5                    Page 28 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Step 8, 0-AP-23.00 BOP      MONITOR STEAM DUMPS FOR PROPER OPERATION Step 9, 0-AP-23.00 SRO      NOTIFY THE FOLLOWING:
* Energy Supply (MOC)
* Polishing Building
* Chemistry
* OMOC Step 10, 0-AP-23.00 SRO      EVALUATE THE FOLLOWING:
* EPIP applicability
* VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.
[VPAP-2802 and EPIP are not applicable for this event.]
Step 11, 0-AP-23.00 SRO          CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR.
When reactor power has decreased >15%, then chemistry will be notified.
END EVENT #5
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1      Scenario No.: 1                    Event No.: 5                  Page 29 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO      1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO      2. Adjust 1-CH-YIC-1113 to desired total gallons RO      3. Adjust 1-CH-FC-1113A to desired flow rate.
RO      4. Place the MAKE-UP MOD SEL switch in the BORATE position.
RO      5. Place the MAKE MODE CNTRL switch in the START position.
RO      6. Check proper valve positions.
RO      7. Adjust boration rate using 1-CH-FC-1113A, as necessary.
RO      8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.
a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.
b) Enter N/A for the remaining steps in this Attachment.
Attachment 5 is on the next page RO      9. Check controllers for Primary Grade water and Boric Acid are set correctly.
RO      10. Place the MAKE-UP MODE SEL switch in the AUTO position.
RO      11. Place the MAKE-UP MODE CNTRL switch in the START position.
RO      12. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 1                    Event No.: 5                  Page 30 of 92 Event
 
== Description:==
Ramp to 75% Power, 0-AP-23.00.
Cue: By Examiner.
Time        Position                              Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions RO      1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO      2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
RO      3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
RO      4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
RO      5. Place the MAKE-UP MODE CNTRL switch in the START position.
RO      6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
RO      7. Check proper valve positions.
RO      8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1113B in the AUTO position RO      9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO      10. Check or place the control switches in the AUTO position.
RO      11. Check controllers for Primary Grade water and Boric Acid are set correctly.
RO      12. Place the MAKE-UP MODE SEL switch in the AUTO position.
RO      13. Place the MAKE-UP MODE CNTRL switch in the START position.
RO      14. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 6                      Page 31 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Time        Position                              Applicants Action or Behavior Team      Diagnose SGTL B SG based on the following:
Alarms:
* 1A-B3 N-16 ALERT
* 1A-A3 N-16 HIGH
* RM-G8 CNDSR AIR EJECTOR ALERT/FAILURE
* RM-H8 1-SV-RI-111 HIGH Indications:
* Increasing trend on 1-MS-RR-193, Control Room N16 Trend Recorder, from Normal to 200 GPD.
* STM LINE B Trend will Lead STM LINE A and STM LINE B.
SRO          Direct Unit to Perform Annunciator Response Procedure for A/E Alert and High Alarms.
Note: Unit 2 Operator will perform ARP for A/E RM Alarms. Unit 2 will hand Page 3 and 4 of RM-H8 ARP to BOP to check Auto Actions complete; following E-0 Team Brief.
Verification of ARP RM-H8, A/E RM High Alarm RM-H8, Step 6 BOP      NOTE: On a high alarm, air ejector gaseous effluent is diverted from vent stack to containment.
CHECK AUTOMATIC ACTIONS - VALVES POSITIONED AS FOLLOWS:
* 1-SV-TV-103 - CLOSED Identifies 1-SV-TV-103 Open, places control switch in close.
* 1-SV-TV-102 - OPEN Identifies 1-SV-TV-102 Closed, places control switch in open.
RM-H8, Step 7 BOP      CHECK AIR EJECTOR VENT TO CTMT VV - OPEN
* 1-SV-TV-102A Identifies 1-EV-RV-102A open Report to SRO that A/E manually aligned to containment.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                  Event No.: 6                    Page 32 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
1-AP-16.00 SRO            Direct the RO to perform the Immediate Action Steps of 1-AP-16.00.
Step 1, 1-AP-16.00 RO      NOTE:
* If SI Accumulators are isolated, 1-AP-16.01, SHUTDOWN LOCA, should be used for guidance.
* RCS average temperature has a direct impact on pressurizer level.
[ 1 ] ___ MAINTAIN PRZR LEVEL:
RO
* Isolate Letdown Close 1-CH-LCV-1460A and 1-CH-LCV-1460B
* Control Charging flow Place 1-CH-FCV-1122, CH Flow Control Valve, in Manual Monitor CH Flow on 1-CH-FI-1122 Identify RCS leak rate less than the capacity of a single CH pump Continue adjustment of CH flow to quantify leak rate to determine if reactor trip required Step 1, 1-AP-1600 SRO            Upon report of completion of Immediate Action Step of 1-AP-16.00, Perform a commensurate brief; continue to Step 2 of 1-AP-16.00.
Step 2, 1-AP-16.00 SRO CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING
* PRZR level
* PRZR pressure
* RCS subcooling RO            Report that PRZR Level, Pressure, and Subcooling Stable RO continues actions to quantify leakrate Step 3, 1-AP-16.00 SRO            PLACE THE FOLLOWING COMPONENTS IN OFF:
RO
* CTMT sump pumps Places 1-DA-P-4B control switch on OFF
* CTMT vacuum pumps Places 1-CV-P-1A control switch in OFF
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 6              Page 33 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 4, 1-AP-16.00 SRO      NOTE: Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.
SRO      CHECK REACTOR TRIP - REQUIRED
* Leak rate - GREATER THAN 50 GPM OR
* Adequate makeup not being provided by blender RO          Reports RCS leak rate greater than 50 gpm.
NOTE: Due to transient on RCS caused by Ramp for previous event, exact quantification of leak rate may be difficult.
Step 5, 1-AP-16.00 SRO          ALIGN CHG PUMP SUCTION TO RWST a) Open 1-CH-MOV-1115B and 1-CH-MOV-1115D RO          Opens CH pump Suction MOVs from RWST, 1-CH-MOV-1115B/D b) Close 1-CH-MOV-1115C and 1-CH-MOV-1115E Closes CH pump Suction from VCT MOVs, 1-CH-MOV-1115C/E Step 6, 1-AP-16.00 SRO      GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 1                    Event No.: 6              Page 34 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
1-E Reactor Trip or Safety Injection RO      [1] CHECK REACTOR TRIP:
a)  Manually trip reactor Pushes the reactor trip push buttons.
b)  Check the following:
* All Rods On Bottom light - LIT
* Reactor trip and bypass breakers - OPEN
* Neutron flux - DECREASING RO Reports Reactor Tripped at completion of Step 1. SRO Acknowledges.
RO      [2] CHECK TURBINE TRIP:
RO          a)  Manually trip the turbine Pushes the turbine trip push buttons.
b)  Check all turbine stop valves - CLOSED c)  Isolate reheaters by closing MSR steam supply SOV
* 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)
RO Reports Turbine Tripped at completion of Step 2. SRO Acknowledges.
RO      [3] VERIFY BOTH AC EMERGENCY BUSES - ENERGIZED RO Reports Both AC Emergency Buses Energized at completion of Step 3. SRO acknowledges.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 6                    Page 35 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
RO      [4] CHECK IF SI INITIATED:
a)    Check if SI is actuated:
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3 SI INITIATED - TRAIN A
* A-F-4 SI INITIATED - TRAIN B RO will determine that SI has not occurred and perform step 4a RNO actions:
RO 4a RNO Check if SI is required or imminent as indicated by any of the following:
* Low PRZR pressure
* High CTMT pressure
* High steamline differential pressure
* High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.
RO reports SI is not in service or required; Immediate Actions of E-0 are complete; recommend transition to ES-0.1 after completion of Step 4. SRO Acknowledges.
After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0 and announce a transition to ES-0.1. After the immediate actions are verified, the team will conduct a brief.
During the Brief RO/BOP reports that ALL RCPs are tripped.
Team Identify 1B SG experiencing a Large SG Tube Leak.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal, with the exception of the alarms already received. He will also state that containment conditions and the electrical conditions are as you see them (or as reported by the RO/BOP).
If not previously performed, Unit 2 Operator will Provide BOP/SRO with ARP pages Unit 2 for A/E RM High alarm for verification of Auto Actions.
Establish priorities at Brief End, RO:
SRO
* Continue with SRO in 1-AP-24.01, Large Steam Generator Tube Leak, BOP:
* Complete verification of A/E High Alarm auto actions.
* Throttle AFW to the SGs IAW Attachment 8 of AP-24.01.
* Contact Service Building Operator to check status of RCP breakers.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 6                  Page 36 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
SRO      When Brief is complete Announce Transition to ES-0.1, Reactor Trip Response, Read the First NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.
Transitions to 1-AP-24.01 Step 1, 1-AP-24.01 SRO      CAUTION: If the leak rate increases to 150 gpm, 1-E-0, Reactor Trip or Safety Injection, must be implemented.
NOTE:
* Procedure 1-ES-0.1, Reactor Trip Response, must not be performed when implementing this procedure.
* Refer to Attachment 8 for guidance on transient AFW control.
CHECK SI - IN SERVICE RO            Identifies NO not required. Team Goes To Step 3.
Note: Attachment 8 actions are start on Page 40.
Step 3, 1-AP-24.01 SRO      CHECK CONDENSATE POLISHING BUILDING - BYPASSED RO            Identifies Polishing Building bypassed Step 4, 1-AP-24.01 SRO      CHECK ALL AC BUSSES - ENERGIZED BY OFFSITE POWER RO          Identifies all AC Buses energized by off-site power by:
* Checks breakers 15H8/15J8 closed
* Station Service buses energized using Voltage/Current indications on Benchboard.
* Checks for Abnormal Electrical System alarms on K Annunciator Panel.
Step 5, 1-AP-24.01 SRO
* CHECK PRZR LEVEL - GREATER THAN 22%
RO      Reports actual pressurizer level and trend.
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 6                  Page 37 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 6, 1-AP-24.01 SRO      CHECK FW STATUS:
a) Check RCS Average temperatures - LESS THAN 554&deg;F RO      Identifies RCS Tave less than 554&deg;F b) Check Feed REG valves - CLOSED RO      Identifies FRVs closed c) Close SG FW isolation MOVs
* 1-FW-MOV-154A
* 1-FW-MOV-154B
* 1-FW-MOV-154C RO/BOP      Closes SG FW Isolation MOVs d) Check AFW pumps - RUNNING
* Motor Driven AFW pumps
* TD AFW pump RO/BOP      Identifies MD and TD AFW Running e) Check total AFW flow - GREATER THAN 540 GPM (350 W/O RCPs)
RO/BOP      Identifies AFW flow indicated f) Check emergency buses - BOTH ENERGIZED RO      Identifies Emergency buses energized g) Control feed flow to maintain narrow range level between 22% and 50%
BOP      Acknowledges control of SG level when returned to NR scale.
Step 7, 1-AP-24.01 SRO      CHECK PCS POINTS USING GROUP 80 REVIEW OR MAIN STEAM P & ID:
* R1RM204C, RI-MS-124
* R1RM205C, RI-MS-125
* R1RM206C, RI-MS-126 RO/BOP      Checks points for abnormal indication.
 
Appendix D                                  Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 6            Page 38 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 8, 1-AP-24.01 SRO      IDENTIFY AFFECTED SG(S):
* Unexpected rise in any SG narrow range level OR
* High radiation from any SG MS line monitor OR
* High radiation from any SG blowdown line OR
* High radiation from any SG sample OR
* High radiation from any SG N-16 monitor RO/BOP      Identifies rise in B SG NR level Step 9, 1-AP-24.01 SRO
* CHECK AFFECTED SG LEVEL:
a) Narrow range level - GREATER THAN 12%
BOP      Acknowledges when B SG NR Level > 12%, perform substep b).
b) Stop feed flow to affected SG(s)
BOP      Isolates AFW flow to B SG, by closing 1-FW-MOV-151 C / D.
 
Appendix D                                Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 6            Page 39 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 10, 1-AP-24.01 SRO      ISOLATE AFFECTED SG(S):
a) Adjust affected SG PORV controller setpoint to 1035 psig BOP      Checks B SG PORV setpoint at 1035 psig b) Check affected SG PORV - CLOSED BOP      Identifies B SG PORV closed c) Check blowdown TVs from affected SG - CLOSED RO      Identifies B SG BD TVs closed.
d) Locally close steam supply valve to TD AFW pump:
* 1-MS-87 for SG A
* 1-MS-120 for SG B
* 1-MS-158 for SG C BOP      Directs Service Building operator to close 1-MS-120.
e) Close SG FW Isolation MOV, 1-FW-MOV-154A, B, or C BOP      Identifies 1-FW-MOV-154B closed f) GO TO Step 13
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 6                  Page 40 of 92 Event
 
== Description:==
SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.
Step 1, AP-24.01, Attachment 8 BOP      Maintain minimum AFW flow of 540 gpm with RCP(s) in service until one SG Narrow Range level is greater than 12%.
Checks AFW ~1050 gpm Step 2, AP-24.01, Attachment 8 Maintain minimum AFW flow of 350 gpm with NO RCPs running, until one SG BOP      Narrow Range level is greater than 12%.
Throttles AFW to SGs per Step 2 to flow rate established by SRO or ~ 120 gpm per SG using 1-FW-MOV-151 A through F control switches.
Step 3, AP-24.01, Attachment 8 BOP      NOTE: AFW to idle loop(s) (RCP secured), should be throttled to prevent depressurization of the SG and subsequent Header / Line SI. AFW flow between approximately 60 gpm and 100 gpm should be adequate to prevent a Header / Line SI.
Identifies NOTE as not applicable for this event.
When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50% by throttling AFW Isolation MOVs:
* SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
* SG B, 1-FW-MOV-151C and 1-FW-MOV-151D
* SG C, 1-FW-MOV-151A and 1-FW-MOV-151B Identifies need to monitor flow rate as SG NR level recovers.
Step 4, AP-24.01, Attachment 8 BOP      Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves:
Identifies Step as not applicable.
Contact Service Building operator to check status of RCP breakers.
BOP          When contacted the Service Building operator will report no abnormalities with the RCP breakers, but the Speed Sensing Panel appears to be malfunctioning.
Performs a Focus Brief to apprise the other Team members of RCP status.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                      Page 41 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
SG Tube Leak escalates to 710 gpm Tube Rupture RO      Diagnose SG Tube Rupture by:
RCS Pressure decrease.
Pressurizer Level decrease.
Manually raise CH flow to maximum.
Identify pressurizer level decreasing.
Report to SRO that Safety Injection is required.
Re-Perform High Level Steps, 1 through 3 of E-0.
Manually Initiate Safety Injection.
Check Annunciator 1A-F3, SI Initiated Train A - LIT Check Annunciator 1A-F4, SI Initiates Train B - LIT Check LHSI Pumps Running.
Report to SRO Immediate Actions of E-0 with SI Complete.
Critical Task 2) Isolate steam release from ruptured SG within 30 Minutes START Time: _____________
SRO      The team will hold a transition brief. During the brief it will be identified that SI was initiated and the SGTL has degraded into a SGTR.
The SRO will set priorities:
RO - Continue with SRO in performance of E-0 to E-3.
BOP - Perform Attachment 1 through 3 of E-0.
Step 5, E-0 SRO/BOP      Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained under last section of Event 9).
SRO/RO      SRO may direct the RO to perform Attachment 10 of 1-E-0 for Ruptured SG Isolation and AFW Control. This may or may not be initiated at any time during the performance of E-0. Attachment 10 actions are contained at the end of this section.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                    Page 42 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 6, E-0 RO
* CHECK RCS AVERAGE TEMPERATURE
* STABLE AT 547&deg;F OR
* TRENDING TO 547&deg;F The team will identify that RCS temperature is decreasing. The team should attribute this to the injection of SI into the RCS and AFW flow to the SGs. It is acceptable for the team to enter the RNO portion of this step and perform the applicable steps (summarized below):
Stop dumping steam Reduce AFW flow to the SG Close MSTVs if cooldown continues Step 7. E-0
: 7. CHECK PRZR PORVs AND SPRAY VALVES:
RO            a) PRZR PORVs - CLOSED b) PRZR spray controls
* Demand at Zero (or)
* Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN Step 8, E-0 SRO      NOTE: Seal injection flow should be maintained to all RCPs.
* CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
RO            a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RCS subcooling will NOT be less than 30 &deg;F RNO for the step is to go to step 9.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                      Event No.: 7                      Page 43 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 9, E-0 RO      CHECK IF SGs ARE NOT FAULTED:
* Check pressures in all SGs a)  STABLE OR INCREASING AND b)    GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.
Step 10, E-0 RO      CHECK IF SG TUBES ARE NOT RUPTURED:
* Condenser air ejector radiation - NOT NORMAL
* SG blowdown radiation - NOT NORMAL
* SG MS radiation - NORMAL
* TD AFW pump exhaust radiation - NORMAL
* SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO should observe B SG NR level going up uncontrollably.
SRO      RNO: GO TO 1-E-3, STEAM GENERATOR TUBE RUPTURE.
SRO      The team will hold a transition brief. During the brief it will be identified that B SG is ruptured, current isolation status of the ruptured SG and that the team is transitioning to 1-E-3.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified alarms. He will also state that containment conditions and the electrical conditions are as you see them.
 
Appendix D                                Required Operator Actions                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 7      Page 44 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
BEGIN Step 1, 1-E-3:
NOTE: Seal injection flow should be maintained to all RCPs.
                        *CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
RO a)  Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO will identify that two charging pumps are running.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RO will identify that RCS subcooling is greater than 30&deg;F RNO is to go to step 2 Step 2, E-3 IDENTIFY RUPTURED SG(s):
* Unexpected rise in any SG narrow range level SRO                OR
* High radiation from any SG MS line monitor OR
* High radiation from any SG blowdown line OR
* High radiation from any SG sample Team identifies B SG NR level rising unexpectedly.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 7                    Page 45 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 3, E-3 SRO      CAUTION:
* If the TD AFW pump is the only available source of feed flow, steam supply to the TD AFW pump must be maintained from at least one SG.
* At least one SG must be maintained available for RCS cooldown.
: 3. ISOLATE RUPTURED SG(s):
RO a) Adjust ruptured SG PORV controller setpoint to 1035 psig b) Check ruptured SG(s) PORV - CLOSED c) Verify blowdown TVs from ruptured SG(s) - CLOSED d) Locally close steam supply valve(s) to TD AFW pump:
* 1-MS-120 for B SG If 1-MS-120 not closed iaw attachment 10 of 1-E-0, then a field operator will be dispatched to close it at this time.
e)  Close ruptured SG(s) MSTV (B)
Partial completion of the critical task (WOG E-3A) to isolate the SG is accomplished by performance of this step. KOA: For the design basis tube rupture, isolate the ruptured SG from the atmosphere/Turbine building within 30 minutes.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 1                    Event No.: 7                    Page 46 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 4, E-3 SRO      CAUTION: If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless needed for RCS cooldown.
* CHECK RUPTURED SG LEVEL:
a) Narrow range level - GREATER THAN 12% [18%]
b) Stop feed flow to ruptured SG(s)
RO              Identifies B SG level >12%, closes 1-FW-MOV-151C/D to isolate AFW Flow c) Check ruptured SG AFW MOVs auto-open signal - DEFEATED Identifies auto-open signal not defeated, SRO goes to Step 4 c) RNO NOTE: BOP may have performed the following IAW Attachment 10.
: 1) Select the ruptured SG AFW MOVs using the following switches:
RO
* H TRAIN DISABLE SELECTOR SWITCH
* J TRAIN DISABLE SELECTOR SWITCH
: 2) Defeat the auto-open signal for the selected MOVs by placing the following key switches in the DISABLE SELECTED position:
* H TRAIN AUTO OPEN ENABLE SWITCH
* J TRAIN AUTO OPEN ENABLE SWITCH Step 5, E-3 SRO      CAUTION: Major steam flow paths from the ruptured SG(s) should be isolated before initiating RCS cooldown.
CHECK RUPTURED SG(S) PRESSURE - GREATER THAN 350 PSIG RO            Identifies B SG pressure ~ 1000 psig.
Step 6, E-3 SRO
* CHECK LOW PRZR PRESS SI SIGNAL - BLOCKED
* Permissive Status light C LIT RO              Identifies PSL C2 NOT LIT.
SRO      WHEN PRZR pressure less than 2000 psig, THEN do the following:
a) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block.
b) Check Permissive Status light C LIT.
NOTE: BOP may have completed this action in E-0, Attachment 1.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                      Event No.: 7                    Page 47 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 7, E-3 SRO      CHECK LOW TAVE SI SIGNAL - BLOCKED
* Permissive Status light F LIT RO            Identifies PSL F1 NOT LIT.
SRO            WHEN Tave less than 543&deg;F, THEN do the following:
a) Turn both HI STM FLOW & LO TAVG OR LP switches to block.
b) Check Permissive Status light F LIT.
NOTE: BOP may have completed this action in E-0, Attachment 1.
Step 8, E-3 SRO    CAUTION:
* Flow on each Main Steamline should be kept less than 1.0 x 106 PPH to prevent Main Steamline isolation during RCS cooldown with the Steam Dumps.
* If no RCPs are running, RCS cooldown and depressurization may cause a false Integrity Status Tree indication on the ruptured loop. The Cold Leg indication on the ruptured loop should be disregarded until after the performance of Step 36.
NOTE: RCP trip criteria does NOT apply after initiation of an operator controlled cooldown.
INITIATE RCS COOLDOWN:
a) Determine required core exit temperature (ONE TIME):
SRO/BOP          Concur Target CETC temperature 485 &deg;F if SG pressure between 901 and 1000 psig, or 495&deg; if SG pressure between 1001 and 1085 psig.
Step 8, E-3, Continued RO            b) Place Steam Dump Mode Select switch in Steam Pressure mode c) Check RCS Tave - LESS THAN 543&deg;F RO          d) Place the STM DUMP CNTRL switch in BYP INTLK and then return to ON e) Check Bypass Status light D LIT RO            f) Dump steam to condenser from intact SG(s) at maximum rate g) Check CETCs - LESS THAN REQUIRED TEMPERATURE SRO          When RCS Temperature < 543&deg;F, SRO will direct the block of HSF SI and check of PSL F1 LIT.
When RCS pressure < 2000 psig, SRO will direct the block of Low Pressure/Header-to-Line SI Signal, and check the PSL C2 LIT.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                      Page 48 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
RO          Performs the Block of SI Signals and check of PSLs when directed.
h) Stop RCS cooldown RO          When target CETC Temperature reached, RO throttles back on steam dumps.
i) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE SRO          SRO will direct a band for control of CETC temperature.
Step 9, E-3 SRO      CHECK INTACT SG LEVELS:
a) Any narrow range level - GREATER THAN 12% [18%]
b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%
RO/BOP            Adjust AFW to restore A and C SG NR Level to 22-50%.
Step 10, E-3 SRO      CAUTION: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure decreases to less than 2335 psig.
                              *CHECK PRZR PORVs AND BLOCK VALVES:
a) Power to PRZR PORV block valves - AVAILABLE b) PRZR PORVs - CLOSED c) PRZR PORV block valves - AT LEAST ONE OPEN Step 11. E-3 SRO            RESET BOTH TRAINS OF SI RO              Push SI Reset Pushbuttons. SI previously reset.
Step 12, E-3 SRO            RESET CLS:
a) Check CTMT pressure - HAS EXCEEDED 17.7 psia RO                  Report No, CTMT has not exceeded 17.7 psia.
RNO a) GO TO Step 13.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                  Page 49 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 13, E-3 SRO          CHECK INSTRUMENT AIR AVAILABLE:
a) Check annunciator B-E NOT LIT RO            Report Yes, B-E-6 Not Lit.
b) Check at least one CTMT IA compressor - RUNNING
* 1-IA-C-4A or 1-IA-C-4B RO            Report Yes, 1-IA-C-4A running c) Check 1-IA-TV-100 - OPEN RO            Report Yes, 1-IA-TV-100 open.
Step 14, E-3 SRO          ALIGN CONDENSER AIR EJECTOR TO CTMT:
a) Check the following:
* 1-SV-TV-102 - OPEN
* 1-SV-TV-103 - CLOSED RO            Reports valves in required position. Valves Manually Aligned by BOP on A/E RM auto failure during Event 6.
b) Open the following valve:
* 1-SV-TV-102A RO/BOP          Opens 1-SV-TV-102A.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                  Page 50 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 15, E-3 SRO      CAUTION: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.
                              *CHECK IF LHSI PUMPS SHOULD BE STOPPED:
a) Check LHSI pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST RO                Reports 1 LHSI pump running with suction aligned to RWST.
b) RCS pressure - GREATER THAN 250 PSIG [400 PSIG]
RO                Reports RCS pressure greater than 250 psig.
c) Stop LHSI pumps and put in AUTO RO                Stops running LHSI pump and places in AUTO.
Step 16, E-3 SRO          CHECK IF RCS COOLDOWN SHOULD BE STOPPED:
a) Check CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP          Reports CETCs < required temperature b) Stop RCS cooldown RO/BOP          Reports RCS Coodown stopped.
c) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP            Reports that RCS temperature being maintained in required band.
Step 17, E-3 SRO          CHECK RUPTURED SG(s) PRESSURE - STABLE OR INCREASING BOP                Reports B SG pressure stable.
Step 18. E-3 SRO      CHECK RCS SUBCOOLING BASED ON CETCs - GREATER THAN 50&deg;F [105&deg;F]
BOP                Reports indicated subcooling value.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                      Event No.: 7                Page 51 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
Step 19, E-3 SRO      DEPRESSURIZE RCS TO MINIMIZE BREAK FLOW AND REFILL PRZR:
a) Check normal spray - AVAILABLE
* RCP C AND 1-RC-PCV-1455B - BOTH AVAILABLE OR
* RCPs A and B, AND 1-RC-PCV-1455A - BOTH AVAILABLE RO            Identifies No pressurizer spray available, SRO Goes To Step 20.
Step 20, E-3 SRO      CAUTION:
* The PRT may rupture if a PRZR PORV is used for RCS depressurization.
Rupturing the PRT may result in abnormal containment conditions.
* Cycling of the PRZR PORV should be minimized.
NOTE: The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PRZR level.
DEPRESSURIZE RCS USING PRZR PORV TO MINIMIZE BREAK FLOW AND REFILL PRZR:
a) PRZR PORV - AT LEAST ONE AVAILABLE b) Open one PRZR PORV until ANY of the following conditions satisfied:
(Attachment 4 lists conditions)
* PRZR level - GREATER THAN 69%
OR
* RCS subcooling based on CETCs - LESS THAN 30&deg;F [85&deg;F]
OR
* BOTH of the following exist:
: 1) RCS pressure - LESS THAN RUPTURE SG(s) PRESSURE
: 2) PRZR level - GREATER THAN 22% [50%]
RO                When Attempt Made to open 1-RC-PCV-1455C, PCV will Not Open.
SRO                Transition to ECA-3.3
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                    Page 52 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
ATTACHMENT 10 of 1-E-0
: 1. Check SI is in progress. If SI is not in progress, then return to procedure step in effect.
RO/BOP      RO/BOP identifies that SI is in progress.
ATTACHMENT 10 of 1-E-0 RO/BOP      2. Identify Ruptured SG by one of the following conditions:
* Unexpected rise in any SG Narrow Range level
* High radiation from any SG MS line monitor
* High radiation from any SG Blowdown line With SRO concurrence identifies B SG as the ruptured SG ATTACHMENT 10 of 1-E-0 RO/BOP      3. Check running or start AFW Pumps, as necessary
* 1-FW-P-3A
* 1-FW-P3B
* 1-FW-P-2 ATTACHMENT 10 of 1-E-0 RO/BOP      4. When ruptured SG Narrow Range level is greater than 12%, then isolate feed flow to ruptured SG by closing SG AFW Isolation MOVs:
* SG B, 1-FW-MOV-151C and 1-FW-MOV-151D RO/BOP closes 1-FW-MOV-151C/D when SG level is greater than 12% Narrow Range.
Completion of Critical Task: WOG - A; Isolate feed flow into and steam flow from ruptured SG before a transition is made to ECA-3.1. STOP Time: _________.
ATTACHMENT 10 of 1-E-0 RO/BOP      5. Select the ruptured SG AFW MOVs using the following switches:
* H TRAIN DISABLE SELECTOR SWITCH
* J TRAIN DISABLE SELECTOR SWITCH
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 7                  Page 53 of 92 Event
 
== Description:==
SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.
Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.
RO/BOP      ATTACHMENT 10 of 1-E-0
: 6. Disable the auto-open signal for the selected MOVs by placing the following keyswitches in the DISABLE SELETED position:
* H TRAIN AUTO OPEN ENABLE SWITCH
* J TRAIN AUTO OPEN ENABLE SWITCH ATTACHMENT 10 of 1-E-0 RO/BOP      CAUTION: At least one SG must be maintained available for RCS heat sink.
: 7. Locally close steam supply valve to the TD AFW pump:
* 1-MS-120 RO/BOP directs field operator to close 1-MS-120.
The field operator will acknowledge the requirement to close 1-MS-120. The field operator will later report that 1-MS-120 is closed.
ATTACHMENT 10 of 1-E-0 RO/BOP      8. Control Feed Flow to the SG IAW the following requirements:
* Minimum AFW flow is 350 gpm with SI initiated, until one SG Narrow Range level is greater than 12%
* When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50%.
* SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
* SG C, 1-FW-MOV-151A and 1-FW-MOV-151B End EVENT #7
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 1                      Event No.: 8                Page 54 of 92 Event
 
== Description:==
1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.
Time        Position                                Applicants Action or Behavior 1-ECA-3.3 Actions SRO      1. CHECK RUPTURED SG(S) NARROW RANGE LEVEL - LESS THAN 75%
[73%]
RO      Reports that B SG Level is greater than 75%.
: 1. RNO - GO TO Step 6 SRO      6. CHECK IF SI CAN BE TERMINATED:
a)  Check RCS subcooling based on CETCs - GREATER THAN 30&deg;F [85&deg;F]
RO/BOP                Identifies that RCS subcooling is greater than 30&deg;F.
b) Check secondary heat sink:
* Total feed flow to SGs - GREATER THAN 350 GPM [450 GPM]
AVAILABLE OR
* Narrow range level in at least one intact SG - GREATER THAN 12%
[18%]
RO/BOP          Identifies A and C SG NR level >12% OR identify >350 gpm flow Available.
c)  Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs                RVLIS INDICATION Running      Full Range          Dynamic Range 0          GREATER THAN 63%
1                              GREATER THAN 36%
2                              GREATER THAN 51%
3                              GREATER THAN 82%
RO/BOP Identify that RVLIS Full Range is Greater than 63%.
d) Check any ruptured SG narrow range level - INCREASING IN AN UNCONTROLLED MANNER OR OFFSCALE HIGH BOP BOP will identify that B SG Level is Off-Scale High.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 1                  Event No.: 8                  Page 55 of 92 Event
 
== Description:==
1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.
SRO      7. STOP ALL BUT ONE CHG PUMP AND PUT IN AUTO RO      Secure one of the running charging pumps SRO      8. ISOLATE HHSI TO COLD LEGS:
a)  Verify the following:
RO              1) CHG pump suctions from RWST - OPEN
* 1-CH-MOV-1115B
* 1-CH-MOV-1115D
: 2) Check CHG pump miniflow recirc valves - OPEN
* 1-CH-MOV-1275A
* 1-CH-MOV-1275B
* 1-CH-MOV-1275C
* 1-CH-MOV-1373 b) Close HHSI to Cold Leg:
* 1-SI-MOV-1867C RO
* 1-SI-MOV-1867D
* 1-SI-MOV-1842 SRO      9. ESTABLISH CHARGING FLOW:
a) Close CHG flow control:
RO
* 1-CH-FCV-1122 a) b) Check CHG line isolation - OPEN
* 1-CH-HCV-1310A c) Open CHG line isolation MOVs RO
* 1-CH-MOV-1289A
* 1-CH-MOV-1289B RO          d) Establish at least 40 gpm charging flow using CHG flow control
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 1                Event No.: 8              Page 56 of 92 Event
 
== Description:==
1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.
SRO      10. CHECK SI FLOW NOT REQUIRED:
* RCS subcooling based on CETCs - GREATER THAN 30&deg;F [85&deg;F]
* Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs                RVLIS INDICATION Running      Full Range      Dynamic Range 0          GREATER THAN 63%
1                            GREATER THAN 36%
2                            GREATER THAN 51%
3                            GREATER THAN 82%
RO          Reports Full Range RVLIS >63%.
END Event 8 End Scenario
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 57 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
ATTACHMENT 1 OF E-0 BOP      1. CHECK FW ISOLATION:
* Feed pump discharge MOVs - CLOSED
* 1-FW-MOV-150A
* 1-FW-MOV-150B
* MFW pumps - TRIPPED
* Feed REG valves - CLOSED
* SG FW bypass flow valves - DEMAND AT ZERO
* SG blowdown TVs - CLOSED BOP      2. CHECK CTMT ISOLATION PHASE I:
* Phase I TVs - CLOSED
* 1-CH-MOV-1381 - CLOSED
* 1-SV-TV-102A - CLOSED
* PAM isolation valves - CLOSED
* 1-DA-TV-103A
* 1-DA-TV-103B BOP will identify 1-DA-TV-100A/B, and 1-MS-TV-109 OPEN and CLOSE them.
BOP      3. CHECK AFW PUMPS RUNNING:
a)  MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                      Event No.: 9                Page 58 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Attachment 1 of E-0 BOP      4. CHECK SI PUMPS RUNNING:
* CHG pumps - RUNNING
* LHSI pumps - RUNNING BOP starts 1-SI-P-1B 1-SI-P-1B START TIME: _____ (for critical task verification, CT-1)
BOP      5. CHECK CHG PUMP AUXILIARIES:
* CHG pump CC pump - RUNNING
* CHG pump SW pump - RUNNING
: 6. CHECK INTAKE CANAL:
BOP
* Level - GREATER THAN 24 FT
* Level - BEING MAINTAINED BY CIRC WATER PUMPS
: 7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:
a)  Check if ANY of the following annunciators - HAVE BEEN LIT
* E-F-10 (High Steam Flow SI)
* B-C-4 (Hi Hi CLS Train A)
BOP
* B-C-5 (Hi Hi CLS Train B)
Identifies annunciators not lit and goes to step 8.
BOP      *8. CHECK IF CS REQUIRED:
a)  CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 9                  Page 59 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Attachment 1 of E-0 BOP      *10. BLOCK LOW PRZR PRESS SI SIGNAL:
a)    Check PRZR pressure - LESS THAN 2000 psig b)  Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c)  Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.
BOP      *11. BLOCK LOW TAVE SI SIGNAL:
Step may not be performed at this time (if Tave is greater than 543&deg;F).
a)  Check RCS Tave - LESS THAN 543&deg;F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c)  Verify Permissive Status light F LIT NOTE:
* CHG pumps should be run in the following order of priority: C, B, A.
* Subsequent SI signals may be reset by re-performing Step 12.
BOP      12. CHECK SI FLOW:
a)  HHSI to cold legs - FLOW INDICATED
* 1-SI-FI-1961 (NQ)
* 1-SI-FI-1962 (NQ)
* 1-SI-FI-1963 (NQ)
* 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c)  Reset SI.
d) Stop one CHG pump and out in AUTO
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 9                      Page 60 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Attachment 1 of E-0 e)  RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:
: 1) Verify reset or reset SI.
: 2) Stop one LHSI pump and put in AUTO.
1-SI-P-1A or 1B STOP TIME: ______
: 3) GO TO Step 13.
Critical Task:    Secure one LHSI pump within 30 minutes of two LHSI pumps in service. [SPS E-1G, CT-1]
Note: If 1-SI-P-1B was not started on Step 4 of Attachment 1, CT becomes Not Applicable.
BOP      13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]
BOP      14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.
BOP      15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next page of this guide)
Depending on timing, this attachment may have already been completed.
BOP      16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Identify failure of 1-VS-MOD-103A CLOSES the MOD.
Unit 2 Operator will state that Unit 2 is at 100% power (if asked)
Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                    Page 61 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Time      Position                              Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 BOP      NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.
ATTACHMENT 2 of 1-E-0 BOP      1. Check opened or open CHG pump suction from RWST MOVs.
* 1-CH-MOV-1115B
* 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 BOP      2. Check closed or close CHG pump suction from VCT MOVs.
* 1-CH-MOV-1115C
* 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 BOP      3. Check running or start at least two CHG pumps. (listed in preferred order)
* 1-CH-P-1C
* 1-CH-P-1B
* 1-CH-P-1A ATTACHMENT 2 of 1-E-0 BOP      4. Check opened or open HHSI to cold legs MOVs.
* 1-SI-MOV-1867C
* 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 BOP      5. Check closed or close CHG line isolation MOVs.
* 1-CH-MOV-1289A
* 1-CH-MOV-1289B
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 62 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
ATTACHMENT 2 of 1-E-0 BOP      6. Check closed or close Letdown orifice isolation valves.
* 1-CH-HCV-1200A
* 1-CH-HCV-1200B
* 1-CH-HCV-1200C RO/BOP will CLOSE 1-CH-HCV-1200A and 1-CH-HCV-1200B ATTACHMENT 2 of 1-E-0 BOP      7. Check opened or open LHSI suction from RWST MOVs.
* 1-SI-MOV-1862A
* 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 BOP      8. Check opened or open LHSI to cold legs MOVs.
* 1-SI-MOV-1864A
* 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 BOP      9. Check running or start at least one LHSI pump.
* 1-SI-P-1A
* 1-SI-P-1B BOP Would have started 1-SI-P-1B as part of attachment 1.
ATTACHMENT 2 of 1-E-0 BOP      10. check High Head SI flow to cold legs indicated.
* 1-SI-FI-1961
* 1-SI-FI-1962
* 1-SI-FI-1963
* 1-SI-FI-1943 or 1-SI-FI-1943A
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                    Page 63 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
ATTACHMENT 2 of 1-E-0 BOP      11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.
* Alternate SI to Cold legs
* Hot leg injection
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 64 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 65 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                Page 66 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                  Event No.: 9                    Page 67 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
If asked, Unit 2 has throttled Chilled Water flow as required by CAUTION prior to Step 10.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 9              Page 68 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
If asked, pressure indicated on PDI-118, 116, 215, and 206 equals the pressure indicated on PDI-100/101/200/201 pressure indicators.
 
Appendix D                              Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 1                    Event No.: 9                      Page 69 of 92 Event
 
== Description:==
BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.
Cue: Pre-load Malfunctions.
Unit 2 will assume responsibility for this attachment at this point.
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 70 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 71 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 72 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 73 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                  Page 74 of 92 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:
Recall IC -261 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.
Acknowledge AAC System Alarm on Waste Disposal Panel Open the monitor window and add the following points to it:
* asp_ao_off
* MS-120, B Steam Supply to TDAFW Pump Enter the following MALFUNCTIONS:
Trigger Malfunction              Delay  Ramp        Trigger  Value    Final      Type (Auto or Manual)
RC4903 PRZR LEVEL XMTR CH                10      20          1      0.0      -0.2        Manual 3 FAILURE (461)
FW1803 B S/G MN FD FLOW                  10        0          3      0.0        1          Manual XMTR FT-1487 FAILS SD0201 HP HTR DRN PP SD-P-1A            10        0          5    FALSE      TRUE        Manual TRIPS: OVR-CURRENT RC2402 STEAM GENERATOR B                10      60          9      0.0        8          Manual TUBE RUPTURE PCV455C_OPEN PCV-1455C                    0        0          11      OFF        OFF        Manual PRZR RELIEF VALVE OPEN PCV455C_CLOSE PCV-1455C                  0        0          11      OFF        ON          Manual PRZR RELIEF VALVE CLOSE RCMOV535_BKR RC-MOV-535                  0        0          16        1        0          AUTO PORV Block Valve RC5601 RC-P-1A BKR 15A3                  0        0          17    FALSE      TRUE        AUTO SPURIOUS TRIP RC5602 SPURIOUS TRIP RCP 1B              0        0          17    FALSE      TRUE        AUTO RC5603 SPURIOUS TRIP RCP 1C              0        0          17    FALSE      TRUE        AUTO AS02 DISABLE SV-TV-102 OPEN              0        0          30    FALSE      TRUE        ACTIVE AS05 DISABLE SV-TV-103                    0        0          30    FALSE      TRUE        ACTIVE CLOSE SI2409 SI RELAY CI1A FAILS TO            0        0          30    FALSE      TRUE        ACTIVE ACTUATE SI2505 SI RELAY SI5B FAILS TO            0        0          30    FALSE      TRUE        ACTIVE ACTUATE
 
Appendix D                                    Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1                            Scenario No.: 1                                    Page 75 of 92 SIMULATOR OPERATORS GUIDE Enter the following EVENT TRIGGERS:
Trigger#                      EVENT                                          Command Trigger setup to trip 1-RC-MOV1535 breaker when control switch in open to stroke test open time, Event 1.
Trigger 14 sets when 1-RC-MOC-1535 closed. Trigger 15 sets when 1-RC-MOV-1535 control switch taken to open. Trigger 16 set when both Trigger 14 and 15 are TRUE. Trigger 16 implements Remote Function trip of 1-RC-MOV-1535 breaker.
14          "rcmov535 .le. 0.0002"                                    Sets Trigger 14 15          "mov535_open"                                              Sets Trigger 15 16          "et_array(14) .and. et_array(15)"                          Sets Trigger 16 Trigger setup to trip A, B, C, RCPs when Generator Output breakers open. (EL2 Auto Trigger). Actuates Trigger which implements Malfunction RC5601/5602/5603.
17          ".not. (elg102_bkr(2) .and.                                Sets Trigger 17 elg1t240_bkr)"
Trigger setup to override 1-RC-LCV-1460A and B control switch to Open to simulate removing PRZR level control output fuses.
20          "chw180<500.0"                              Set Trigger 20 when Letdown flow < 1 gpm.
21          "chlcv460a_open"                      Set Trigger 21 when 1-CH-LCV-1460A switch taken to Open.
22          "chlcv460b_open"                      Set Trigger 22 when 1-CH-LCV-1460B switch taken to Open.
23          "et_array(20) .and. et_array(21)"      Sets Trigger 23 when Trigger 20 and 21 are ACTIVE.
Actuates override for 1-CH-LCV-1460A switch in Open 24          "et_array(20) .and. et_array(22)"      Sets Trigger 24 when Trigger 20 and 22 are ACTIVE.
Actuates override for 1-CH-LCV-1460B switch in Open Enter the following Remote Functions:
Override                                    Set Condition                        Trigger AAC_SMS_MODE OFF AAC DG                                      OFF                                  30 LOCAL MODE SWITCH POSITION
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                  Page 76 of 92 SIMULATOR OPERATORS GUIDE Enter the following Switch Overrides:
Override                                Set Condition                      Trigger Override CH LCV-460A OPEN                                ON                              23 Override CH LCV 460B OPEN                                ON                              24 TRIGGER                  TYPE                                      DESCRIPTION 1                    MAN            Fails PZR Level CH III to ~34%.
3                    MAN            B SG MN Feed Flow Transmitter fails high.
5                    MAN            Trip running High Pressure Drain Pump Steam Generator Tube Leak, 74 gpm 9                    MAN 11                    MAN            Overrides 1-RC-PCV-1455C control switch Open OFF, Close ON 16                  AUTO            Open Breaker to 1-RC-MOV-1535 17                  AUTO            Spurious Trip A/B/C RCPs when Gen. Output Bkrs open 23                  AUTO            Overrides 1-CH-LCV-1460A control switch Open.
24                  AUTO            Overrides 1-CH-LCV-1460B control switch Open.
AS02 DISABLE SV-TV-102 OPEN AS03 DISABLE SV-TV-103 CLOSE SI2409 SI RELAY CI1A FAILS TO ACTUATE 30                  ACTIVE SI2505 SI RELAY SI5B FAILS TO ACTUATE AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION
 
Appendix D                                Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 1                          Page 77 of 92 SIMULATOR OPERATORS GUIDE Verify the following control room setup:
Place the simulator in RUN and verify normal 100% power operation indications.
Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:
Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).
Verify Ovation System operating.
Reset ICCMs.
Verify Component Switch Flags.
Verify Brass Caps properly placed.
Verify SG PORVs set for 1035 psig.
Verify Rod Control Group Step Counters indicate properly.
Verify Ovation CRT display.
Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)
Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:
AP-53.00            AP-18.00            AP-23.00                    AP-16.00 E-0                                    E-3 (2)                      ECA-3.3 OP-CH-007                                Reactivity Sheet OP-ZZ-002                              PT-18.6I Verify Reactivity Placard is current.
Verify ALL PINK MAGNETS are accounted for.
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 1                                  Page 78 of 92 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.
Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.
If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.
In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.
Assign operating positions.
Ask for and answer questions.
 
Appendix D                            Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 79 of 92 SIMULATOR OPERATORS GUIDE Conduct shift turnover:
The initial conditions have Unit 1 at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance. In accordance with VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
The last shift performed two 35 gallon dilutions followed by a manual makeup for training. A BAST boron concentration is 8.0 w/%.
Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, Pressurizer Block Valve Stroke Test. Performance of PT-18.6I has been authorized and has been PSA analyzed for current plant conditions.
When the team has accepted the shift, proceed to the Session Conduct Section.
 
Appendix D                          Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 80 of 92 SIMULATOR OPERATORS GUIDE Session Conduct:
* Ensure conditions in Simulator Set-up are established.
* Ensure Trigger 30 is active prior to team entering the simulator.
* Verify Exam Security has been established and ASP_AO_OFF = True.
EVENT 1        Test Cycle PORV Block Valves, 1-PT-18.6I BOOTH:
30 minutes prior to the beginning of the scenario, provide the team with a copy of 1-PT-18.6I, Pressurizer Block Valve Stroke Test. The team will pre-brief the PT prior to entering the simulator.
Trigger setup to trip 1-RC-MOV1535 breaker when control switch in open to stroke test open time, Event 1. Monitor the following triggers as 1-RC-MOV-1535 is closed/opened.
Trigger 14 sets (becomes Active) when 1-RC-MOC-1535 closed.
Trigger 15 sets (becomes Active) when 1-RC-MOV-1535 control switch taken to open.
Trigger 16 sets when both Trigger 14 and 15 are TRUE.
Trigger 16 implements Remote Function to trip 1-RC-MOV-1535 breaker.
Operations Supervisor/Management/Work Week Coordinator:
* If contacted, will acknowledge 1-RC-MOV-1535 breaker tripped when the valve was re-opened, suspension of the PT, and Tech Spec Clock identified (1 hour/72 hour).
Field Operator: (3 minute delay from request to answer)
* If Contacted, as Service Building Operator, to check the status of 1-RC-MOV-1535 breaker, 1H1-2S 6A; report that the breaker has tripped (in the trip free position).
 
Appendix D                                Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                Page 81 of 92 SIMULATOR OPERATORS GUIDE EVENT 2          PRZR Level Transmitter 1-RC-LI-1461 Fail to 34%, 0-AP-53.00.
When cued by examiner, implement Trigger #1.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00.
* If contacted, ask for SRO recommendation for performing 1-OP-RP-001, Shift Manager will call back).
* If contacted, will take responsibility for writing the CR.
STA:
* If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge (but not confirm/deny) any TS LCOs.
* If asked, the STA will report that 1-RC-LI-1461 is a Reg. Guide 1.97 component. The STA will also report that review of CEP 99-0029 has been discussed with the Shift Manager.
* If asked, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Field Operators:
Maintenance/Work Week Coordinator:
* If contacted, will acknowledge instrumentation failure and commence investigations and/or efforts to place the channel in trip.
Unit 2 Operator:
* No action for this event.
Role play as other individuals as needed.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                Page 82 of 92 SIMULATOR OPERATORS GUIDE EVENT 3          Feed Flow Channel Fails High, 0-AP-53.00.
When cued by examiner, implement Trigger #3.
Operations Supervisor/Management:
* If contacted, acknowledge feed flow channel failure. The individual(s) contacted will also acknowledge any TS LCOs.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into AP-53.00.
* If contacted, will ask SRO for recommendation concerning performance 1-OP-RP-001. Shift Manager will call back.
STA:
* If contacted, will acknowledge feed flow channel failure. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
* If contacted, will take responsibility for writing the CR.
* When asked: Failed channel is a RG 1.97 variable.
* When asked, CEP-0029 has been reviewed and discussed with the Shift Manager. VPAP-2802 and TRM section 3.3 have been reviewed and discussed with the Shift Manager.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Field Operators:
* Will perform actions as directed.
Maintenance/ Work Week Coordinator:
* If contacted, will acknowledge the feed flow channel failure and contact I&C to commence preparation to place the failed channel in trip.
Unit 2:
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 1                                Page 83 of 92 SIMULATOR OPERATORS GUIDE
* If contacted, will acknowledge the failure of the feed flow channel.
Role-play as other individuals as needed.
EVENT 4          Loss of HPD, 1-AP-18.00.
When the Evaluator indicates Ready, Activate Trigger #5.
Operations Supervisor/Management:
* If contacted, will acknowledge the trip of 1-SD-P-1A, and the need to ramp at 1%/minute to 75%
power.
* If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC, the Shift Manager will direct a 1%/minute ramp rate.
STA:
* If contacted, will acknowledge the trip of 1-SD P-1A and the need to ramp at 1%/minute to 75%
power.
* If asked, the STA will acknowledge the need to borate and use rods (will acknowledge the team review of pre-planned reactivity plans and OP-RX-010, if performed). If asked to perform the OP-RX-010 review, the STA will state that he is not able to at this time.
* After directed, the STA will report that VPAP-2802 has reviewed and discussed with the hift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
* When contacted: EPIPs have been reviewed with the Shift Manager.
Maintenance/ Work Week Coordinator:
* If contacted, will acknowledge the failure and notify electrical maintenance to investigate.
 
Appendix D                            Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 1                                  Page 84 of 92 SIMULATOR OPERATORS GUIDE
* If contacted, will acknowledge the requirements to reduce reactor power.
Field Operators: (Wait three (3) minutes from direction of a local action to the report of local condition found.)
* If contacted, the condensate polishing building operator will acknowledge the need to ramp the unit.
* If asked, the condensate polishing building operator acknowledge bypass of the polisher.
* When contacted, as the Service Building Operator concerning the status of 1-SD-P-1A power supply breaker, 1-EP-BKR-15B6, report that the breaker is open with a timed overcurrent drop on A phase.
* When contacted, as the Turbine Building Operator to check the status of 1-SD-P-1A, report that there are no apparent abnormalities other than the A HPD pump has tripped and HPD tank high level divert, 1-SD-FCV-107, is diverting to the condenser.
Unit 2:
* If contacted, will acknowledge the trip of 1-SD-P-1A and the need to ramp at 1%/minute to 75%
power.
Role-play as other individuals as needed.
 
Appendix D                            Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 85 of 92 SIMULATOR OPERATORS GUIDE EVENT 5        Ramp to 75%, 0-AP-23.00.
Operations Supervisor/Management:
* If contacted, will acknowledge Ramp to 75% required due to the loss of 1-SD-P-1A.
* If contacted, will take responsibility for writing the CR.
* When contacted: The Shift Manager will review EPIPs for applicability. They are not applicable.
STA:
* If contacted, will acknowledge the impending ramp to 75% power.
* If contacted, will take responsibility for writing the WR and CR.
* When contacted: The STA reports that VPAP-2802 has been reviewed discussed with the Shift manager.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them. STA will acknowledge reactivity plan developed by RO/SRO.
Unit 2 Operator:
* If notified of Ramp: Acknowledge ramp of Unit 1.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 86 of 92 SIMULATOR OPERATORS GUIDE EVENT 6          SGTL 74 gpm, A/E RM Auto Actions Fail, RCPs Trip on swap to RSST.
When the Evaluator is ready and the Blender is in AUTO, implement Trigger # 9.
Note: It would be preferable to wait until power is <80% to implement this failure to allow for ramp stabilization prior to creating RCS leak to allow the team to assess leakrate with more precision.
Operations Supervisor/Management:
* If contacted, will acknowledge RCS leakage into the B SG. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into AP-16.00.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
 
Appendix D                          Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                Scenario No.: 1                                  Page 87 of 92 SIMULATOR OPERATORS GUIDE STA:
* If contacted, will acknowledge the RCS leakage into the B SG.
* If asked to calculate the RCS leak rate, state that it is difficult to ascertain at this time, but you will continue to monitor as time permits.
* If contacted, will take responsibility for writing the WR and CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
Health Physics:
* If contacted, will acknowledge B SGTL.
Role play as other individuals as needed.
Operations Supervisor/Management:
* If contacted, will acknowledge entry into 1-E-0, ES-0.1. AP-24.01.
* If contacted, will acknowledge the SGTR on B SG.
* If contacted, will acknowledge the isolation of B SG (if informed).
Field Operators:
* If contacted, to report abnormalities on RCPs, report no 86 devices drops apparent on RCP breakers, but the Speed Sensing Panel appears to be malfunctioning; lights blinking on and off.
 
Appendix D                            Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 88 of 92 SIMULATOR OPERATORS GUIDE EVENT 7                SGTL becomes SGTR (710) gpm). 0-AP-16.00, E-0, E-3.
Notify Examiner when B SG NR level reaches 12%. To increase SGTL to SGTR, double click on RC2402, set DEG at 79%, 60 sec ramp, Insert.
After the SGTR implemented, Actuate Trigger 11 to fail PORV 1455C control switch.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will acknowledge entry into 1-E-0, 1-E-3.
* If contacted, will acknowledge the SGTR on B SG.
* If contacted, will acknowledge the isolation of B SG (if informed).
STA:
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
Unit Two:
* If asked, blowdown and air ejector RM readings are [as indicated at the time].
* If requested, acknowledge RM alarms, and perform ARP actions.
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
* If asked: Unit 2 RWST cross-ties are open.
* If asked: take responsibility to notify HP of B SG PORV lifting.
Field Operators:
* If contacted, field operators will perform valve manipulations as required:
* 1-MS-120 - set ms_120 to zero upon request
 
Appendix D                            Required Operator Actions                  Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                      Page 89 of 92 SIMULATOR OPERATORS GUIDE
* Acknowledge direction to place Number 1 and 2 Turbine Building Sump pumps in OFF locally, and initiate 0-OSP-PL-003, Turbine Building Sump Pump Status Verification.
 
Appendix D                          Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                            Page 90 of 92 SIMULATOR OPERATORS GUIDE EVENT 8                PZR PORV 1-RC-PCV-1455C not open, 1-ECA-3.3.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will acknowledge entry into 1-ECA-3.3.
* If contacted, will acknowledge the SGTR on B SG.
* If contacted, will acknowledge the isolation of B SG (if informed).
STA:
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
Unit Two:
* If asked, blowdown and air ejector RM readings are [as indicated at the time].
* If requested, acknowledge RM alarms, and perform ARP actions.
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
Field Operators:
* If contacted, field operators will perform vale manipulations as required:
* 1-MS-120 - set ms_120 to zero upon request
 
Appendix D                          Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                        Page 91 of 92 SIMULATOR OPERATORS GUIDE EVENT 9                BOP Failures, 1-SI-P-1B no auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
Unit Two:
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
* If asked, MRC differential pressure is a found.
* If asked, Unit 2 has throttled Chilled Water flow IAW E-0, Attachment 3 guidance.
Field Operators:
* If contacted, field operators will perform valve manipulations as required.
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 1                                Page 92 of 92 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:
* If contacted, will acknowledge the failures and commence investigations.
HP:
* If contacted, will acknowledge B SGTR.
STA:
* If asked, will report that he will calculate the time to B fill, time permitting.
* If contacted, will enter the control room and commence reviewing status trees and prepare for the transient brief (items are reported as you see them or previously reported).
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. Radiological conditions are as indicated. He will also state that containment conditions and the electrical conditions are as you see them.
Role play as other individuals as needed.
The scenario will end upon reaching Step 11 of 1-ECA-3.3 or at the lead examiners discretion.
 
Appendix D                                              Scenario Outline                                      Form ES-D-1 NRC EXAM - SCENARIO #3 Facility: Surry Power Station                    Scenario No.: 3                          Op-Test No.: 2014-001 Examiners: ____________________________ Operators:                              _____________________________
Initial Conditions: Time in Core Life - Middle of Life; Core Cycle - Cycle 26 Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportablility is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
Event            Malf.      Event                                              Event No.            No.        Type*                                          Description N - BOP 1                    N/A        N - SRO        Deleted.
2                RC0801,            I - RO      Failure of Median Tave in the Low Direction, AP-53.00.
                  -1 Deg 3                                I - BOP MS0801, TS - SRO Failure of Steam Flow Channel III Low, A SG. AP-53.00
                  -1 Deg C - RO 4                EL4902 TS - SRO      1J 4160V emergency Bus Off-site Power Supply Breaker Trips.
Switch                        Test Button on Main Turbine Control Fails causing the LP Turbine 5                                R - RO O/R, TEST_IR R - SRO        1 Intercept and Reheat Stop Valve Closure. AP-23.00 Ramp to N - BOP      71% Power.
L_IIL RC04,                        RCS leak of 35 gpm. AP-16.00.
6              3.5% Deg          C - RO TS- SRO RM0202, 7                +.1 Deg, RM0201,        C - BOP        Containment Particulate and Gas RM auto actions on High Alarm
                  +.1 Deg                      fail to function CA03 CA04 RC0101, 8                .6% Deg M - All      SBLOCA. AP-16.00, E-0.
 
Appendix D                                    Scenario Outline                                  Form ES-D-1 NRC EXAM - SCENARIO #3 SETPT 9          for Hi-Hi CLS change to 60 psia.
O/R          M - All CLS_AC Hi and HI-HI CLS fail to function, requiring manual alignments of T_TRA        C - BOP        components, and FR-Z.1 entry.
O/R CLS_AC T_TRB
*      (N)ormal,    (R)eactivity,  (I)nstrument,  (C)omponent,    (M)ajor
: 1) Deleted Normal Evolution.
Event #2: Median Tave Fails Low. (I - RO)
The RO will diagnose this failure due to Rod motion and alarms received. The RO will place Rod Control to manual and place charging flow to manual IAW the Immediate Actions Steps of 0-AP-53.00, Loss of Vital Instrumentation/Controls. Following a short brief, the Team will complete AP-53.00.
Verifiable Actions:
: 1) RO/BOP will place Rod Control in manual to stop outward rod motion.
: 2) RO will place charging flow in manual and maintain Pressurizer level at program.
Technical Specifications:
: 1) Should the SRO review Tech Specs, no items will be found.
Technical Requirements Manual/RG 1.97
: 1) No TRM or RG 1.97 requirements are associated with this failure.
Event #3: Steam Flow Channel III Fails Low on A SG. (I - RO, TS-SRO)
The BOP will diagnose the failure based upon alarms and indications received, place the A FRV in manual to control A SG NR level, and restore SG NR level to program IAW 0-AP-53.00, Loss of Vital Instrumentation/Controls.
The affected channel of Steam Flow will be de-selected and the A FRV returned to automatic.
Verifiable Actions:
: 1) The BOP will place the A FRV in manual and restore the A SG NR level to program.
: 2) The RO will de-select the failed channel.
: 3) The BOP will return the A FRV to automatic.
Technical Specifications:
SRO will Review Technical Specifications and determine:
: 1) Tech Spec Table 3.7-1, Item 17, Operator Action 6. With the Number of Operable Channels less than the Total Number of channels, Operation may continue provided the channel is placed in trip within 72 hours, The channel may
 
Appendix D                                  Scenario Outline                                  Form ES-D-1 NRC EXAM - SCENARIO #3 be bypassed for 12 for surveillance testing, and if the requirement cannot be met be in at least Hot Shutdown in 6 hours.
: 2) Tech Spec Table 3.7-2, Item 1.e. High Steam flow in 2/3 steam lines coincident with Low Tavg or low steam line pressure, Operator Action 20. With the number of Operable channels less than the Total number of channels, Operation may continue provided the channel is placed in trip within 72 hours, the channel may be bypassed for surveillance for 12 hours. If these conditions are not satisfied in the time permitted, be in Hot Shutdown in the next 6 hours and reduce RCS temperature and pressure to < 350&deg;F/450 psig in the following 12 hours.
: 3) Tech Spec Table 3.7-3, Item 2a, Steam line Isolation, refers to requirements listed in 2) above.
Technical Requirements Manual/R.G. 1.97.
: 1) TRM - No requirements listed for this failure in section 3.3.2, Appendix R Instrumentation.
: 2) RG 1.97 - Attachment 1, D-19 Variable, 1 Channel per SG required.
Event #4: Loss of 1J 4160V Emergency Bus, Breaker 15J8 opens, #3 EDG Starts and Loads on 1J Bus. (C - RO, TS - SRO).
The Team will diagnose the loss of the 1J Emergency Bus and Start and Load of #3EDG on the bus based on alarms and indications received. The SRO will enter 1-AP-10.07, Loss of Unit 1 Power and proceed through the procedure until the end is reached.
Verifiable Actions:
: 1) BOP/RO will start the B CH pump to provide load to the #3EDG.
: 2) BOP/RO will secure the A and C CH pumps.
: 3) RO will place the B CC pump in PTL in order to re-close the J stub bus tie breaker.
: 4) RO will start A CC pump.
Technical Specifications:
: 1)      The SRO will consult Tech Specs 3.16.B.2 and determine the Unit may be operated for 7 days provided the dependable alternate source can be OPERABLE within 8 hours. SRO will consult with the Shift Manager concerning whether the Dependable alternate source can be Operable within 8 hours.
: 2)      SRO may refer to Tech Spec 3.6.I and determine AFW cross-tie clock is not required.
: 3)      SRO will identify 6/30 clock Tech Spec 3.16, while the alignment of running charging pumps is made using 1-AP-10.07, Attachment 4.
Technical Requirements Manual / RG 1.97:
: 1)      No TRM or RG 1.97 requirements are affected by this event. (The identification of TRM items is normally an STA function - follow-up question post-scenario is recommended at Lead Evaluator discretion.)
Event #5: #1 LP Turbine Left Intercept and Reheat Stop Valve Close, (R - RO, R - SRO, N -
BOP)
The RO/BOP will diagnose this failure based Indications received. The Team will initiate AP-53.00/AP-38.00 and determine that a power reduction to 71% is required using 0-AP-23.00, Rapid Load Reduction.
Verifiable Actions:
 
Appendix D                                  Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #3
: 1) RO will manipulate the CVCS system to Emergency Borate and establish a continuous boration to control RCS Tave during the Turbine Ramp.
: 2) RO will use control rods to adjust delta flux and assist in RCS Tave control.
: 3) BOP will operate Turbine controls to reduce turbine load.
Technical Specifications/TRM/RG-1.97:
: 1) None associated with this Failure.
Event #6: RCS leak of 35 gpm. (C - RO, TS-SRO)
Following completion of the ramp, the RCS leak will be initiated. The RO will perform 1-AP-16.00, Excessive RCS Leakage, Immediate Actions to quantify the leakage.
Verifiable Actions:
: 1) The RO will isolate letdown and control charging flow in manual to quantify RCS leakage.
Technical Specifications:
: 1) The SRO should consult Tech Specs Section 3.1.C, RCS leakage, and identify that RCS leakage is in excess of the allowed maximum and enter a second 6/30 clock to be in HSD/CSD.
Event #7: Failure of RM-159/160 auto actions. (C - BOP)
As the Team is responding to the RCS leak, RM-159/160 for containment Particulate and Gas Rad Monitors will alarm. The BOP will respond using the associated ARPs and determine that the auto functions for these RMs have not occurred. The BOP will follow the ARP guidance and swap containment Instrument Air compressor suction to the external source.
Verifiable Actions:
: 1) The BOP will swap containment instrument air compressors to outside suction by closing 1-IA-TV-101A and 1-IA-TV-101B.
Technical Specifications:
: 1) The SRO may consult Tech Specs and find no requirement for this failure.
Event #8: SBLOCA. (M - ALL)
The RO will diagnose the increase in RCS leakage due to the alarms and indications received, and re-perform the Immediate Actions of 1-AP-16.00. When leakage is determined to be greater than the capacity of a single CH pump, The RO will trip the reactor, perform the Immediate Actions of E-0, and manually safety inject on Step 4.
Due to the size of the RCS leak, several minutes will elapse before RCP trip criteria are met following the reactor trip.
Verifiable Actions:
: 1) RO will raise charging flow and determine leakage is beyond the capacity of single charging pump.
: 2) RO will trip the reactor and perform the Immediate Action Steps of E-0, including manual Safety Injection actuation.
Critical Task:
CT-1: WOG E-1C: Trip all RCPs so that CET temperatures do not become superheated when forced circulation in RCS stops; Trip all
 
Appendix D                                    Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #3 RCPs within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).
Event #9: Failure of Hi and Hi-Hi CLS auto and manual actuation The RO and SRO will continue with E-0 actions; the BOP will be assigned to perform Attachments 1, 2, and 3 of E-0. Upon transition to 1-E-1, Loss of Reactor or Secondary Coolant, containment pressure will have increased to the Hi and HI-HI CLS setpoint (~13 minutes following Event initiation), and CLS Train A and Train B pushbuttons overridden OFF will force entry into FR-Z.1 to start Containment Depressurization equipment.
Verifiable Actions:
: 1) BOP will reset SI, block SI signals when conditions permit, secure one of the three running CH pumps, and secure one of the two running LHSI pumps.
: 2) RO will throttle AFW to the SGs as directed in E-0.
: 3) RO will operate the CS pumps and valves to align CS to containment for depressurization in FR-Z.1, Response to High Containment Pressure.
: 4) BOP will continue manual alignment of valves for Hi and Hi-Hi CLS failure in Attachment 4 of E-0 following transition from FR-Z.1 to 1-E-1.
Critical Task:
CT-2: WOG E-0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (red-path) challenge develops to the CSF. Establish CS flow from at least one CS pump before containment pressure exceeds 60 psia AND at least one RS train before RMT.
Scenario should continue until Lead Evaluator Cue or Step 18 of 1-E-1.
Follow-up Classification: Site Area Emergency FS-1.1.
 
Appendix D                                              Scenario Outline                                        Form ES-D-1 NRC EXAM - SCENARIO #3 Initial Conditions: IC #1 100%, MOL - Cycle 26. The unit has been at 100% power for > 30 days Pre-load malfunctions: (Trigger 30s) o    Override Hi CLS Act pushbutton - TRA o    Override HI CLS Act pushbutton - TRB o    AC_SMS_MODE, OFF, AAC DG LOCAL MODE SWITCH POSITION o    RS0901, TRN A HI CLS FAILS TO ACTIVATE o    RS0902, TRN B HI CLS FAILS TO ACTIVATE Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:
. Unit 1 is at 100% power. All systems and crossties are operable with the following exception:
o AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Turnover:
Unit 1 is at 100% power. All systems and crossties are operable with the following exception:
AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. . IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* Unit boron 760 PPM.
* A BAST 8.0 w/%.
Event        Malf. #s        Severity                          Instructor Notes and Required Feedback 1                N/A                      Deleted 2            RC0801            -1 Deg    Failure of Median Tave in the Low Direction, AP-53.00.
3            MS0801            -1 Deg    Failure of Steam Flow Channel III Low, A SG. AP-53.00 4            EL4902            TRUE      1J 4160V emergency Bus Off-site Power Supply Breaker Trips.
Switch 5                O/R,                    Test Button on Main Turbine Control Fails causing the LP Turbine 1 ON TEST_IRL                    Intercept and Reheat Stop Valve Closure. AP-23.00 Ramp to 71% Power.
_IIL 6                                3.5%
RC04 Deg    RCS leak of 35 gpm. AP-16.00.
RM0202          +.1 Deg
: 7.            RM0201,          +.1 Deg    Containment Particulate and Gas RM auto actions on High Alarm fail to CA03            TRUE      function.
CA04            TRUE
                              .6 DEG, 8            RC0101          600 Sec    SBLOCA Ramp
 
Appendix D                              Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #3 SETPT for 9      Hi-Hi CLS  60 psia O/R CLS_ACT    ACTIVE
_TRA                Hi and HI-HI CLS fail to function, requiring manual alignments of components, and FR-Z.1 entry.
O/R CLS_ACT    ACTIVE
_TRB Scenario Objectives:
A. Deleted.
B. Given a failure of Median Tave in the Low Direction, respond IAW AP-53.00.
C. Given a failure of the selected Steam Flow channel on the A SG, respond IAW AP-53.00 to take manual control of the A FRV, control A SG NR level and return the A FRV to automatic.
D. Given the trip of the off-site power supply breaker to the 1J 4160V Bus and the subsequent start and load of #3 EDG on the bus, respond IAW AP-10.07 to restart/verify proper loads on the 1J bus.
E. Given the malfunction of the 1RL/1LL test pushbutton, respond IAW AP-53.00, AP-38.00, and AP-23.00 to ramp the Unit to 71 % power.
F. Given an RCS leak of 35 gpm, respond IAW AP-16.00 to quantify the leakrate.
G. Given a containment Gas High RM Alarm, respond IAW ARP to verify/perform the associated automatic actions.
H. Given a SBLOCA inside containment with the failure of Hi-Hi-CLS to actuate, respond IAW E-0 and E-1 to respond to the RCS transient; and restore containment depressurization equipment IAW FR-Z.1.
 
SHIFT TURNOVER INFORMATION OPERATING PLAN:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
Shift orders are to maintain 100% power on Unit #1.
The last shift performed two 35 gallon alt dilutions followed by a manual makeup for training.
A BAST at 8.0 W/%. .
 
Appendix D                              Required Operator Actions              Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3              Event No.: 1      Page 9 of 103 Event
 
== Description:==
Swap Running EH Pumps, 1-OP-EH-001, Section 5.6.
Cue: When team ready.
Time        Position                            Applicants Action or Behavior EVENT #1 DELETED.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                    Event No.: 2                  Page 10 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
Note:  An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.
The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.
A facility representative will be present for consultation with the Evaluation Team, as needed.
Time        Position                                  Applicants Action or Behavior Diagnoses failure of median Tave with the following indications/alarms:
Team Alarms:
* 1H-C4, LOW TAVE FW CONTROL
* 1H-A4, T AVG > < T REF DEVIATION
* 1G-F8, ROD BANK D WITHDRAW
* 1C-C8, PRZR HIGH LEVEL HEATERS ON Indications:
* Median Tave (recorder and indicator) off-scale low
* Individual Loop Taves indicating NORMAL
* Control Rods stepping OUT and reactor power decreasing SRO          Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS RO          [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL RO identifies individual loop Tave indications are normal
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                      Event No.: 2                  Page 11 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
RO        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION RO takes manual control of the control rods to stop the outward rod motion and also takes manual control of pressurizer level control (1-CH-FCV-1122) to maintain pressurizer level at program.
It should be noted that charging might not be placed in manual until procedurally directed.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
SRO Directs BOP to perform Annunciator Response Procedure 1G-F8.
Completes Brief and continues with AP-53.00.
NOTE: 1G-F8 response located at the end of this section.
SRO        *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO              Identify that reactor power is less than 100%.
SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
* Median Tave, Step 9 RO        Identify that Median Tave has failed LOW.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 2                      Page 12 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
SRO        Caution prior to step 9:
CAUTION: Delta flux must be monitored and maintained within band if rods have moved.
Note Prior to Step 9:
NOTE: Depending on the instrumentation failure, the TAVE input to the Steam Dumps may be invalid, causing the Steam Dumps to stay open longer or never open at all.
SRO        9. CHECK LOOP/MEDIAN T/Tave - NORMAL a)  Median Tave - NORMAL a)  RNO - Do the following:
: 1) Place ROD CONT MODE SEL switch in MANUAL, as required.
RO will report that Rod Control is already in manual.
: 2) Take manual control of charging, as necessary to maintain pressurizer level at program.
RO will report that charging flow is in manual or will place charging flow in manual.
: 3) Refer to Attachment 4 (Describes Tave control system)
: 4) If no other instrumentation failure exists, then go to step 13.
Goes to Step 13 0-AP-53.00 SRO        13.      CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001 RO        Checks 1-OPT-RX-001, Attachment 4, and determines that the Calorimetric program is unaffected.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                    Event No.: 2                  Page 13 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE SRO directs STA to review Reg. Guide 1.97. The STA will report that Median Tave is not a Reg. Guide 1.97 component.
: 13.      RNO - GO TO Step 16 SRO        16. Review the following:
* TS 3.7
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA reports that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
SRO        17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS RO        Reports no other instrument failure exists.
GOES TO STEP 19 SRO        19. PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C
                          - END -
Note: If Control Rods stepped out greater than 230 steps, the team will perform ARP 1G-F8. 1G-F8 Actions are contained on the next two pages
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                    Event No.: 2                Page 14 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
1G-F8 (Rod Bank D Withdrawal)
BOP        1. CHECK ALARM - ROD DEMAND POSITION GREATER THAN OR EQUAL TO 228 STEPS ON CONTROL BANK D - GP 1 DEMAND POSITION.
Identifies that Bank D is greater than 230 steps.
1G-F8 (Rod Bank D Withdrawal)
BOP
: 2. PUT ROD CONTROL MODE SEL SWITCH IN MANUAL.
Verifies that Rod Control is in Manual.
1G-F8 (Rod Bank D Withdrawal)
BOP
: 3. VERIFY ROD MOTION - STOPPED 1G-F8 (Rod Bank D Withdrawal)
: 4. CHECK BOTH CONTROL BANK D STEP COUNTERS - LESS THAN OR EQUAL TO 230 STEPS.
If less than 230 steps proceed to Step 5.
RNO -
a)  Step rods out to make both Bank D Step Counters equal. (Group step counters must be equalized by stepping out only, to prevent Rod Group Sequence Error).
Steps Rods out as needed to equalize group step counters.
b)  Reset Bank D Step Counters to 230 steps.
Uses a stylus to reset the Bank D Step Counters to 230 steps.
1G-F8 (Rod Bank D Withdrawal)
BOP NOTE:
Rods may have to be stepped in as many as two steps below the fully withdrawn position to clear Annunciator 1G-F8.
: 5. STEP CONTROL BANK D RODS IN AS NECESSARY TO CLEAR 1G-F8, ROD BANK D WITHDRAW.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 2                  Page 15 of 103 Event
 
== Description:==
Failure of Median Tave in the Low Direction, 0-AP-53.00.
Cue: By Examiner.
BOP        1G-F8 (Rod Bank D Withdrawal)
: 6. POSITION CONTROL BANK D RODS AS DETERMINED BY SHIFT SUPERVISION 1G-F8 (Rod Bank D Withdrawal)
BOP NOTE:
Both group step counters for Control Bank D should be the same before performing Step 7.
: 7. LOCALLY CHECK THE BANK OVERLAP COUNTER - AT 384 PLUS CURRENT CONTROL BANK D DEMAND POSITION.
Contacts a field operator to determine the bank overlap counter.
384 + 228 = 612 Field operator will report bank overlap position as indicated on the simulator.
1G-F8 (Rod Bank D Withdrawal)
BOP
: 8. NOTIFY SHIFT SUPERVISION END OF EVENT 2
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 3                  Page 16 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior Diagnoses failure 1-MS-FT-1474 with the following indications/alarms:
BOP Alarms:
* 1H-E5 STM GEN 1A FW >< STM FLOW
* 1F-D7 STM GEN 1A CH 4 FW < STM FLOW
* 1H-G5 STM GEN 1A LVL ERROR.
Indications:
* Step decrease in 1A SG Steam Flow indication CH-III
* Decreasing level on A SG.
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS BOP        [1] VERIFY REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL BOP identifies Channel IV indication for steam flow is NORMAL.
BOP        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of A SG feed reg valve and increases demand (FF >
SF) to restore level to program.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 3                  Page 17 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
SRO        *3        VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO        Identify that reactor power is less than 100%.
Note:    Based on the feed flow > steam flow mismatch established by the BOP, Calorimetric power may exceed 100% during restoration of A SG NR level to program.
SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
SG Steam Flow, Step 7 BOP            States A Steam Flow affected.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 3                  Page 18 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.
SRO        7. CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS -
NORMAL
* Steam Pressure BOP
* Steam Flow
* Feed Flow
* Steam Generator Level Determines CH III Steam flow instrumentation for A SG is NOT normal.
BOP Step 7. RNO IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level BOP        Control system has failed, THEN do the following:
a)  Place the associated Feed Reg Valve in MANUAL.
RO        Verifies A SG MFRV controller, 1-FW-FCV-1478, in manual b) Control SG level at program level (44%, a band will be given).
BOP        Verifies A SG NR level is returning to program level.
c) Select the redundant channel for affected SG(s)
RO        Selects Channel IV Steam Flow for A SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV).
d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.
BOP        Places A SG FRV controller, 1-FW-FCV-1478, in automatic control
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 3                      Event No.: 3                  Page 19 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
SRO        Step 7. RNO (Continued)
Perform follow-up actions:
a)  Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.
b) Refer to the following Tech Spec 3.7 items:
* Table 3.7-1, 12 and 17
* Table 3.7-2, 1.c, 1.e, and 3.a
* Table 3.7-3, 2.a, and 3.a Determines Table 3.7-1 item 17, 3.7-2 item 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours).
c)  Refer to Attachment 1.
d) IF no other instrumentation failure exists, THEN GO TO Step 13.
SRO        13. Review OPT-RX-001, Rx Power Calorimetric using PCS computer program, Attachment 4, to determine operability of calorimetric and need to perform OPT-RX-007, Shift Average Power Calculation.
SRO/RO determines that OPT-RX-001 is NOT impacted and OPT-RX-007 will NOT need to be performed.
If it appears that the SRO/RO will take action to perform 1-OPT-RX-007, the Unit 2 Operator will state that he will perform 1-OPT-RX-007.
Note: Lead Evaluator must concur with Unit 2 action to perform 1-OPT-RX-007.
SRO        14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 14 if not Reg. Guide 1.97)
SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-MS-FT-1474 is a Reg. Guide 1.97 component.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 3                    Page 20 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.
Cue: By Examiner.
SRO        15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report review of CEP 99-0029 is complete and has been reviewed with the Shift Manager.
[CEP 99-0029 requires one channel of steam flow indication per SG, with channel available, no further action is required.]
SRO        16. Review the following:
* TS 3.7 Determines Table 3.7-1 item 17, 3.7-2 item 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours).
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
SRO        17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS BOP        Reports no additional failure exists SRO        GOES TO Step 19 SRO        19. PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C
                          - END EVENT        #3
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 3                    Event No.: 4                  Page 21 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Time        Position                                  Applicants Action or Behavior 1-AP-10.07 TEAM        Diagnose the failure based on the following:
Alarms:
1K-B8, UPS SYSTEM 1B TROUBLE 1K-D5, CC PP 1B IN LOCAL CONTROL OR OL TRIP 1K-E7, CC PPS DISCH HDR LO PRESS 1B-G5, INST AIR DRYER TROUBLE Indications:
                              #3 EDG Start and Load on 1J 4160 V Bus.
1-CC-P-1B GREEN and AMBER Breaker Indication Lights LIT.
1-AP-10.07 SRO        SRO will hold a Transient Brief and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
Directs the BOP to review ARPs for Lit annunciators, SRO/RO will continue with 1-AP-10.07.
Directs RO/BOP to contact Service Building Operator to check local status of Breaker 15 J8.
Completes Brief and continues with AP-10.07.
Step 1, 1-AP-10.07 SRO        NOTE:
* If both units are affected, local actions should be coordinated.
* The AAC Diesel Generator will automatically start if an undervoltage occurs on Transfer Buses D and F.
* With Degraded Voltage or Undervoltage on 2J Bus, or a loss of Unit 2B DC Bus, Breaker 15J3 will not close automatically, except with a valid Unit 1 SI signal.
* EPIPs may be applicable.
: 1.        CHECK UNIT - BLACKOUT HAS OCCURRED
* Transfer Buses D and F - DEENERGIZED AND
* All Station Service Buses - DEENERGIZED RO            Reports Blackout has not occurred.
SRO        GOES TO Step 39.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                  Page 22 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 39, 1-AP-10.07 SRO        39      CHECK THE FOLLOWING BREAKERS - ANY OPEN:
* 15D1 OR
* 15F1 OR
* 15H8 OR
* 15J8 RO            Reports Breaker 15J8 Open.
Step 40, 1-AP-10.07 SRO        40      CHECK 4160V EMERGENCY BUSES - BOTH ENERGIZED RO            Reports both Emergency Buses Energized.
Step 41, 1-AP-10.07 SRO        41      CHECK SI OR HI HI CLS - NOT ACTUATED RO        Reports SI or HI HI CLS NOT Actuated Step 42, 1-AP-10.07 SRO CAUTION:        To prevent overload of EDG 1, the UV trip of 1-CH-P-1A should NOT be reset if 1-CH-P-1C is running on the normal feeder AND the UV trip of 1-CH-P-1C (Normal) should NOT be reset if 1-CH-P-1A is running.
NOTE: A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading..
NOTE: The CHG pumps powered from the 1H Bus receive an auto-start signal when the 1J Bus is deenergized.
42        INITIATE ATTACHMENT 4 TO ALIGN EMERGENCY BUS LOADS TO PREVENT EDG OVERLOADING SRO            Directs BOP to perform Attachment 4 of 1-AP-10.07.
Note: Attachment 4 actions listed at the end of this section.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                  Page 23 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 43, 1-AP-10.07 SRO        43      GO TO STEP 45 Step 45, 1-AP-10.07 SRO        NOTE: At least one method of communications should be established before commencing local actions.
45      CHECK COMMUNICATIONS CAPABILITY:
* Gaitronics OR
* Station Radios RO            Reports Gaitronics and / or Station Radios Available.
Step 46, 1-AP-10.07 SRO        46      CHECK EDG - HAS REENERGIZED AFFECTED EMERGENCY BUS
* 15H3 - CLOSED OR
* 15J3 - CLOSED RO            Reports 15J3 Breaker closed.
Step 47, 1-AP-10.07 SRO        47      RESTORE EMERGENCY BUS STUB BUS:
a) Put CC PUMP control switch in PTL RO            Places 1-CC-P-1B control switch in PTL.
b) Put RHR PUMP control switch in PTL RO            Checks 1-RH-P-1B in PTL.
c) Locally close Stub Bus feeder breakers on energized Emergency Buses
* 15J9 OR
* 15H9 SRO            Directs RO to contact Service Building Operator to Close 15J9.
RO            Contacts Service Building Operator to Close breaker 15J9 When local report of Breaker 15J9 closed, RO holds Focus Brief to inform the Team, and checks Annunciator 1K-H4 Clear.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 3                  Event No.: 4                  Page 24 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 48, 1-AP-10.07 SRO        CAUTION:
* When the EDG is the only source of power to an Emergency Bus, the associated Component Cooling Pump should NOT be in service if a HI-HI CLS is in progress.
* Restrictions on CC pump operation do NOT apply below RCS temperature of 350&deg;F.
48        CHECK CC PUMPS - AT LEAST ONE RUNNING RO            Reports No CC Pumps running on Unit 1.
SRO            Holds Team brief to discuss the start of 1-CC-P-1A. Since CC system is cross-tied and the CC header is pressurized, throttling the CC pump discharge valve prior to start is unnecessary. Team will concur and the brief closed.
SRO            Direct RO to Start 1-CC-P-1A.
RO            Makes Gaitronics Announcement and Starts 1-CC-P-1A.
Step 49, 1-AP-10.07 SRO        49        PLACE STANDBY CC PUMP IN AUTO-AFTER-STOP SRO            Direct RO to Place 1-CC-P-1B in Auto after Stop.
RO            Places 1-CC-P-1B in AUTO.
Evaluator Note: At Evaluator discretion, the next Event (Event 5) may be initiated at this time.
Step 50, 1-AP-10.07 SRO        50        CHECK RHR - WAS IN SERVICE RO            Reports RHR NOT in service.
SRO            GOES TO Step 52.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                  Event No.: 4                  Page 25 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 52, 1-AP-10.07 SRO        CAUTION:
* If a HI-HI CLS has occurred on Unit 1, 1-FC-P-1A must not be started on EDG 1 if 1-CS-P-1A is running.
* If a HI-HI CLS has occurred on Unit 2, 1-FC-P-1B must not be started on EDG 2 if 2-CS-P-1A is running.
NOTE:
* Power supplies to 1-FC-P-1A (Norm)1H1-2N2A, (Alt)1B1-1-4D, or (Backup) 2H1-2S10B.
* Power supplies to 1-FC-P-1B (Norm) 2H1-2S10B, (Alt)1B1-1-4D, or (Backup)1H1-2N2A.
52      CHECK SFP COOLING - EITHER PUMP RUNNING RO            Reports 1-FC-P-1B Running Step 53, 1-AP-10.07 SRO        53      CHECK INTAKE CANAL LEVEL - STABLE OR INCREASING RO            Reports Intake Canal Level 29 feet and Stable.
Step 54, 1-AP-10.07 SRO        NOTE: If two CHG pump CC pumps or two CHG pump SW pumps are running, one pump should be secured and placed in AUTO.
54      CHECK CHG PUMP AUXILIARIES:
* CHG pump CC pump - RUNNING
* CHG pump SW pump - RUNNING RO            Reports 1-CC-P-2A and 1-SW-P-10A Running.
Step 55, 1-AP-10.07 SRO        55      CHECK SEMI-VITAL BUS - POWER HAS BEEN INTERRUPTED RO            Reports Semi-Vital Bus Power has not been interrupted.
SRO            GOES TO Step 57 Step 57, 1-AP-10.07 SRO        57      CHECK BOTH PRZR PORV BLOCK VALVES - ENERGIZED RO            Reports Both PRZR Block Valves energized
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                    Page 26 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 58, 1-AP-10.07 SRO        58      CHECK CC TO EXCESS LETDOWN HX - NOT TRIPPED
* FI-CC-109 RO/BOP            Reports FI-CC-109 Flow is Approximately 160 gpm and Stable.
Step 59, 1-AP-10.07 SRO        59      CHECK IA SYSTEM ANNUNCIATORS - NOT LIT:
* 1B-E6, IA LO HDR PRESS/IA COMPR 1 TRBL
* 1B-G5, INST AIR DRYER TRBL
* 1B-E5, SA COMPR TRBL
* 1B-F5, CTMT INST AIR COMPR TRBL RO            Reports 1B-E6 and 1B-G5 are LIT.
SRO            Directs BOP to review the ARPs for the lit annunciators.
BOP            Directs Turbine Building Operator to investigate cause for alarms in IA System.
Step 60, 1-AP-10.07 SRO        60      CHECK UNIT CONDITIONS a) PRZR level - STABLE b) PRZR pressure - STABLE c) RCS TAVE - STABLE RO            Reports Parameter normal with no abnormal trends.
Step 61, 1-AP-10.07 SRO        61      CHECK VENTILATION FANS - OPERATING
* Auxiliary BLDG Central
* Safeguards BOP            Reports Auxiliary Building Central and Safeguards fans operating normally
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                    Page 27 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 62, 1-AP-10.07 NOTE: Any MCR Chiller that was operating prior to the loss of power will have tripped and the compressor will not automatically restart. The Chiller must be shutdown and then restarted IAW 0-OP-VS-006, Control Room and Relay Room Ventilation System.
SRO 62      CHECK THE FOLLOWING MCR VENTILATION EQUIPMENT -
OPERATING:
* One Control Room Chiller (Two Control Room Chillers if SI initiated on either unit AND any MCR or ESGR temperature indicator greater than 84&deg;F)
BOP            Reports 1-VS-E-4C and 1-VS-E-4E Running.
SRO
* One Unit 1 Control Room AHU
* One Unit 2 Control Room AHU
* One Unit 1 ESGR AHU
* One Unit 2 ESGR AHU BOP            Reports One Unit 1 and Unit 2 MCR and ESGR AHU operating.
Step 63, 1-AP-10.07 SRO        63      CHECK CRDM FANS - THREE RUNNING BOP            Reports Three CRDM Fans Running Step 64, 1-AP-10.07 SRO        64      CHECK CONTAINMENT AIR RECIRC FANS - THREE RUNNING BOP            Reports three fans running.
Step 65, 1-AP-10.07 SRO        CAUTION:
* If a HI-HI CLS has occurred on Unit 1, 1-FC-P-1A must not be started on EDG 1 if 1-CS-P-1A is running.
* If a HI-HI CLS has occurred on Unit 2, 1-FC-P-1B must not be started on EDG 2 if 2-CS-P-1A is running.
NOTE:
* Power supplies to 1-FC-P-1A (Norm)1H1-2N2A, (Alt)1B1-1-4D, or (Backup) 2H1-2S10B.
* Power supplies to 1-FC-P-1B (Norm) 2H1-2S10B, (Alt)1B1-1-4D, or (Backup)1H1-2N2A.
65      CHECK SFP COOLING - EITHER PUMP RUNNING RO            Reports 1-FC-P-1B Running
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                Page 28 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 66, 1-AP-10.07 SRO        66      CHECK AFW MOVS - BOTH TRAINS ENERGIZED BOP            Reports all AFW MOVs energized.
Step 67, 1-AP-10.07 SRO        67      CHECK BORIC ACID ALIGNMENT:
* One Tank in service
* One BATP in service BOP            Reports 1-CH-P-2A running and aligned to the A BAST.
Step 68, 1-AP-10.07 SRO        68    CHECK CVCS HEAT TRACING PRIMARY AND BACKUP PANELS - ALL ENERGIZED
* Primary panels 2A1, 2A2, and 2A3 - powered from 1H 480V Bus RO            Reports heat tracing panels energized.
Step 69,1-AP-10.07 NOTE: The N-16 and MGPI Radiation Monitors are powered from Breaker 1H1                                    4B2 or 2H1-1-2D-2 depending on the position of throw-over switch 1-EP-TRS-DB-101 located near MCC 1H1-1.
SRO        69      CHECK RADIATION MONITORS - OPERABLE
* No sample pump deenergized
* No flow faults
* No monitors deenergized
* Annunciator 1A-C3, N-16 TROUBLE - NOT LIT
* Annunciator 0-RMA-C5, PROCESS VENT RAD MON TRBL - NOT LIT
* Annunciator 0-RMA-D5, VENT STACK #2 RAD MON TRBL - NOT LIT BOP            Reports sample pumps energized, No flow faults, No monitors deenergized.
Reports Annunciators 1A-C3, RMA-C5, RMA-D5 - not LIT.
Step 70, 1-AP-10.07 NOTE:      The CTMT Particulate and Gas Rad Monitor skids are powered from 1MR1A, Breaker 43, which is supplied from 480V MCC 1C1-2. These monitors are required to comply with Tech Spec 3.1.C.1.
SRO        70    LOCALLY CHECK CTMT PARTICULATE AND GAS RAD MONITOR -
OPERABLE (SKID/ SAMPLE PUMP ENERGIZED) (IF MCC 1C1-2 CONFIRMED TO BE DEENERGIZED, NO NEED TO CHECK LOCALLY)
SRO            Directs BOP to dispatch Aux Building Operator to check local RM skid.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                  Page 29 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 71, 1-AP-10.07 SRO        71. ___ CHECK SW SUPPLY MOVS - ALL ENERGIZED RO            Reports SW MOVS energized.
Step 72, 1-AP-10.07 SRO        72      CHECK TECH SPEC LCOS:
* Tech Spec 3.16 SRO            The SRO will consult Tech Specs 3.16.B.2 and determine the Unit may be operated for 7 days provided the dependable alternate source can be OPERABLE within 8 hours. SRO will consult with the Shift Manager concerning whether the Dependable alternate source can be Operable within 8 hours.
SRO may refer to Tech Spec 3.6.I and determine AFW cross-tie clock is not in effect.
SRO will identify 6/30 clock Tech Spec 3.16, while the alignment of running charging pumps is made using 1-AP-10.07, Attachment 4.
SRO will brief the Team on Tech Spec requirements.
Step 73, 1-AP-10.07 CAUTION:      If any EDG has operated below 570 KW for three days, additional loading will be required to prevent exhaust system souping. Refer to Attachments 7 and 8.
SRO        73    CHECK 4160V EMERGENCY BUS 1H - ENERGIZED FROM OFFSITE POWER
* 15F1 - CLOSED
* 15H8 - CLOSED RO/BOP            Reports 15F1 and 15H8 breakers closed.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 4                    Page 30 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 74, 1-AP-10.07 CAUTION:
* Shift Supervision should direct the loading of EDG 3 to 1J or 2J Emergency Bus to best support plant recovery.
* If any EDG has operated below 570 KW for three days, additional loading will be required to prevent exhaust system souping. Refer to Attachments 7 and 8.
NOTE:
* The RSS transformer cooling fans, heaters, and load tap changer controls are powered from 1J1-1-3B2 or 2J1-1-4A2 depending on position of the throwover switch near 1-SA-TK-2 in Unit 1 Turbine BLDG basement. The switch shall be aligned to an energized bus.
* Until the throwover switch is aligned to an energized bus, the RSST load tap changers are inoperable. Tech Spec 3.16.B.2 should be reviewed for required actions.
SRO        74    CHECK AC EMERGENCY BUS 1J - ENERGIZED FROM OFFSITE POWER
* 15D1 - CLOSED
* 15J8 - CLOSED RO/BOP            Reports breaker 15D1 closed, breaker 15J8 Open.
Step 74, RNO Do the following:
a) IF 1J Bus energized from EDG 3, THEN do the following:
: 1) Monitor EDG 3 parameters IAW Attachment 8.
SRO            SRO Directs RO/BOP to contact Service Building Operator to monitor #3 EDG using Attachment 8 of 1-AP-10.07.
: 2) Continue efforts to restore normal Emergency Bus power.
: 3) WHEN cause of power loss identified and corrected, THEN initiate 0-AP-10.08, STATION POWER RESTORATION.
Step 75, 1-AP-10.07 SRO        75. ___ CHECK ANY STATION SERVICE BUS - DEENERGIZED:
* 15A1 and 15A2 - OPEN OR
* 15B1 and 15B2 - OPEN OR
* 15C1 and 15C2 - OPEN BOP            Reports All Station Service Buses energized.
SRO        Step 75, RNO IF ALL 480V Station Service Buses are energized, THEN GO TO Step 97.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                  Event No.: 4                  Page 31 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 97, 1-AP-10.07 SRO        97      NOTIFY THE FOLLOWING:
* OMOC
* STA
* Electrical Foreman SRO            Notifies Shift Manager that 1-AP-10.07 complete and request notification to OMOC, STA, and Electrical Foreman be made.
Attachment 4 of 1-AP-10.07 on next page.
END EVENT #4
 
Appendix D                                    Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 3                      Event No.: 4                  Page 32 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Time      Position                                    Applicants Action or Behavior Step 1, Attachment 4, 1-AP-10.07 BOP CAUTION: An EDG can NOT initially be loaded to greater than 1300 KW prior to an SI or HI HI CLS, with the exception of loads that will trip when a HI HI CLS occurs, or loads which are running yet assumed to start on a HI HI CLS.
CAUTION: Total EDG load shall not exceed 2750 KW.
NOTE:
* The purpose of this Attachment is to limit EDG loading so that a subsequent HI HI CLS actuation will not overload the EDG.
* EDG load must be monitored closely during pump operations.
* A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading.
BOP
: 1. IF EDG 1 is the sole source of power to Emergency Bus 1H, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.
Identifies #1 EDG NOT the sole source to 1H Emergency Bus and GOES TO Step 2.
Step 2, Attachment 4, 1-AP-10.07 BOP        NOTE: A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading.
Notifies SRO of 6/30 hour TS 3.16 clock in effect until 1-CH-P-1B running on #3 EDG.
BOP
: 2. IF EDG 3 is the sole source of power to Emergency Bus 1J, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.
: a. Check running or start 1-CH-P-1B or 1-CH-P-1C on Emergency Bus 1J IAW Shift Supervision direction.
BOP            Starts 1-CH-P-1B with concurrence of SRO.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                      Event No.: 4                  Page 33 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 2, Attachment 4, 1-AP-10.07 BOP                b. IF a CHG pump can NOT be started on Emergency Bus 1J, THEN do the following. Otherwise, enter N/A.
Enters N/A for substeps b.1, b.2, and b.3.
: c. Check or place the remaining CHG pump supplied from Emergency Bus 1J in PTL.
Identifies 1-CH-P-1C (Alternate) in PTL.
: d. IF Emergency Bus 1H is supplied by offsite power, and 1-CH-P-1A or 1-CH-P-1C is running, THEN stop CHG pump(s) supplied from Emergency Bus 1H and place in Auto.
RO/BOP            Confer with SRO and secures 1-CH-P-1A and 1-CH-P-1C.
: e. Determine Emergency Bus 1J load limit IAW the following equation, where (x) equals the total of the KW ratings of all RUNNING equipment from the table below.
                                            *___________ + 1300 KW = _________________
(x)                        EDG Load Limit BOP            BOP will write 100 in the (x) blank, and write 1400 in the EDG Load Limit blank.
: f. IF existing EDG load is greater than the limit calculated in Substep e.
above, THEN reduce EDG load to less than or equal to the calculated load.
BOP will identify ~950kW load on #3 EDG.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                  Event No.: 4                    Page 34 of 103 Event
 
== Description:==
1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.
Cue: By Evaluator.
Step 3. Attachment 4, 1-AP-10.07 BOP        3. Notify Auxiliary Building Operator to increase monitoring of CHG pump lube oil temperature.
BOP contacts the Aux Building Operator to monitor CHG pump lube oil temperature Step 4, Attachment 4, 1-AP-10.07 BOP        4. Increasing monitoring of CHG pump bearing temperatures using the Plant Computer system.
BOP will monitor CHG pump bearing temperatures using the Plant Computer system.
BOP returns the Attachment to the SRO and provides a short brief of Attachment results.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 35 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
Time        Position                                  Applicants Action or Behavior Team        Identify the failure of the Test Button based on the following:
Alarms:
PCS Alarm for MSR Indications:
                                    ~ 9 MW step decrease indicated on MW Videographic Recorder.
0.2 &deg;F increase in RCS Tave Test 1RL 1IL Button on turbine control panel 1RL CLOSED indicating light LIT on turbine control panel 1IL CLOSED indicating light LIT on turbine control panel.
Note: Team may directly enter 1-AP-38.00 (see page 39).
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS NOTE: SRO may directly enter AP-38.00, MAIN STEAM SYSTEM CONTROL MALFUNCTION. See Page 39.
BOP        [1] VERIFY REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL BOP identifies Valve Position Indications are NORMAL.
BOP        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP Identifies no controls need to be placed in Manual.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 36 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
SRO        *3        VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO        Identify that reactor power is less than 100%.
SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
Turbine Valve Position, Step 10 BOP            Reports #1 LP Turbine Left Intercept and Reheat Stop Valves are closed.
CAUTION: If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.
SRO        10. ___ CHECK STEAM SYSTEM CONTROLS - NORMAL
* Steam Dumps / PORVs
* Turbine Controls
* Turbine Valve Positions
* Turbine Monitoring Lights BOP            Reports Turbine Valve positions are abnormal.
SRO            Initiates AP-38.00
 
Appendix D                                  Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                      Event No.: 5                      Page 37 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
Time        Position                                  Applicants Action or Behavior Step 1, 1-AP-38.00 SRO        1  CHECK STEAM DUMP VALVES - CLOSED BOP            Reports Steam Dump Valves closed / normal.
Step 2, 1-AP-38.00 SRO        2    CHECK SG PORVS - CLOSED BOP            Reports SG PORVs closed Step 3, 1-AP-38.00 SRO        3        CHECK THE FOLLOWING CONDITIONS:
* Reactor power - LESS THAN OR EQUAL TO 100%
* Turbine load - NORMAL BOP            Reports reactor power < 100%
RO            Reports Turbine Load NOT Normal SRO        Stabilize Reactor power and Turbine load less than 100% using Attachment 2.
NOTE: No Actions required in Attachment 2 for this event.
Step 4, 1-AP-38.00 NOTE: The power reductions required by Step 4 are intended for failures causing full or partial closure of a control valve, or if valve closure is required for maintenance.
SRO        4        CHECK MAIN TURBINE AND MSR STEAM CONTROL VALVES:
a)        MSR Steam supply MOVs and FCVs - NORMAL BOP            Report MSR MOVs and FCVs normal.
b)        Turbine Governor Valves and Stop Valves - NORMAL BOP            Report Turbine GVs and SVs normal.
c)        Reheat Stop and Intercept Valves - NORMAL BOP                Report Reheat Stop and Intercept Valves ABNORMAL RNO c)    Reduce Reactor power to less or equal to 71% IAW 0-AP-23.00, RAPID LOAD REDUCTION, OR 1-OP-TM-005, UNIT RAMPING OPERATIONS.
SRO        INITIATES 0-AP-23.00 to reduce load to less than 71%.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 38 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
RO        Reactivity control during AP-23.00 Ramp:
146 gallons of Boric Acid needed to reduce power to 71%. 50 gallons added during Emergency Boration, leaving 96 gallons to be added using normal boration at an average rate of 5.8 gpm. Control Bank D rod height at end of ramp 197 Steps.
Gallons of PG to be added to stabilize at end of ramp 1957.
SRO        Completes Brief and continues with AP-23.00.
EVALUATOR NOTE: RO Emergency borates for 25 seconds which corresponds to
                          ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.
SRO        Caution Prior to Step 1:
* Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.
Notes Prior to Step 1:
* Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
* When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
* Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
* The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
* For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.
0-AP-23.00 RO        1. TURN ON ALL PRZR HEATERS
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                Page 39 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
: 2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:
BOP            a) Verify turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.
RO            b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5&deg;F.
SRO/BOP            c) Verify or place turbine in IMP IN or IMP OUT as determined by Shift Supervision The SRO can choose IMP IN or IMP OUT.
BOP            d) Adjust SETTER to desired power level e)  Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute) f)  Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) g) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.
SRO        3. CHECK EMERGENCY BORATION - REQUIRED The team may decide to emergency borate after the ramp has progressed to the point that Tave and Tref are matched (or close).
SRO        Note Prior to Step 4:
* Step 4 or Step 5 may be performed repeatedly to maintain Tave and Tref matched, Flux in band, and control rod position above the LO-LO insertion limit.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 40 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
0-AP-23.00 RO        4. PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:
a) Verify or raise CHG flow to greater than 75 gpm b) Transfer the in-service BATP to FAST c) Open ( )-CH-MOV-( )350 (~25 seconds) d) Monitor EMRG BORATE FLOW
                                        *  ( )-CH-FI-( )110 e)  After required emergency boration, perform the following:
: 1) Close ( )-CH-MOV-( )350
: 2) Transfer the in-service BATP to AUTO
: 3) Restore Charging flow control to normal RO        5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.
SRO        Notes Prior to Step 6:
* If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
* RCS Tave must be maintained less than or equal to 577&deg;F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
* I & C should be contacted to provide assistance with adjusting IRPIs.
RO        6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG RO        *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.
BOP        8. MONITOR STEAM DUMPS FOR PROPER OPERATION
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                Event No.: 5                    Page 41 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
0-AP-23.00 SRO        9. NOTIFY THE FOLLOWING:
* Energy Supply (MOC)
* Polishing Building
* Chemistry
* OMOC SRO        10. EVALUATE THE FOLLOWING:
* EPIP applicability
* VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.
[VPAP-2802 and EPIP are not applicable for this event.]
SRO        11. CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR When reactor power has decreased >15%, then chemistry will be notified.
END EVENT #5
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 3                    Event No.: 5                  Page 42 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
Time        Position                                Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO        1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO        2. Adjust 1-CH-YIC-1113 to desired total gallons RO        3. Adjust 1-CH-FC-1113A to desired flow rate.
RO        4. Place the MAKE-UP MODE SEL switch in the BORATE position.
RO        6. Check proper valve positions.
: 5. Place the MAKE-UP MODE CNTRL switch in the START position RO RO        7. Adjust boration rate using 1-CH-FC-1113A, as necessary.
RO        8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.
a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.
b) Enter N/A for the remaining steps in this Attachment.
Attachment 5 is on the next page RO        9. Check controllers for Primary Grade water and Boric Acid are set correctly.
RO        10. Place the MAKE-UP MODE SEL switch in the AUTO position.
RO        11. Place the MAKE-UP MODE CNTRL switch in the START position.
RO        12. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 3                  Event No.: 5                  Page 43 of 103 Event
 
== Description:==
Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.
Cue: 1-CC-P-1B in Auto and Examiner Ready.
Time        Position                                Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions
: 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
: 2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
: 3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
: 4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
: 5. Place the MAKE-UP MODE CNTRL switch in the START position.
: 6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
: 7. Check proper valve positions.
: 8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position
: 9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
: 10. Check or place the control switches in the AUTO position.
: 11. Check controllers for Primary Grade water and Boric Acid are set correctly.
: 12. Place the MAKE-UP MODE SEL switch in the AUTO position.
: 13. Place the MAKE-UP MODE CNTRL switch in the START position.
: 14. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 6                      Page 44 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
Time        Position                                Applicants Action or Behavior Team      Diagnoses the failure with the following indications:
Alarms:
* RM-Q7 - CTMT PART ALERT/FAILURE
* RM-Q8 - CTMT GAS ALERT/FAILURE
* RM-R8 - CTMT GAS RM-RI-160 HIGH Indications:
* CTMT Sump Level increasing
* 1-DA-P-4A running continuously Unit 2 will perform RM ARPs, but will be unable to perform Auto Action verification.
1-AP-16.00 SRO      Direct initiation of 1-AP-16.00, EXCESSIVE RCS LEAKAGE SRO      Notes Prior to Step 1:
* If SI Accumulators are isolated, 1-AP-16.01, Shutdown LOCA, should be used for guidance.
* RCS average temperature has a direct impact on pressurizer level.
RO      [1] MAINTAIN PRZR LEVEL:
* Isolate Letdown
* Control Charging flow RO closes 1-CH-LCV-1460A and 1-CH-LCV-1460B to isolate letdown. The RO will take manual control of 1-CH-FCV-1122 to stabilize pressurizer level.
SRO      The team will hold a short transient brief which may simply be stated as An RCS Leak is in progress, are there any other higher priorities? (words to the effect).
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 6                  Page 45 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
1-AP-16.00 RO      2. CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING
* PRZR Level
* PRZR Pressure
* RCS Subcooling Identifies all parameters are stable under the control of the operator. Team should identify RCS leak rate less than 50 gpm.
Note: Due to ramp previously in progress and Tave trend, the RCS leakrate will be more difficult to calculate.
RO      3. PLACE THE FOLLOWING COMPONENTS IN OFF:
* CTMT sump pumps
* CTMT vacuum pumps RO will place the Containment Sump and Vacuum Pumps in OFF.
SRO      Note Prior to Step 4:
* Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.
RO      *4. CHECK REACTOR TRIP - REQUIRED
* Leak rate - GREATER THAN 50 GPM OR
* Adequate makeup not being provided by blender RO will identify that the leak rate is less than 50 gpm. Note: this can be complicated by temperature trend associated with ramp (may take more time).
4., RNO GO to Step 7.
Evaluator Note: If the Team Identifies RCS leakage > 50 gpm and manually trips the reactor, notify the Simulator Operator to Initiate Event #8, SBLOCA).
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 6                  Page 46 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
SRO      7    CHECK SECONDARY RADIATION - NORMAL OR STABLE IF THERE IS PRE-EXISTING TUBE LEAK
* Air Ejector Rad Monitor
* SG Blowdown Rad Monitors
* Main Steam Line Rad Monitors
* Secondary sample
* N-16 Rad Monitors Unit 2          Report Unit 1 Air Ejector and Blowdown Rad Monitors - Normal BOP            Reports Main Steam, and N-16 Rad Monitor Normal (using PCS)
SRO      8    CHECK RCS LEAK RATE - LESS THAN 10 GPM RO            Reports leak rate > 10 GPM SRO            Step 8 RNO Do the following:
a)      Initiate unit shutdown IAW the appropriate operating procedure.
b)      Control charging flow and seal injection to maintain PRZR level.
c)      Evaluate EPIP applicability
[TS 3.1.C, RCS Operational Leakage. The following specifications are applicable to RCS operational LEAKAGE whenever Tavg (average RCS temperature) exceeds 200&deg;F (200 degrees Fahrenheit).
: 1. RCS operational LEAKAGE shall be limited to:
: a. No pressure boundary LEAKAGE
: 3. If RCS pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within the limit specified in 3.1.C.1.d, the unit shall be brought to HOT SHUTDOWN within 6 hours and COLD SHUTDOWN within the following 30 hours.]
SRO      9  CHECK UNIT CONDITIONS
* PRZR level - STABLE OR INCREASING
* PRZR pressure - STABLE OR INCREASING
* Tave - STABLE RO          Reports PRZR Level, Pressure and RCS Tave Stable.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 6                Page 47 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
SRO      10 CHECK LETDOWN LEAK - INDICATED BOP
* Annunciator 0-VSP-F4, AUX BLDG SUMP HI LVL - LIT RO
* Annunciator 1B-A3, CTMT SUMP HI LVL - LIT Unit 2
* Aux Bldg radiation - HIGH
* CTMT radiation - HIGH RO/BOP
* Local Report of leak RO
* Leak rate decrease following isolation in Step 1 RO
* Abnormal Letdown flow indication prior to isolation in Step 1 RO
* Non-Regenerative HX tube leak - INDICATED BOP
* CC Surge Tank level - INCREASING Unit 2
* CC Activity - INCREASING All indication checked for leak identification are NO SRO      Goes to Step 12 12 CHECK RCS LEAKRATE WITH LETDOWN SECURED - REDUCED 12 RNO Do the following:
a)  Return letdown to service IAW the following, if desired:
* Normal letdown, IAW Attachment 2 OR
* Excess letdown, IAW 1-OP-CH-006, SHIFTING LETDOWN b) GO TO Step 15.
[TS 3.1.C, RCS Operational Leakage. The following specifications are applicable to RCS operational LEAKAGE whenever Tavg (average RCS temperature) exceeds 200&deg;F (200 degrees Fahrenheit).
: 1. RCS operational LEAKAGE shall be limited to:
: a. No pressure boundary LEAKAGE
: 3.      If RCS pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within the limit specified in 3.1.C.1.d, the unit shall be brought to HOT SHUTDOWN within 6 hours and COLD SHUTDOWN within the following 30 hours.]
 
Appendix D                              Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3              Event No.: 6 Page 48 of 103 Event
 
== Description:==
RCS Leak 35 gpm, 1-AP-16.00.
Cue: By Evaluator.
END OF EVENT #6
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 7                  Page 49 of 103 Event
 
== Description:==
Containment particulate and gas RM fail, no Auto Actions.
Cue: Initiated by Event 6.
Time        Position                                Applicants Action or Behavior 1-RM-R8 Actions BOP        NOTE: BOP will be handed Steps 3 and 4 of ARP to verify auto actions of CTMT GAS High alarm.
BOP        3  VERIFY CTMT PURGE SYS - ISOLATED a) CTMT PURGE SUP - CLOSED
* 1-VS-MOV-100A
* 1-VS-MOV-100B
* 1-VS-MOV-100C
* 1-VS-MOV-100D BOP will verify Purge valves closed on the Unit 1 Ventilation Panel by observing RED and GREEN lights extinguished, and GREEN magnet over Shut position indicating light signifying Valve Closed.
b) CTMT PURGE SUP fans - STOPPED
* 1-VS-F-4A
* 1-VS-F-4B BOP will identify Purge Supply Fans secured by observing RED and GREEN indicating lights extinguished.
c) CTMT PURGE BYP valve - CLOSED
* 1-VS-MOV-101 BOP        4  VERIFY CTMT IA SYSTEM ALIGNMENT:
* 1-IA-TV-101A - CLOSED
* 1-IA-TV-101B - CLOSED Identifies 1-IA-TV-101A / B Open by observing position indicating lights on Unit 1 Vertical board RED Light LIT.
Step 4 RNO Manually Align Valves BOP will close the valves by depressing and holding the GREEN indicating light until only the GREEN indicating light is lit.
NOTE: When either 1-IA-TV-101A / B are closed, 1-IA-AOV-103 will open (checked in Step 5 below).
 
Appendix D                                Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 7            Page 50 of 103 Event
 
== Description:==
Containment particulate and gas RM fail, no Auto Actions.
Cue: Initiated by Event 6.
BOP        5  CHECK CTMT IA COMPR OUTSIDE SUCT - OPEN
* 1-IA-AOV-103 BOP will observe 1-IA-AOV-103 OPEN by observing RED position indicating light LIT.
End EVENT #7
 
Appendix D                                  Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                      Page 51 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                                Applicants Action or Behavior Team            Diagnose escalation of RCS Leak by the following:
Alarms:
1C-B8, PRZR LO PRESS 1B-A3, CTMT SUMP HI LVL Indications:
Lowering RCS Pressure PRZR Level decreasing SRO            Direct RO to re-perform Immediate Actions of AP-16.00.
RO      [1] MAINTAIN PRZR LEVEL:
* Isolate Letdown
* Control Charging flow RO checks 1-CH-LCV-1460A and 1-CH-LCV-1460B closed.
The RO will increase flow using 1-CH-FCV-1122 to control PRZR level.
SRO      The team will hold a short transient brief which may simply be stated as An RCS Leak is in progress, are there any other higher priorities? (words to the effect).
1-AP-16.00 SRO      2. VERIFY THE FOLLOWING PARAMETERS - STABLE OR INCREASING
* PRZR Level
* PRZR Pressure
* RCS Subcooling Identifies all parameters are stable under the control of the operator. Team should identify RCS leak rate greater than 50 gpm.
NOTE: SRO may direct RO to manually trip the reactor and safety inject at this point due to degrading plant parameters.
RO      3. PLACE THE FOLLOWING COMPONENTS IN OFF:
* CTMT sump pumps
* CTMT vacuum pumps RO will check the Containment Sump and Vacuum Pumps in OFF.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                      Event No.: 8            Page 52 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
SRO      Note Prior to Step 4:
* Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.
SRO      *4. CHECK REACTOR TRIP - REQUIRED
* Leak rate - GREATER THAN 50 GPM OR
* Adequate makeup not being provided by blender RO will identify that the leak rate is greater than 50 gpm.
SRO      5  ALIGN CHG PUMP SUCTION TO RWST a) Open 1-CH-MOV-1115B and 1-CH-MOV-1115D b) Close 1-CH-MOV-1115C and 1-CH-MOV-1115E RO Evaluator Note: Team may or may not manually align these valves depending on timing.
SRO      6        GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION SRO          Directs RO to trip the reactor, perform E-0, and Manually Safety Inject on Step 4.
 
Appendix D                                Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                    Event No.: 8        Page 53 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                                Applicants Action or Behavior 1-E Reactor Trip or Safety Injection RO      [1] CHECK REACTOR TRIP:
a)  Manually trip reactor Pushes the reactor trip push buttons.
b)  Check the following:
* All Rods On Bottom light - LIT
* Reactor trip and bypass breakers - OPEN
* Neutron flux - DECREASING RO      [2] CHECK TURBINE TRIP:
RO          a)  Manually trip the turbine Pushes the turbine trip push buttons.
b)  Verify all turbine stop valves - CLOSED c)  Isolate reheaters by closing MSR steam supply SOV
* 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)
RO      [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                  Page 54 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
[4] CHECK IF SI INITIATED:
RO            a)  Check if SI is actuated:
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3 SI INITIATED - TRAIN A
* A-F-4 SI INITIATED - TRAIN B RO 4b) Manually initiate SI The RO will manually initiate SI at step 4 by pushing both SI pushbuttons.
After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal, with the exception of the alarms already received. He will also state that containment conditions and the electrical conditions are as you see them (or as reported by the RO/BOP).
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                      Page 55 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
SRO      The team will hold a transition brief. During the brief it will be identified that SI was initiated and the RCS leak has degraded into a LOCA.
SRO/BOP      5. Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained the end of Event 8).
SRO/RO      SRO may direct the RO to perform Attachment 8 of 1-E-0 for Transient AFW Control, or opt to throttle AFW as part of E-0, Step 6.
RO      *6. CHECK RCS AVERAGE TEMPERATURE
* STABLE AT 547&deg;F OR
* TRENDING TO 547&deg;F The team will identify that RCS temperature is decreasing. The team should attribute this to the injection of SI into the RCS and AFW flow to the SGs. It is acceptable for the team to enter the RNO portion of this step and perform the applicable steps (summarized below):
Stop dumping steam Reduce AFW flow to the SGs Close MSTVs if cooldown continues
: 7. CHECK PRZR PORVs AND SPRAY VALVES:
RO            a) PRZR PORVs - CLOSED b) PRZR spray controls
* Demand at Zero (or)
* Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                      Page 56 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
SRO      NOTE: Seal injection flow should be maintained to all RCPs.
RO      *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RCS subcooling may or may not be less than 30 &deg;F at this time.
RNO for the step is to go to step 9.
Critical Task:
CT-1: WOG E-1C: Trip all RCPs so that CETC temperatures do not become superheated when forced circulation in RCS stops; Trip all RCPS within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).
NOTE: If RCP trip Criteria are met prior to reaching this Step, the Continuous Actions Page (CAP) contains these criteria. After this Step is read, this step or the CAP can be used for criteria as long as the Team is performing E-0.
RO      9. CHECK IF SGs ARE NOT FAULTED:
* Check pressures in all SGs a)  STABLE OR INCREASING AND b)  GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 8                  Page 57 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
SRO      10. CHECK IF SG TUBES ARE NOT RUPTURED:
Unit 2
* Condenser air ejector radiation - NORMAL Unit 2
* SG blowdown radiation - NORMAL
* SG MS radiation - NORMAL
* TD AFW pump exhaust radiation - NORMAL
* SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO      RO will use PCS indication for MS and TDAFW Exhaust radiation.
Unit 2 will be used to report Condenser A/E and SG Blowdown radiation trend.
SRO      11 CHECK RCS - INTACT INSIDE CTMT
* CTMT radiation - NORMAL
* CTMT pressure - NORMAL
* CTMT RS sump level - NORMAL RO      Identify CTMT conditions as abnormal SRO      GO TO 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT.
SRO      The team will hold a transition brief. During the brief the SRO will set priorities. The RO and BOP will state the parameters associated with the brief placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified alarms. He will also state that containment conditions and the electrical conditions are as you see them.
The SRO will complete the Brief and continue with E-1.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 8                    Page 58 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                                Applicants Action or Behavior Step 1, 1-E-1 SRO          NOTE: Criteria for FR-Z.1 Entry may be met at any time during performance of 1-E-1. (FR-Z.1 Actions in Section 9).
1  CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO identify 2 CH pumps running.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RO reports actual subcooling.
c) Stop all RCPs RO Stops RCPs if not already tripped.
d) RCS pressure - LESS THAN 1275 PSIG [1475 PSIG]
e) Close CHG pump miniflow recirc valves:
* 1-CH-MOV-1275A
* 1-CH-MOV-1275B
* 1-CH-MOV-1275C RO closes or verifies closed mini-flow recirc valves.
Critical Task:
CT-1: WOG E-1C: Trip all RCPs so that CET temperatures do not become superheated when forced circulation in RCS stops; Trip all RCPs within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).
NOTE: Critical Task copied from E-0 if timing of scenario leads to RCP trip criteria identified on entry to 1-E-1.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                    Page 59 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
1-E-1 SRO      2    CHECK IF SGs ARE NOT FAULTED:
* Check pressures in all SGs:
* STABLE OR INCREASING AND
* GREATER THAN 100 PSIG RO reports SGs are not faulted.
NOTE: SG pressures may be decreasing due to cooldown. RO may report SG pressure as lowering. The SRO will obtain Team concurrence that SG pressure decrease is related to RCS cooldown not a SG fault. The brief is closed.
1-E-1 SRO      *3 CHECK INTACT SG LEVELS:
a) Narrow range level - GREATER THAN 12% [18%]
b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%
1-E-1 SRO      4    CHECK IF SG TUBES ARE NOT RUPTURED:
* Condenser air ejector radiation - NORMAL
* SG blowdown radiation - NORMAL
* SG main steam radiation - NORMAL
* TD AFW pump exhaust radiation - NORMAL
* SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER Unit 2 may be used to report Unit 1 condenser air ejector and blowdown radiation monitor readings.
RO      Report MS and TDAFW RM readings using PCS. Identify SG NR levels NOT increasing in an uncontrolled manner.
1-E-1 CAUTION: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure decreases to less than 2335 psig.
SRO      *5    CHECK PRZR PORVs AND BLOCK VALVES:
a) Power to PRZR PORV block valves - AVAILABLE RO            Report PRZR block valves both available.
b) PRZR PORVs - CLOSED
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                Page 60 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
RO            Report PRZR PORVs closed.
c) PRZR PORV block valves - AT LEAST ONE OPEN RO            Report PRZR block valves both open.
1-E-1 SRO      *6. ___ CHECK IF SI FLOW SHOULD BE REDUCED:
a) RCS subcooling based on CETCs - GREATER THAN 30&deg;F [85&deg;F]
RO          Reports indicated subcooling.
b) Secondary heat sink:
RO
* Total feed flow to INTACT SGs - GREATER THAN 350 GPM [450 GPM]
OR
* Narrow range level in at least one intact SG - GREATER THAN 12% [18%]
RO          Reports SGs have adequate level and AFW flow.
RO          c) RCS pressure - STABLE OR INCREASING RO          Reports RCS pressure decreasing.
SRO          RNO a) OR c) GO TO Step 7.
1-E-1 SRO      *7 CHECK IF HI HI CLS INITIATED:
* CS pump(s) - RUNNING OR
* Any Hi Hi CLS annunciator - LIT NOTE: At this Point CTMT pressure may have increased to the HI and/or Hi-Hi CLS setpoint. The Team should identify that Hi and Hi-Hi CLS do not automatically initiate and take manual action to perform the automatic actions. (FR-Z.1 Actions in Section 9)
When the Team identify that Hi-Hi CLS has not actuated, a transition to FR-Z.1 will be made. When the transition is made Critical Task 2 begins:
CRITICAL TASK:
(Actions for FR-Z.1 will follow 1-E-1, Step 18). Page 77
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                  Page 61 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
1-E-1 SRO      8  CHECK SERVICE WATER AVAILABLE:
a) Check Intake Canal level - BEING MAINTAINED BY CW PUMPS RO          Reports Intake Canal level is 29 feet and Stable.
b) GO TO Step 12 1-E-1 SRO      *12      CHECK IF CS PUMPS CAN BE STOPPED:
a) Check the following:
* RWST level - LESS THAN 3%
AND
* CS Pump amps - FLUCTUATING RO          Reports actual RWST Level.
RNO a) GO TO Step 14. WHEN the following conditions are met, THEN do Steps 12b through 12f.
* RWST level - LESS THAN 3%
AND
* CS Pump amps - FLUCTUATING 1-E-1 SRO      CAUTION: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.
                        *14 CHECK IF LHSI PUMPS SHOULD BE STOPPED:
a) Check RCS pressure:
: 1) Pressure - GREATER THAN 250 PSIG [400 PSIG]
RO          Reports RCS pressure > 250 PSIG [400 PSIG]
: 2) Pressure - STABLE OR INCREASING Reports RCS pressure Lowering.
RNO 2) GO TO Step 15.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                Page 62 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
1-E-1 15 CHECK RCS AND SG PRESSURES:
* Check pressure in all SGs - STABLE OR INCREASING
* Check RCS pressure - STABLE OR DECREASING NOTE: SG pressures may be decreasing due to coodown. RO may report SG pressure as lowering. The SRO will obtain Team concurrence that SG pressure decrease is related to RCS cooldown not a SG fault. The brief is closed 1-E-1 SRO      16 CHECK IF EDGs CAN BE STOPPED:
a) Check AC emergency buses - ENERGIZED BY OFFSITE POWER RO          Reports that H Emergency bus energized by off-site power, and J emergency powered from #3 EDG.
b) Reset both trains of SI if necessary RO RO presses SI reset pushbuttons.
c) Check CTMT pressure - LESS THAN 14 PSIA RO Reports actual containment pressure (pressure will be greater than 14 psia).
RNO c) GO TO Step 17. WHEN pressure less than 14 psia, THEN do Steps 16d and 16e.
1-E-1 SRO      17 CHECK INSTRUMENT AIR AVAILABLE:
a) Check annunciator B-E NOT LIT RO            Reports B-E-6 NOT LIT.
b) Check at least one CTMT IA compressor - RUNNING
* 1-IA-C-4A or 1-IA-C-4B RO            Reports 1-IA-C-4A running.
c) Check 1-IA-TV-100 - OPEN RO                Reports 1-IA-TV-100 position.
NOTE: When BOP performs Attachment 4 of E-0, 1-IA-TV-100 may be closed; SRO/BOP may confer over closure of the valve since Hi-Hi CLS actions are being
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 63 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
manually performed.
1-E-1 SRO      18      INITIATE EVALUATION OF PLANT STATUS:
END OF EVENT 8 END OF SCENARIO
 
Appendix D                                Required Operator Actions                Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8      Page 64 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                              Applicants Action or Behavior Attachment 1 of E-0 1  CHECK FW ISOLATION:
* Feed pump discharge MOVs - CLOSED
* 1-FW-MOV-150A
* 1-FW-MOV-150B
* MFW pumps - TRIPPED
* Feed REG valves - CLOSED
* SG FW bypass flow valves - DEMAND AT ZERO
* SG blowdown TVs - CLOSED Attachment 1 of E-0 2  CHECK CTMT ISOLATION PHASE I:
* Phase I TVs - CLOSED
* 1-CH-MOV-1381 - CLOSED
* 1-SV-TV-102A - CLOSED
* PAM isolation valves - CLOSED
* 1-DA-TV-103A
* 1-DA-TV-103B Attachment 1 of E-0 3  CHECK AFW PUMPS RUNNING:
a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY Attachment 1 of E-0 BOP      4. CHECK SI PUMPS RUNNING:
* CHG pumps - RUNNING
* LHSI pumps - RUNNING
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 8                Page 65 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Attachment 1 of E-0 BOP
: 5. CHECK CHG PUMP AUXILIARIES:
* CHG pump CC pump - RUNNING
* CHG pump SW pump - RUNNING Attachment 1 of E-0 BOP      6. CHECK INTAKE CANAL:
* Level - GREATER THAN 24 FT
* Level - BEING MAINTAINED BY CIRC WATER PUMPS Attachment 1 of E-0
: 7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:
a)  Check if ANY of the following annunciators - HAVE BEEN LIT
* E-F-10 (High Steam Flow SI)
BOP
* B-C-4 (Hi Hi CLS Train A)
* B-C-5 (Hi Hi CLS Train B)
Identifies annunciators not lit and goes to step 8.
Attachment 1 of E-0 BOP
                        *8. CHECK IF CS REQUIRED:
a)  CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                Page 66 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Attachment 1 of E-0 BOP      *10. BLOCK LOW PRZR PRESS SI SIGNAL:
a)    Check PRZR pressure - LESS THAN 2000 psig b)  Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c)  Check Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.
Attachment 1 of E-0 BOP      *11. BLOCK LOW TAVE SI SIGNAL:
Step may not be performed at this time (if Tave is greater than 543&deg;F).
a)  Check RCS Tave - LESS THAN 543&deg;F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c)  Check Permissive Status light F LIT Attachment 1 of E-0 NOTE:
* CHG pumps should be run in the following order of priority: C, B, A.
* Subsequent SI signals may be reset by re-performing Step 12.
BOP
: 12. CHECK SI FLOW:
a)  HHSI to cold legs - FLOW INDICATED
* 1-SI-FI-1961 (NQ)
* 1-SI-FI-1962 (NQ)
* 1-SI-FI-1963 (NQ)
* 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c)  Reset SI.
d) Stop one CHG pump and out in AUTO
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                    Event No.: 8                    Page 67 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Step 12, Attachment 1 of E-0, Continued e)  RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:
: 1) Verify reset or reset SI.
: 2) Stop one LHSI pump and put in AUTO.
: 3) GO TO Step 13.
Attachment 1 of E-0 BOP
: 13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]
Attachment 1 of E-0 BOP
: 14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.
Attachment 1 of E-0 BOP
: 15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next Page of this guide)
Depending on timing, this attachment may have already been completed.
Attachment 1 of E-0 BOP
: 16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Unit 2 Operator will state that Unit 2 is at 100% power (if asked)
Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 8                    Page 68 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Time        Position                              Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 SRO      NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.
ATTACHMENT 2 of 1-E-0 RO/BOP      1. Check opened or open CHG pump suction from RWST MOVs.
* 1-CH-MOV-1115B
* 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 RO/BOP      2. Check closed or close CHG pump suction from VCT MOVs.
* 1-CH-MOV-1115C
* 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 RO/BOP      3. Check running or start at least two CHG pumps. (listed in preferred order)
* 1-CH-P-1C
* 1-CH-P-1B
* 1-CH-P-1A ATTACHMENT 2 of 1-E-0 RO/BOP      4. Check opened or open HHSI to cold legs MOVs.
* 1-SI-MOV-1867C
* 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 RO/BOP      5. Check closed or close CHG line isolation MOVs.
* 1-CH-MOV-1289A
* 1-CH-MOV-1289B
 
Appendix D                              Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                  Event No.: 8      Page 69 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
ATTACHMENT 2 of 1-E-0 RO/BOP      6. Check closed or close Letdown orifice isolation valves.
* 1-CH-HCV-1200A
* 1-CH-HCV-1200B
* 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 RO/BOP      7. Check opened or open LHSI suction from RWST MOVs.
* 1-SI-MOV-1862A
* 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 RO/BOP      8. Check opened or open LHSI to cold legs MOVs.
* 1-SI-MOV-1864A
* 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 RO/BOP      9. Check running or start at least one LHSI pump.
* 1-SI-P-1A
* 1-SI-P-1B ATTACHMENT 2 of 1-E-0 RO/BOP      10. Check High Head SI flow to cold legs indicated.
* 1-SI-FI-1961
* 1-SI-FI-1962
* 1-SI-FI-1963
* 1-SI-FI-1943 or 1-SI-FI-1943A
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 8                  Page 70 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
ATTACHMENT 2 of 1-E-0 RO/BOP      11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.
* Alternate SI to Cold legs
* Hot leg injection
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 71 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 72 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 73 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
 
Appendix D                                Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                Event No.: 8 Page 74 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Unit 2 will prompt BOP: Chilled Water has been aligned IAW CAUTION prior to Step 1.
 
Appendix D                              Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                    Event No.: 8                    Page 75 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
Unit 2 will prompt BOP: MCR Boundary DP is the same as DP indicated on Unit 2 Ventilation Panel.
Unit 2 will prompt BOP: Unit 2 remains operating at 100%
power.
Unit 2 will assume responsibility for the Attachment action from this point.
 
Appendix D                              Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 3                Event No.: 8 Page 76 of 103 Event
 
== Description:==
SBLOCA, 1-AP-16.00, 1-E-0.
Cue: By Evaluator or if the Team manually trips the reactor during Event #6.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 9                    Page 77 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
Time        Position                                  Applicants Action or Behavior 1-FR-Z.1 Actions CAUTION: If 1-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, is in effect, containment spray systems should be operated as directed by 1-ECA-1.1, instead of Step 1 below.
SRO        1    CHECK IF CS REQUIRED:
a) Check CTMT pressure - HAS INCREASED TO GREATER THAN 23 PSIA b) Check CS pumps - RUNNING                b) IF RWST level greater than 3%,
THEN start CS pumps. IF any CS pump can NOT be started, THEN monitor OSRS pumps for cavitation.
RO            Starts 1-CS-P-1A / 1B                      IF cavitation is indicated, THEN put affected OSRS pump in PTL c) Check CS system valves - OPEN            c) Manually align CS valves.
* 1-CS-MOV-100A
* 1-CS-MOV-100B
* 1-CS-MOV-101A and B
* 1-CS-MOV-101C and D
* 1-CS-MOV-102A and B RO            Opens Valves Listed Above (BOLDED).
d) Stop all RCPs RO            Stops RCPS and acknowledges Loop Low Flow Alarms.
Critical Task:
CT-2: WOG E-0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (red-path) challenge develops to the CSF. Establish CS flow from at least one CS pump before containment pressure exceeds 60 psia AND at least one RS train before RMT.
Evaluator Note: To meet the CT, One Train of CTMT Depressurization must be aligned. One CS pump with either of its associated discharge MOVs open.
1-CS-P-1A Running, with 1-CS-MOV-101A or 1-CS-MOV-101B OPEN. OR 1-CS-P-1B Running, with 1-CS-MOV-101C or 1-CS-MOV-101D OPEN.
CRITICAL TASK:
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 9                      Page 78 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
1-FR-Z.1 Actions SRO        2  CHECK SW FLOW TO RS HXs -                      Align valves as necessary.
GREATER THAN 4750 GPM RO            Checks flow > 4750 GPM following the Opening of the SW Valves Listed below.
a) Check the following valves - OPEN
* 1-SW-MOV-103A, B, C, and D
* 1-SW-MOV-104A, B, C, and D
* 1-SW-MOV-105A, B, C, and D RO            Open the SW MOVs listed above.
1-FR-Z.1 Actions SRO        3  CHECK RS SYSTEMS:
a) Check RWST level -LESS THAN 60%                  a) Do the following:
: 1) Monitor RWST level.
: 2) WHEN RWST level is less than 60%, THEN perform Steps 3b and 3c.
1-FR-Z.1 Actions SRO        4  CHECK INTAKE CANAL LEVEL - GREATER THAN 24 FT RO            Reports Intake Canal Level 29 feet and Stable.
1-FR-Z.1 Actions SRO        5  CHECK CTMT ISOLATION VALVES -
CLOSED IAW ATTACHMENT 1                              IF flow path NOT necessary, THEN close valves BOP            Aligns Valves as necessary.
NOTE: BOP and SRO may confer on leaving 1-IA-TV-100 open.
NOTE: FR-Z.1 Actions located at the end of this section.
1-FR-Z.1 Actions SRO        6. ___ CHECK MSTVs - CLOSED                              Manually close MSTVs.
RO/BOP            Closes MSTVs if not already performed.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                      Event No.: 9                  Page 79 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
1-FR-Z.1 Actions CAUTION:
* At least one SG must be maintained available for RCS cooldown.
* If all SGs are faulted, at least 60 gpm [100 gpm] feed flow should be maintained to each SG.
SRO        7. ___ CHECK IF FEED FLOW SHOULD BE ISOLATED TO ANY SG(s):
a) Check pressures in all SGs:                    a) GO TO Step 8
* ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR
* ANY SG COMPLETELY DEPRESSURIZED RO/BOP            Reports SGs NOT Faulted.
1-FR-Z.1 Actions SRO        8  CHECK SERVICE WATER AVAILABLE:
a) Check Intake Canal level - BEING MAINTAINED BY CIRC WATER PUMPS RO/BOP            Reports Intake Canal Level 29 feet and Stable. Being maintained by CW pumps.
b) RETURN TO procedure and step in effect SRO            Returns to 1-E-1, Step In Effect.
 
Appendix D                                Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                Event No.: 9 Page 80 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
Valves Operated for Hi CLS Failure.
Valves Operated for Hi Hi CLS Failure.
Valve BOP/SRO may confer and leave open.
 
Appendix D                                Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                  Event No.: 9 Page 81 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
Valves Operated for Hi CLS Failure.
Valves Operated for Hi Hi CLS Failure.
Valve BOP/SRO may confer and leave open.
 
Appendix D                                Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 3                Event No.: 9 Page 82 of 103 Event
 
== Description:==
Hi and Hi-Hi CLS Fail, FR-Z.1.
Cue: By Event 8.
Section Not Performed for this Scenario.
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 83 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 84 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 85 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 3                                  Page 86 of 103 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:
Recall IC -263 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.
Open the monitor window and add the following points to it:
* asp_ao_off
* set sphhcntprs_k1 = 60
* iadryer_reset
    *    ??
Enter the following MALFUNCTIONS:
Trigger Malfunction            Delay    Ramp        Trigger  Value    Final      Type (Auto or Manual)
RC0801 TAVE TAYLOR MATH                10        0          1      0          -1          MAN UNIT FAILURE HI/LOW MS0801 SG A STM FLOW                    10        30          3      0          -1          MAN TRNSMTR MS-FT-475 FAILURE EL4902 BKR 15J8 SPURIOUS TRIP          10        0          5    FALSE      TRUE          MAN RC04 RCS LEAK NONISOLABLE              10        0          9      0        3.5          MAN (0 - 1200 GPM)
RM0202 PROCESS RAD                      10        0          9      0        0.1          MAN MONITOR RI-RMS-159 FAILURE RM0201 PROCESS RAD                      10        0          9      0        0.1          MAN MONITOR RI-RMS-160 FAILURE CA03 Disable IA-TV-101A Auto            0        0          9    FALSE      TRUE          MAN Closure CA06 Disable IA-TV-101B Auto            0        0          9    FALSE      TRUE          MAN Closure RC0101 RCS COLD LEG A PIPE              10      600          11      0          .6          MAN RUPTURE RS0901 TRN A HI CLS FAILS TO            0        0          30    FALSE      TRUE        ACTIVE ACTIVATE RS0902 TRN B HI CLS FAILS TO            0        0          30    FALSE      TRUE        ACTIVE ACTIVATE
 
Appendix D                              Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3                        Page 87 of 103 SIMULATOR OPERATORS GUIDE Enter the following Remote Functions:
Override                            Set Condition                      Trigger AC_SMS_MODE                                  OFF                              30 Enter the following Override:
Override                            Set Condition                      Trigger TEST_IRL_IIL EHC                          ON, 10 Sec TD                          7 TEST 1RL 1IL CLS_ACT_TRA                                  OFF                              30 CLS_ACT_TRB                                  OFF                              30 TRIGGER                  TYPE                                  DESCRIPTION 1                    MAN            TAVE TAYLOR MATH UNIT FAILURE LOW 3                    MAN            SG A STM FLOW TRNSMTR MS-FT-475 FAILURE 5                    MAN            BKR 15J8 SPURIOUS TRIP 7                    MAN            IRL/ILL TEST PUSHBUTTON FAILURE RCS LEAK NONISOLABLE (35 GPM) with AUTO ACTIONS RM-MAN 9                                  159/160 FAILURE 11                    MAN            LBLOCA WITH HI and HI HI CLS FAILED
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 3                                Page 88 of 103 SIMULATOR OPERATORS GUIDE Verify the following control room setup:
Place the simulator in RUN and verify normal 100% power operation indications.
Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:
Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).
Verify Ovation System operating.
Reset ICCMs.
Verify Component Switch Flags.
Verify Brass Caps properly placed.
Verify SG PORVs set for 1035 psig.
Verify Rod Control Group Step Counters indicate properly.
Verify Ovation CRT display.
Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)
Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:
AP-53.00            AP-16.00            AP-23.00                    1-OPT-RX-007 (3)
E-0                                    E-1 (2)
OP-CH-007                                MOL OP-RX-010 OP-ZZ-002 Verify Reactivity Placard is current.
Verify ALL PINK MAGNETS are accounted for.
 
Appendix D                            Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3                                Page 89 of 103 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.
Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.
If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.
In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.
Assign operating positions.
Ask for and answer questions.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 3                                Page 90 of 103 SIMULATOR OPERATORS GUIDE Conduct shift turnover:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
Shift orders are to maintain 100% power on Unit #1.
The last shift performed two 35 gallon alt dilutions followed by a manual makeup for training.
A BAST at 8.0 W/%.
When the team has accepted the shift, proceed to the Session Conduct Section.
 
Appendix D                                  Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 3                              Page 91 of 103 SIMULATOR OPERATORS GUIDE Session Conduct:
* Ensure conditions in Simulator Set-up are established.
* Ensure Trigger 30 is active prior to team entering the simulator.
* Verify Exam Security has been established and ASP_AO_OFF = True.
EVENT 1          Deleted.
EVENT 2          Failure Median Tave Low, 0-AP-53.00.
When cued by examiner, implement Trigger #1.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of Median Tave. The individual(s) contacted will also acknowledge entry into AP-53.00.
* If contacted, will take responsibility for writing the CR.
* If asked, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
STA:
* If contacted, will acknowledge the failure of Median Tave.
* If asked, the STA will report that upon review of CEP 99-0029, Median Tave is NOT listed in CEP 99-0029.
* If asked, the STA will review VPAP-2802 and TRM Section 3.3 and report that the results of the review have been discussed with Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
 
Appendix D                              Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3                            Page 92 of 103 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:
* If contacted, will acknowledge instrumentation failure and commence investigation of the failure.
Unit 2 Operator:
* If contacted, will acknowledge the failure.
Role play as other individuals as needed.
 
Appendix D                                  Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 3                              Page 93 of 103 SIMULATOR OPERATORS GUIDE EVENT 3          Failure of Steam Flow Channel Low, A SG. 0-AP-53.00.
When cued by examiner, implement Trigger #3.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of 1-MS-FT-1474. The individual(s) contacted will also acknowledge any TS LCOs.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into 72 hour clock to place the channel in trip.
* If contacted, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
STA:
* If contacted, will acknowledge the failure of 1-MS-FT-1474. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
* If contacted, will take responsibility for writing the CR.
* If asked, 1-MS-FT-1474 is a RG 1.97 variable
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
* When directed, STA review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
Field Operators:
* Will perform actions as directed.
I&C:
* If notified by MCR to place the channel in trip, state that you will review the procedure and notify the Shift Manager when ready to brief.
 
Appendix D                            Required Operator Actions  Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3    Page 94 of 103 SIMULATOR OPERATORS GUIDE Maintenance/ Work Week Coordinator:
* If contacted, will notify I&C of the failure.
Unit 2:
* If contacted, will acknowledge the channel failure.
Role-play as other individuals as needed.
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 3                                Page 95 of 103 SIMULATOR OPERATORS GUIDE EVENT 4          1J 4160V emergency bus off-site power supply breaker trips. 1-AP-10.07.
When the Evaluator is ready, Implement Trigger #5 for the failure. Evaluator may go to next event (event #5) when 1-CC-P-1B is placed in Auto.
Operations Supervisor/Management:
* If contacted, will acknowledge the loss of 1J 4160 V bus, and the start and load of #3 EDG.
* If contacted, will inform OM on Call and Electrical Foreman.
STA:
* If contacted, will acknowledge the loss of 1J 4160V bus and the start and load of #3 EDG.
* After directed, the STA will report that VPAP-2802 has been reviewed and discussed with the Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
Maintenance/ Work Week Coordinator:
* If contacted, will acknowledge the failure and commence investigations.
Field Operators:
* If contacted, will check status of 15J8 breaker and find an individual in the area that reports he bumped the cabinet while cleaning and heard a loud noise. 1-CC-P-1B must have been returned to Auto before this report is made.
* If asked, the condensate polishing building operator will report current polishing building DP (read from simulator screen).
* When Directed, to check status of IA compressors (1B-E6 ARP), CA6 1-IA-C-1 IA Local Panel, the local panel will have an Alarm light lit. Depress U1_IAC1_SET button to clear alarm.
 
Appendix D                            Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 3                              Page 96 of 103 SIMULATOR OPERATORS GUIDE
* When Directed, to check status of IA Dryer (1B-E5 ARP), the dryer will be bypassed, use IADRYER_RESET on monitor to reset the dryer.
* When contacted, to close 15J9 breaker, EL11, Unit 1 - 4160 Breakers, 15J9, scroll to bottom of pop-up box, double click on SW_15J9_RF, select close, INSERT.
* When contacted, RM-159/160 Particulate and Gas RM skid is normal.
* When contacted, concerning monitoring of #3 EDG parameters, follow instructions.
Unit 2:
* If contacted, acknowledge start and load of #3 EDG on Unit 1.
Role-play as other individuals as needed.
 
Appendix D                            Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                              Page 97 of 103 SIMULATOR OPERATORS GUIDE EVENT 5        Test Button failure, 1RL/1IL close, 0-AP-23.00 ramp to 71%.
When 1-CC-P-1B in Auto and examiner ready, implement Trigger #7.
Operations Supervisor/Management:
* If contacted, will acknowledge closure of 1RL/1IL. Also acknowledge the entry into AP-53.00/AP-38.00 for the failure.
* If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC (Lead Evaluator), the Shift Manager will direct a 1%/minute ramp rate.
* If contacted, will take responsibility for writing the CR.
Unit 2 Operator:
* If notified, acknowledge the failure and impending ramp of Unit 1.
STA:
* If contacted, will acknowledge the closure of 1RL/1IL, and entry into AP-53.00/AP-38.00.
* If contacted, will take responsibility for writing the WR and CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
* The STA will acknowledge the Reactivity Plan reported by the RO.
* If contacted, STA review of VPAP-2802 complete and reviewed with Shift Manager.
 
Appendix D                          Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                Scenario No.: 3                            Page 98 of 103 SIMULATOR OPERATORS GUIDE Field Operators:
* If contacted, as the Turbine Building Operator to walkdown the Turbine during the ramp, acknowledge the direction.
* If contacted, as the polishing building operator, acknowledge the direction to monitor polisher DP.
* If contacted, as Turbine Building operator, the 1RL/1IL valves are closed, no external abnormalities noted.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 99 of 103 SIMULATOR OPERATORS GUIDE EVENTS 6      RCS Leak 35 gpm. 1-AP-16.00.
Note: It would be preferable to wait until power is <80% to implement this failure to allow for ramp stabilization prior to creating RCS leak; this will allow the team to assess leakrate with more precision.
When the Evaluator is ready, implement Trigger # 9. If the Team manually trips the reactor, the Evaluator may prompt initiation of Event #8.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will acknowledge entry into AP-16.00.
* If contacted, will acknowledge Unit shutdown imminent due to excessive RCS leakage.
* If contacted, will acknowledge EPIPs require evaluation.
STA:
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
* When Notified, acknowledge that EPIPs require evaluation.
* If contacted, will enter the control room and and prepare for the transient brief (items are reported as you see them or previously reported).
Unit Two:
* When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 100 of 103 SIMULATOR OPERATORS GUIDE
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO/BOP.
* If asked, blowdown and air ejector RM readings are [as indicated at the time].
* When required, assist Unit by acknowledging Fire Panel Alarms.
* If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
Field Operators:
* If contacted, field operators will perform valve manipulations as required:
Health Physics:
* If contacted, will acknowledge the leak of RCS coolant into containment.
Maintenance/Work Week Coordinator:
* If contacted, will acknowledge the failure.
Maintenance/Work Week Coordinator:
* If contacted, will acknowledge the failure.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 101 of 103 SIMULATOR OPERATORS GUIDE EVENT 7        Particulate and gas RM fail, No Auto Actions.
Implemented with Trigger #9.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of the automatic actions on RM-160 High alarm.
* If contacted, will take responsibility for writing the WR and CR.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
* If directed, perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
Field Operators:
* If directed, field operators will perform local manipulations as required.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 102 of 103 SIMULATOR OPERATORS GUIDE EVENT 8        SBLOCA, 1-AP-16.00, 1-E-0.
When the Evaluator is ready, actuate Trigger #11. Prompt the Evaluator when RCS Subcooling reaches 35 &deg;F and decreasing so that start time for CT-1 is monitored.
Operations Supervisor/Management:
* If contacted, will acknowledge the reactor trip and Entry into E-0.
* If contacted, will take responsibility for writing the WR and CR.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
STA
* Enter MCR when called and standby to monitor CSFSTs.
* When entry conditions for Containment Orange Path identified, circle the appropriate Path and show to the SRO.
Field Operators:
* If directed, field operators will perform local manipulations as required.
Role play as other individuals as needed.
 
Appendix D                          Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 3                            Page 103 of 103 SIMULATOR OPERATORS GUIDE EVENT 9        Hi and HI-CLS Failure, FR-Z.1.
Implemented by ACTIVE Triggers.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of Hi and Hi-Hi CLS.
STA:
* When the Team identifies containment pressure has exceeded 23 psia, use CSFSTs to mark flowpath to FR-Z.1, ORANGE path and present to SRO.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
* When BOP performs Attachment 3 of E-0, MCR Boundary DP readings are the same as the indication on Unit 2 Ventilation Panel. Unit 2 has initiated 0-AP-50.00. Unit 2 remains at 100% power. Assume responsibility for E-0, Attachment 3, monitoring of SFP.
* If asked, Unit 2 RWST cross-ties are open.
Field Operators:
* If directed, field operators will perform local manipulations as required.
Role play as other individuals as needed.
 
Appendix D                                              Scenario Outline                                        Form ES-D-1 NRC EXAM - SCENARIO #4 Facility: Surry Power Station                      Scenario No.: 4                            Op-Test No.: 2014-001 Examiners: ____________________________ Operators:                                  _____________________________
Initial Conditions: Time in Core Life - Middle of Life; Core Cycle - Cycle 26 Unit 1 and 2 operating at 100%. All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* 1-CC-P-1D tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4)
RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
* Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
* A BAST at 8.0 W/%.
* PSA is Green.
Event            Malf.        Event                                                Event No.            No.          Type*                                              Description 1                  N/A                          Deleted 2                RC4802,            I - RO        1-RC-PT-1445 fails high, PRZR Pressure channel fail high. AP-31.00,
                  +1 Deg          TS - SRO        Increasing or Decreasing RCS Pressure.
3                MS1305,          I - BOP        Steam Pressure Channel III, B SG fails High. 0-AP-53.00, Loss of Vital
                  +1 Deg          TS-SRO          Instrumentation/Controls.
CH2101, 4                +1 Deg            I - RO      Failure of VCT Level Channel LT-115 High.
CC0302 5                CC0802          C - BOP        Overcurrent on B CC pump with breaker mechanically stuck closed SW_15J9_        TS - SRO        causing the trip of Stub Bus Supply breaker.
RF, TRIP C - RO 6                                TS - SRO RD1236          R - RO /      Dropped Rod Control Bank C, Group 1; AP-1.00, Rod Control SRO        Malfunction, AP-23.00, Rapid Load Reduction.
N - BOP 7                RC MOV                          RC Loop C Tc MOV disc falls into flow stream, Valid First-Out 595, 30%          M - All      received, No Auto or Manual Reactor Trip. 1-FR-S.1, Response to Nuclear Generation/ATWS.
RD17 SI1502, 8                40% Deg                          LOCA outside of Containment in Unit 1 Valve Pit Area.
SI1603            M - All SI1606 SI2402 9                SI2405                          SI Relay SI2A fails to Actuate, SI Relay SI5A Fails to Actuate; 1-SI-P-1A CC1801                          not auto start; MOV-1115D, CH-MOV-115C, CH-MOV1289A, CV-TV-C - BOP 150A, and CH-TV-1204A fail to re-position on SI. 1-CC-P-1A Auto Start Disabled.
*          (N)ormal,    (R)eactivity,      (I)nstrument,    (C)omponent,      (M)ajor
 
Appendix D                              Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #4 Event #1:  Deleted.
Event #2:  1-RC-PT-1445 Fails High. (I - RO, TS-SRO)
The RO will respond to the alarms and indications received by performing the Immediate Actions of AP-53.00, Loss of Vital Instrumentations/controls; or 1-AP-31.00, Increasing or Decreasing RCS pressure. RCS pressure is expected to lower to less than 2205 psig for a short time period resulting in a Tech Spec consultation.
Verifiable Actions:
: 1) RO will place control switch for 1-RC-PCV-1456 in close.
: 2) BOP may place Rod Control in manual to stop rod motion caused by the reactivity inserted by the pressure coefficient.
: 3) RO will close 1-RC-MOV-1535 due to Technical Specification requirements.
Technical Specifications:
: 1) The SRO will consult Tech Specs, TS Section 3.1.A.6, and determine that 1-RC-PCV-1456 is Inoperable but capable of being manually cycled, and enter a one hour clock to close the block valve for the PORV. The block valve will remain energized.
: 2) Further consultation will find Tech Spec 3.12.F.1 to restore RCS pressure >2205 psig in 2 hours or reduce Thermal Power to less than 5% in the next 6 hours. The Core Operating Limits Report (COLR, DRP-21) provides the reference for 2205 psig RCS pressure.
Technical Requirements Manual/R.G. 1.97
: 1) No TRM or R.G. 1.97 requirements apply.
Event #3:  Steam Pressure Channel III Fails High on B steam line causing B steam flow increase and B FRV to open. (I - BOP, TS - SRO)
The BOP will respond to the alarms and indication received by placing the B FRV in manual and restoring B SG NR level to program IAW 1-AP-53.00, Loss of Vital Instrumentation/Controls. The Abnormal Procedure will require the Controlling Steam Flow channel to be swapped to Channel IV so that the B FRV can be restored to Auto.
Verifiable Actions:
: 1) BOP will place the B FRV in manual and restore B SG NR level to program.
: 2) RO will shift controlling channel.
Technical Specifications The SRO should consult Tech Specs and determine the following:
 
Appendix D                            Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #4
: 1) Tech Specs Section 3.7, Table 3.7-1, Item 17, Low steam generator water level with steam/feedwater flow mismatch, Operator Action 6. With the number of Operable channels on less than the total number of channels, Power Operation may proceed provided the channel is placed in the trip condition in 72 hours, the channel may be bypassed for 12 hours for surveillance; if these requirements are not met, the Unit must be placed in Hot Shutdown within 6 hours.
: 2) Tech Spec 3.7, Table 3.7-2, Item 1.c., High differential pressure between any steam line and the steam header, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours; the channels may be bypassed for 12 hours for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours and reduce RCS temperature and pressure to less than 350&deg;F/450 psig in the following 12 hours.
: 3) Tech Spec 3.7, Table 3.7-2, Item 1.e.1 and 1.e.3, High Steam line flow in 2/3 steam lines coincident with low Tavg or low line pressure, Operator Action
: 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours; the channels may be bypassed for 12 hours for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours and reduce RCS temperature and pressure to less than 350&deg;F/450 psig in the following 12 hours.
: 4) Tech Spec Table 3.7-3, item 2a, Steam Line Isolation. Refers to Tech Spec Table 3.7-2, Item 1.e. See Above.
: 5) Tech Spec Table 3.7-6, Item 16, SG Pressure, 2 per SG are required. This condition is met.
Technical Requirements Manual/R.G. 1.97:
: 1) The TRM Section 3.3 2, Appendix R Instrumentation, Table 3.3.2-1, Steam Generator Pressure 1-MS-PI-1485 is a Primary indicator. One of the three listed transmitters must be Functional to meet the requirement. Two of the three are Functional. No TRM requirements for this failure. (The TRM review is normally performed by the STA in consultation with the Shift Manager; if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).
RG-1.97
: 1) RG-1.97 variables, Steam Generator pressure is an A-02 variable, 2 channels per SG are required, table refers to Tech Spec Table 3.7-6. (The RG 1.97 review is normally performed by the STA in consultation with the Shift Manager; if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).
Event #4:  VCT Level Transmitter LT-115 Fails High. (I - RO)
The RO is expected to diagnose this failure based upon alarms and indications received.
The RO will perform the Immediate Action Steps of 0-AP-53.00, Loss of Vital Instrumentation/Controls and place the VCT divert valve, 1-CH-LCV-1115A, in the NORM position to stop divert of Letdown flow to the PDTT. The Team will continue through the abnormal procedure.
 
Appendix D                            Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #4 Verifiable Actions:
: 1) RO will place the control switch for 1-CH-LT-1115A in the NORM position to stop letdown diversion to the PDTT.
Technical Specifications:
: 1) There are no Tech Spec or TRM actions required for this failure.
Technical Requirements Manual:
: 1) None for this failure.
Reg. Guide 1.97:
: 1) RG 1.97 requirements: 1-CH-LI-1115 is a D-29 variable, Category 2. 1 channel is required. Required Action C from Attachment 2; restore the required channel to functional status and use alternate indication to accomplish this function, if possible (VCT level channel 1-CH-LI-1112 functional and meets this requirement). Completion Time 60 days if no alternate indication available OR on or before the next planned outage if an alternate indication is available. (The RG 1.97 review is normally performed by the STA in consultation with the Shift Manager, if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).
Event #5:  Overcurrent of the B CC pump with the Breaker Stuck closed, resulting in the trip of the stub bus breaker 15J9 on overcurrent. (C - BOP, TS-SRO)
The BOP is expected to diagnose this failure based on alarms and indications received.
The BOP will place the B CC pump in PTL.
Verifiable Actions:
: 1) BOP will place the control switch for 1-CC-P-1B in PTL.
: 2) BOP will start 1-CC-P-1A.
Technical Specifications:
: 1) The SRO will consult Tech Specs 3.13.A.2 and 3.13.B, and determine that the minimum Operable CC pumps requirement is not met. For 2 Unit operation 3 CC pumps must be operable, and TS 3.13.B cannot be met, the SRO should identify a TS 3.01 6 hour clock to HSD, and a 30 hour clock to CSD.
: 2) Consult Tech Spec 3.5.A.1 and determine the Minimum Operable RHR pumps requirement is not met. This requires, IAW TS 3.5.B, that a 14 day clock be entered to restore A RHR pump to an Operable condition.
 
Appendix D                              Scenario Outline                                Form ES-D-1 NRC EXAM - SCENARIO #4 Technical Requirements Manual
: 1) IAW IAW TRM 3.7.9.A additional 72 hour and 14 day clocks are in effect to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status. Normally an STA function in consult with Shift Manager, recommend use of follow up question.
Event #6:  Dropped Control Rod, M-4, Control Bank C, Group 1. (C - RO, R - RO, TS - SRO, R
          - SRO, N - BOP)
The RO is expected to diagnose this failure based on alarms and indications received and place Rod Control in manual to stop outward rod motion IAW 0-AP-1.00, Rod Control Malfunction.
The Team will continue in AP-1.00 to the point where 0-AP-23.00, Rapid Load Reduction will be used to reduce reactor power to 70-74% to meet the TS requirement to be <75%
of Rated Power within 1 hour.
Verifiable Actions:
: 1) RO will place rod control in manual.
: 2) BOP will perform actions of Annunciator Response Procedure 1G-F8, Bank D WITHDRAWAL to realign group step counters.
Technical Specifications:
: 1) The SRO will determine that the dropped control rod is Inoperable since it is misaligned from its Bank > +/- 12 steps. IAW Tech Spec 3.12.C.3, power must be reduced to < 75% Rated Power within 1 hour, and the High Neutron Flux trip setpoint shall be reduced to  85% of Rated Power within the next 4 hours.
: 2) Shutdown margin must be determined to be satisfactory within 1 hour and every 12 hours thereafter.
: 3) Hot channel factors are shown to be within limits of TS 3.12.B.1 in 72 hours and it shall be demonstrated that the value of Fxy(Z) used in the Constant Axial Offset Analysis is still valid.
: 4) Reevaluation of each accident analysis of Table 3.12-1 is performed within 5 days, to confirm the previous analysis of these accidents remain valid.
: 5) If, except for operation at THERMAL POWER < 50% or for physics and control rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2%, then:
: a. Within 2 hours, either the hot channel factors shall be determined and the power level adjusted to meet the requirement of Specification 3.12.B.1, or
 
Appendix D                              Scenario Outline                                  Form ES-D-1 NRC EXAM - SCENARIO #4
: b. The power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours.
: 6) If the QUADRANT POWER TILT exceeds 10%, the power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours.
Event #7:  Tcold Loop stop disc detaches and drops into the flowstream, Valid First-Out indication, No automatic or manual reactor trip, FR-S.1. (M - ALL)
This Event begins the Major Accident sequence. The RO will identify a First-Out alarm is received, the alarm is valid (Low Flow Condition in C RCS Loop), the reactor has not automatically tripped, attempt a manual reactor trip, and then perform the Immediate Action of 1-FR-S.1, Response to Nuclear Power Generation/ATWS.
The reactor trip breakers will be opened locally two (2) minutes after the Team directs an Operator to perform this action (based upon time critical operator action time requirement for locally tripping the reactor trip breakers).
The Team will complete 1-FR-S.1, transition to 1-E-0, Reactor Trip or Safety Injection to perform the Immediate Operator Actions, Transition to 1-ES-0.1, Reactor Trip Response, and perform a brief.
Verifiable Actions:
: 1)    RO will attempt to trip the reactor using both reactor trip pushbuttons.
: 2)    RO will check or place rods control in automatic.
: 3)    RO will manually trip the turbine.
: 4)    RO verifies control rods inserting at >48 steps per minute.
: 5)    When rod speed lowers to < 48 steps per minute; RO places rod control in manual and inserts rods.
Critical Task:
CT-1: DRP-049 E-12, Insert negative reactivity into the core by at least one of the following methods before completing the Immediate Action Steps of FR-S.1.
Insert Control Rods in auto or manual within 30 seconds of the onset of the ATWS event.
Event #8:  LOCA Outside of Containment. (M - ALL)
The Team will be alerted to this condition based upon alarms and indications received, return to 1-E-0, and manually Safety Inject.
The RO and SRO continue with E-0 while the BOP performs Attachments 1, 2, and 3 of E-0. The Team will transition from 1-E-0 to 1-ECA-1.2, LOCA Outside Containment. In 1-ECA-1.2, the LOCA will be isolated by closing 1-SI-MOV-1890C, common LHSI pump discharge to RCS Cold Legs. The Team will transition to 1-E-1, Loss of Reactor or Secondary Coolant.
 
Appendix D                                  Scenario Outline                              Form ES-D-1 NRC EXAM - SCENARIO #4 Verifiable Actions:
: 1) RO will manually initiate SI.
: 2) During performance of 1-E-0 Attachments the BOP will identify and correct the following items: 1-SI-P-1A not auto start, 1-CH-MOV-1115D not auto open, 1-CH-MOV-1115C not auto close, 1-CH-MOV-1289A not auto close, 10CV-TV-150A and 1-CH-TV-1204A not auto close.
Critical Task:
CT-2: Critical Task: E 1.2. Trip all RCPs within 5 minutes of reaching RCP Trip Criteria. (WOG E-1-C).
CT-3: WOG ECA-1.2A, Isolate the LOCA outside containment before transition out of ECA-1.2, or cavitation of any LHSI pump. SPS- Isolate LOCA outside containment before transition out of ECA-1.2 (PSA).
Post Scenario Classification:
Follow-up Classification: Site Area Emergency, FS-1.1.
The Scenario can be terminated upon 1-E-1 entry or Lead Evaluator Cue.
 
Appendix D                                                Scenario Outline                                        Form ES-D-1 NRC EXAM - SCENARIO #4 Initial Conditions: IC #1 100%, MOL - Cycle 26. The unit has been at 100% power for > 30 days Pre-load malfunctions: (Trigger 30s) o SI2402, SI RELAY SI2A FAILS TO ACTUATE o SI2405, SI RELAY SI5A FAILS TO ACTUATE o AAC_SMS_MODE, OFF, AAC DG LOCAL MODE SWITCH POSITION o CC1801, DISABLE CCP1A AUTO START o SW_25J10_RF, 1-CC-P-1D CONTROL SWITCH, PTL Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:
Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:
AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
1-CC-P-1D id tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
Turnover:
Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. . IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* 1-CC-P-1D, D CC pump tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
* Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
* A BAST at 8.0 W/%.
* PSA id Green.
Event      Malf. #s      Severity                            Instructor Notes and Required Feedback 1              N/A            N/A        Deleted.
2            RC4802,        +1 Deg        1-RC-PT-1445 fails high, PRZR Pressure channel fail high. AP-31.00, Increasing or Decreasing RCS Pressure.
3            MS1305,        +1 Deg        Steam Pressure Channel III, B SG fails High. 0-AP-53.00, Loss of Vital Instrumentation/Controls.
4            CH2101,        +1 Deg        Failure of VCT Level Channel LT-115 High.
CC0302          TRUE 5            CC0802                        Overcurrent on B CC pump with breaker mechanically stuck closed causing the TRUE          trip of Stub Bus Supply breaker.
SW_15J9_
RF            TRIP 6            RD1236                        Dropped Rod Control Bank C, Group 1; AP-1.00, Rod Control Malfunction, AP-TRUE        23.00, Rapid Load Reduction.
: 7.          RC MOV 30%
RC Loop C Tc MOV disc falls into flow stream, Valid First-Out received, No Auto 595                        or Manual Reactor Trip. 1-FR-S.1, Response to Nuclear Generation/ATWS.
TRUE RD17 SI1502,        40% Deg 8          SI1603            TRUE          LOCA outside of Containment in Unit 1 Valve Pit Area.
SI1606            TRUE
 
Appendix D                                Scenario Outline                                      Form ES-D-1 NRC EXAM - SCENARIO #4 9      SI2402              SI Relay SI2A fails to Actuate, SI Relay SI5A Fails to Actuate;1-SI-P-1A not auto SI2405      C - BOP  start, CH-MOV-1115D, CH-MOV-115C, CH-MOV1289A, CV-TV-150A, and CH-TV-1204A fail to re-position of SI.
Scenario Objectives:
A. Deleted.
B. Given a failure of 1-RC-PT-1445 in the high direction respond IAW AP-53.00/AP-31.00 to regain control of RCS pressure.
C. Given the failure of Steam Pressure Channel III, B SG fails High repons IAW 0-AP-53.00, Loss of Vital Instrumentation/Controls.
D. Given the failure of VCT level 1-CH-LI-1115 high, respond IAW AP-53.00 to secure the divert of letdown flow to the PDTT.
E. Given the loss of the 1J stub bus, respond IAW 1K-H4 to restore CC flow to normal on Unit 1.
F. Given a dropped rod, respond IAW AP-1.00 and AP-23.00 to ramp the Unit to 70-74%.
G. Given a valid reactor trip signal with no automatic reactor trip respond IAW FR-S.1 to shutdown the reactor.
H. Given a LOCA outside of Containment respond IAW E-0 and ECA-1.2 to isolate the RCS leak path.
I. Given various component failing to reposition utilize E-0 Attachments to identify and place the components in the correct position.
 
SHIFT TURNOVER INFORMATION OPERATING PLAN:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* 1-CC-P-1D is tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
Shift orders are to maintain 100% power on Unit #1.
The last shift performed two 35 gallon dilutions followed by a manual makeup for training.
A BAST at 8.0 W/%.
PSA is Green.
 
Appendix D                              Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                    Event No.: 1          Page 11 of 98 Event
 
== Description:==
Perform 1-OP-RP-001. Section 5.2, Preparation for Channel II Testing.
Cue: When team ready.
Time        Position                              Applicants Action or Behavior EVENT 1 - Deleted
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 4                    Event No.: 2                    Page 12 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
Note:  An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.
The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.
A facility representative will be present for consultation with the Evaluation Team, as needed.
Time        Position                                  Applicants Action or Behavior RO        Diagnoses the event using the following:
Alarms:
1C-F8, PRZR HI PRESS 1D-H4, PRZR SFTY VV PWR RELIEF VV OPEN Indications:
1-RC-PCV-1456, PRZR PORV, RED Open Lights LIT.
RCS Pressure Decreasing.
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS Note: SRO may directly enter 1-AP-31.00, Increasing or Decreasing RCS Pressure, Page 14.
RO        [1] Check REDUNDANT INSTRUMENT CHANNEL(S) INDICATION - NORMAL Identifies RCS Pressure decreasing using 1-RC-PI-1444 or RCS Wide Range Pressure Indicated on A / B ICCM Display.
RO        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-RC-PV-1456 control switch in Close. Verifies 1-RC-PCV-1456 closes by GREEN Light LIT, RED Light off.
RO/BOP            During pressure transient, the Rod Control Switch may be placed in MANUAL due to Rods stepping OUT due to pressure coefficient.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 2                    Page 13 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00 SRO      *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO          Identify that reactor power is less than 100%.
SRO      Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO      *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
* PRZR Pressure Control, Step 5 RO      The RO will identify that 1-RC-PI-1445 failed high.
NOTE: RCS pressure decrease will cause a slight decrease in RCS Tave due to negative reactivity from the moderator pressure coefficient.
SRO      5        CHECK PRZR SPRAY VALVE CONTROLLERS - NORMAL RO          RO identifies PRZR Spray Valves controllers normal.
SRO      6  GO TO ( )-AP-31.00, INCREASING OR DECREASING RCS PRESSURE SRO announces transition to AP-31.00.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 2                    Page 14 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior 1-AP-31.00 SRO      [ 1 ] ___ CHECK PRZR PORVS - CLOSED RO      Identifies 1-RC-PCV-1456 closed.
1-AP-31.00 Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-31.00 1-AP-31.00 CAUTION: A Safety Injection may occur if the unit is not tripped prior to RCS pressure decreasing below 2100 psig.
SRO      2    CHECK RCS PRESSURE - DECREASING RO      Identifies RCS Pressure rising following PORV Closure.
2 RNO IF RCS pressure is stable or increasing following PORV closure, THEN GO TO Step 10.
Note: If the RO responds to Step as conditions were prior to PORV closure, this flow path is incorrect and a follow-up may be required.
1-AP-31.00 SRO      10 CHECK RCS PRESSURE - STABILIZING AT OR TRENDING TO 2235 PSIG RO      Identifies RCS pressure trending to 2235 psig.
1-AP-31.00 SRO      11. GO TO STEP 17
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 2                    Page 15 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
1-AP-31.00 SRO      17 CHECK MASTER CONTROLLER                                  GO TO Step 19
                              - IN MANUAL RO      Identifies Master Pressure Controller in Auto 1-AP-31.00 SRO 19 CHECK PRZR PORVS - EITHER INOPERABLE
* 1-RC-PCV-1455C
* 1-RC-PCV-1456 RO      Identifies 1-RC-PCV-1456 Inoperable.
1-AP-31.00 20 CLOSE BLOCK VALVE FOR INOPERABLE PORV SRO
* 1-RC-MOV-1535 if 1-RC-PCV-1456 inoperable RO      Places 1-RC-MOV 1535 control switch in close. Monitors MOV until GREEN indicating light LIT and RED Light out.
1-AP-31.00 SRO      21 CHECK PRZR PORVS - EITHER                                  GO TO Step 23 INCAPABLE OF BEING MANUALLY CYCLED
* 1-RC-PCV-1455C
* 1-RC-PCV-1456 RO      States Both PORVs are capable of being manually cycled.
1-AP-31.00 SRO      23 NOTIFY THE FOLLOWING:
* OM on call
* STA
* I&C Notifies Shift Manager of the Event and requests notifications be made.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 2                    Page 16 of 98 Event
 
== Description:==
1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.
Cue: By Examiner.
1-AP-31.00 SRO      24 REFER TO TECH SPECS:
* 3.1.A.5
* 3.1.A.6
* 3.1.C
* 3.12.F
: 1) The SRO will consult Tech Specs, TS Section 3.1.A.6, and determine that 1-RC-PCV-1456 is Inoperable but capable of being manually cycled, and enter a one hour clock to close the block valve for the PORV. The block valve will remain energized.
: 2) Further consultation will find Tech Spec 3.12.F.1 to restore RCS pressure >2205 psig in 2 hours or reduce Thermal Power to less than 5% in the next 6 hours. The Core Operating Limits Report (COLR, DRP-21) provides the reference for 2205 psig RCS pressure.
NOTE: Following closure of block valve the 1 hour Tech Spec clock clears. RCS pressure decreases to < 2205 psig during the transient; once the PORV has been closed, pressure recovers quickly and goes above 2205 psig.
SRO updates the Team concerning the identified items in Tech Specs and updates the Shift manager.
1-AP-31.00 SRO      25 REVIEW APPLICABILITY:
* VPAP-2802
* EAL Matrix SU6.1 SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.
1-AP-31.00 SRO      26        RESTORE PRESSURE CONTROL SYSTEM(S) TO NORMAL END EVENT 2
 
Appendix D                                  Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 3                  Page 17 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior 0-AP-53.00 BOP        Diagnoses failure 1-MS-PT-1485 with the following indications/alarms:
Alarms:
* 1H-E6 STM GEN 1B FW >< STM FLOW
* 1F-C8 STM GEN 1B CH 3 FW < STM FLOW
* 1H-G6 STM GEN 1B LVL ERROR.
Indications:
* Step increase in 1B SG Steam Flow indication CH-III
* Increasing level on B SG.
0-AP-53.00 SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS 0-AP-53.00 BOP        [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL BOP identifies Channel IV indication for steam flow/Steam Pressure is NORMAL 0-AP-53.00 BOP        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and lowers demand (FF < SF) to restore level to program
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 3                    Page 18 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00.
0-AP-53.00 SRO        *3        VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO        Identify that reactor power is less than 100%.
Note:    Based on the feed flow > steam flow mismatch during initial stage of the Event, Calorimetric power may exceed 100% during restoration of B SG NR level to program.
0-AP-53.00 SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
0-AP-53.00 SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
SG Pressure, Step 7 BOP            States B SG Pressure affected.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 3                    Page 19 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.
SRO        7. CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS -
NORMAL
* Steam Pressure
* Steam Flow
* Feed Flow
* Steam Generator Level BOP        Determines CH III Steam pressure instrumentation for B SG is NOT normal.
Step 7. RNO IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level Control system has failed, THEN do the following:
a)  Place the associated Feed Reg Valve in MANUAL.
BOP        Verifies B SG MFRV controller, 1-FW-FCV-1488, in manual b) Control SG level at program level (44%, a band will be given).
BOP        Verifies B SG NR level is returning to program level.
c) Select the redundant channel for affected SG(s)
RO        Selects Channel IV Steam Flow for B SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV).
d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.
BOP        Places B SG FRV controller, 1-FW-FCV-1488, in automatic control
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 3                    Page 20 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        Step 7. RNO (Continued)
Perform follow-up actions:
a)  Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.
b) Refer to the following Tech Spec 3.7 items:
* Table 3.7-1, 12 and 17
* Table 3.7-2, 1.c, 1.e, and 3.a
* Table 3.7-3, 2.a, and 3.a
: 1) Tech Specs Section 3.7, Table 3.7-1, Item 17, Low steam generator water level with steam/feedwater flow mismatch, Operator Action 6. With the number of Operable channels one less than the total number of channels, Power Operation may proceed provided the channel is placed in the trip condition in 72 hours, the channel may be bypassed for 12 hours for surveillance; if these requirements are not met, the Unit must be placed in Hot Shutdown within 6 hours.
: 2) Tech Spec 3.7, Table 3.7-2, Item 1.c., High differential pressure between any steam line and the steam header, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours; the channels may be bypassed for 12 hours for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours and reduce RCS temperature and pressure to less than 350&deg;F/450 psig in the following 12 hours.
: 3) Tech Spec 3.7, Table 3.7-2, Item 1.e.1 and 1.e.3, High Steam line flow in 2/3 steam lines coincident with low Tavg or low line pressure, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours; the channels may be bypassed for 12 hours for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours and reduce RCS temperature and pressure to less than 350&deg;F/450 psig in the following 12 hours.
: 4) Tech Spec Table 3.7-3, item 2a, Steam Line Isolation. Refers to Tech Spec Table 3.7-2, Item 1.e. See Above
: 5) Tech Spec Table 3.7-6, Item 16, SG Pressure, 2 per SG are required. This condition is met (2 of 3 channels still Operable).
c)  Refer to Attachment 1.
d) IF no other instrumentation failure exists, THEN GO TO Step 13.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 3                    Page 21 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        13. CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001.
SRO/RO reviews OPT-RX-001, Attachment 4, and determines Calorimetric is NOT impacted and OPT-RX-007 will NOT need to be performed.
0-AP-53.00 SRO        14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 16 if not Reg. Guide 1.97)
SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-MS-PT-1485 is a Reg. Guide 1.97 component.
0-AP-53.00 SRO        15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
[CEP 99-0029 requires two channels of Steam Pressure indication per steam generator, refers to Tech Spec 3.7, Table 6, Item 16, 2 required per SG.]
0-AP-53.00 SRO        16. Review the following:
* TS 3.7 Determines Table 3.7-1 item 17, 3.7-2 item 1.c. and 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours). Also TS-3.7, Table 6, item 16, two SG Pressure Indicators per SG.
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
[VPAP-2802 and TRM Section 3.3 are not impacted by this failure.]
 
Appendix D                                Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 3 Page 22 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.
Cue: By Examiner.
0-AP-53.00 SRO        17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS BOP        Reports no additional failure exists SRO        GOES TO Step 19 0-AP-53.00 SRO        19. PROVIDE NOTIFICATIONS AS NECESSARY:
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C END EVENT #3
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 4                    Event No.: 4                    Page 23 of 98 Event
 
== Description:==
Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.
Cue: When initiated by Team Time        Position                                  Applicants Action or Behavior Diagnoses failure 1-CH-LT-1115 with the following indications/alarms:
BOP Alarms:
* 1D-G1 VCT HI - LO LVL Indications:
* 1-CH-LCV-1115A Amber Divert light LIT.
* Decreasing VCT level on channel 1-CH-LI-1112.
SRO        Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS RO        [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -
NORMAL RO identifies Channel LI-1112 VCT Level indication is NORMAL.
RO        [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION RO places the control switch for 1-CH-LCV-1115A in NORM position to close the VCT Divert Valve. Monitors to ensure amber light extinguishes and VCT level stabilizes.
SRO        Conducts a Brief summarizing the Event and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Completes Brief and continues with AP-53.00.
SRO        Note: Discusses with RO control of VCT level and monitoring of channel 1-CH-LT-1112 to ensure that VCT level will not drop to the point where the CH pumps could air bind. The SRO will set a band for manual makeup to the VCT and a minimum VCT level where the manual swap to the RWST will be required.
 
Appendix D                                    Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 4                    Event No.: 4                  Page 24 of 98 Event
 
== Description:==
Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.
Cue: When initiated by Team SRO        *3        VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%
RO        Identify that reactor power is less than 100%.
SRO        Notes Prior to Step 4:
* Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
* When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.
SRO        *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:
VCT Level, Step 12e RO SRO        12 e)      VCT level Instrumentation - NORMAL RO            States 1-CH-LT-1115, VCT Level Channel affected.
SRO        Refer to Attachment 6 Attachment 6, 0-AP-53.00 SRO            If ( )-CH-LT-( )115 fails high, ( )-CH-LCV-( )115A will open. Manual control of the blender will be required. Automatic swap-over of the CHG pump suction from the VCT to the RWST will not function.
: a. VCT High level divert of ( )-CH-LCV-( )115A to PDT at 85%
: b. VCT High level alarm at 82%
: c. Auto makeup to VCT stop at 34%
: d. Auto makeup to VCT start at 27%
: e. VCT Low level alarm at 24%
: f. CHG pump suction swap over to the RWST at 13% (2/2)
SRO            Note: Discusses with RO control of VCT level and monitoring of channel 1-CH-LT-1112 to ensure that VCT level will not drop to the point where the CH pumps could air bind. The SRO will set a band for manual makeup to the VCT and a minimum VCT level where the manual swap to the RWST will be required.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2012-1          Scenario No.: 4                  Event No.: 4                Page 25 of 98 Event
 
== Description:==
Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.
Cue: When initiated by Team SRO        13 CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001 SRO/RO            SRO/RO determines that OPT-RX-001, Attachment 4, is NOT impacted and OPT-RX-007 will NOT need to be performed.
: 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 SRO              VARIABLE (Go to Step 16 if not Reg. Guide 1.97)
The STA will report that 1-CH-LI 1115 is a Reg. Guide 1.97 component.
SRO        15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
[CEP 99-0029 requires 1 channel of VCT level indication. 1-CH-LT-1112 may be used as an alternate indication. Restore 1-CH-LT-1115 before the next outage.]
SRO        16. Review the following:
* TS 3.7
* VPAP-2802
* TRM Section 3.3, Instrumentation SRO            SRO will consult Tech Specs and find no items affected.
SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
[VPAP-2802 and TRM Section 3.3 are not impacted by this failure.]
0-AP-53.00 SRO        17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -
EXISTS BOP        Reports no additional failure exists SRO        GOES TO Step 19
 
Appendix D                                Required Operator Actions          Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                Event No.: 4 Page 26 of 98 Event
 
== Description:==
Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.
Cue: When initiated by Team
: 19. PROVIDE NOTIFICATIONS AS NECESSARY:
SRO
* Shift Supervision
* OMOC
* STA (PRA determination)
* I&C END EVENT #4
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                    Page 27 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior TEAM        Diagnose the failure using the following:
Alarms:
1K-D5, CC PP 1B IN LOCAL CONTROL OR OL TRIP 1K-E7, CC PPS DISCH HDR LO PRESS 1K-H4, 4KV EMERG BUS STUB BUS TIE BKR TRIP Indications:
Breaker 15J9, 1J Stub Bus Breaker, indicates Open on PCS Breaker 15J10, 1-CC-P-1B breaker indication RED and GREEN Light OFF.
1-CC-P-1B amps indication at 0. 1-CC-P-1A not running.
Note: ARP Steps start on Page 30.
Note: If the Team opts to trip the reactor, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-AP-10.07 SRO SRO will hold a Transient Brief and Establish priorities.
RO will provide Critical Parameters using Brief Placard.
BOP will provide Critical Parameters using Brief Placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
Directs the BOP to review ARPs for Lit annunciators, SRO/RO will continue with 1-AP-10.07.
Directs RO/BOP to contact Auxiliary Building Operator to check status of 1-CC-P-1A and 1-CC-P-1B. Direct Service Building Operator to check status of 1-CC-P-1B breaker, BKR 15J10, and the 1J stub bus breaker, 15J9.
Completes Brief and continues with AP-10.07.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                      Event No.: 5                  Page 28 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
Step 1, 1-AP-10.07 SRO      NOTE:
* If both units are affected, local actions should be coordinated.
* The AAC Diesel Generator will automatically start if an undervoltage occurs on Transfer Buses D and F.
* With Degraded Voltage or Undervoltage on 2J Bus, or a loss of Unit 2B DC Bus, Breaker 15J3 will not close automatically, except with a valid Unit 1 SI signal.
* EPIPs may be applicable.
: 1. CHECK UNIT - BLACKOUT HAS OCCURRED
* Transfer Buses D and F - DEENERGIZED AND
* All Station Service Buses - DEENERGIZED RO          Reports Blackout has not occurred.
SRO      GOES TO Step 39.
Step 39, 1-AP-10.07 SRO      39 CHECK THE FOLLOWING BREAKERS - ANY OPEN:
* 15D1 OR
* 15F1 OR
* 15H8 OR
* 15J8 RO          Reports Breakers Closed.
39 RNO      IF all 480V Emergency Buses energized, THEN GO TO Step 75.
SRO      Goes to Step 75.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                  Event No.: 5                  Page 29 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
Step 75, 1-AP-10.07 SRO      75 CHECK ANY STATION SERVICE BUS - DEENERGIZED:
* 15A1 and 15A2 - OPEN OR
* 15B1 and 15B2 - OPEN OR
* 15C1 and 15C2 - OPEN RO      Reports breakers 15A2 / 15B2 / 15C2 closed.
SRO      75 RNO      IF ALL 480V Station Service Buses are energized, THEN GO TO Step 97.
SRO          Goes to Step 97.
Step 97, 1-AP-10.07 SRO      97 NOTIFY THE FOLLOWING:
* OMOC
* STA
* Electrical Foreman ARP 1K-D5 BOP      1  CHECK 1-CC-P-1B IN LOCAL CONTROL DUE TO PLANT EVOLUTION 1-CC-P-1B not in Local due to Plant Evolution.
No Plant evolution in progress.
IF 1-CC-P-1B tripped due to leak or rupture, THEN do the following:
No leak or rupture indicated.
IF leak or rupture NOT present, THEN GO TO Step 3.
Go to Step 3
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                      Page 30 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
ARP 1K-D5 BOP      3. VERIFY STANDBY CC PP - STARTED
* 1-CC-P-1A No, 1-CC-P-1A not running Consults SRO concerning Manual start of 1-CC-P-1A.
Announces and Starts 1-CC-P-1A.
ARP 1K-D5 BOP      4 CHECK 1-CC-P-1B - TRIPPED DUE TO UNDERVOLTAGE ON THE 1J EMERGENCY BUS Do the following:
a) IF CC pump NOT tripped, THEN do the following:
b) Locally check breaker 15J10.
c) Locally check 1-CC-P-1B.
BOP          When local status of 1-CC-P-1B received, Focus Brief to inform Team that 1-CC-P-1B normal; 1-CC-P-1B breaker is closed, breaker 15J10 closed with an overcurrent trip flag, breaker 15 J9, stub bus breaker, is open with an overcurrent trip flag.
d) IF unable to restore 1-CC-P-1B, THEN do the following:
: 1) Initiate a Condition Report.
: 2) Review Tech Spec 3.13.
: 3) GO TO Step 7.
ARP 1K-D5 BOP      7  VERIFY CC SYSTEM PARAMETERS - NORMAL
* CC Surge Tank Level - STABLE
* CC Pump amps - STABLE
* AUX BLDG and CTMT Sump levels - NORMAL Review parameters, identify no trends exist, report parameters as normal.
ARP 1K-D5 BOP      8  PROVIDE NOTIFICATIONS:
* OMOC
* STA Inform SRO to Notify OMOC and STA.
Move to next ARP.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                    Page 31 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
ARP 1K-E7 BOP      1  VERIFY CC HEADER PRESSURE - LESS THAN 90 PSIG
* PI-CC-100, CC PP DISCH PRESS Reports PI-CC-100 indicates approximately 100 psig.
Step 1 RNO Do the following:
a) Increase surveillance of CC parameters.
b) Initiate a Work Request.
c) GO TO Step 18.
ARP 1K-E7 BOP      18      NOTIFY SHIFT SUPERVISION Notifies SRO, ARP 1K-E7 complete, a CR is required.
Moves to 1K-H4 ARP ARP 1K-H4 BOP      1  VERIFY ALARM - LOSS OF EMERGENCY BUS
* Bus 1H Undervolt - 15H8 TRIPPED OR
* Bus 1J Undervolt - 15J8 TRIPPED Identifies 1H and 1J not tripped Step 1 RNO Do the following:
a) Check for loss of Stub Bus loads:
* CC Pump
* RHR Pump Identifies Stub bus loads have been lost.
Step 1 RNO b) IF Stub Bus loads lost, THEN do the following:
: 1) Start standby pumps IAW Shift Supervision direction.
: 2) Locally check stub bus tie breaker cubicles in ESGR.
: 3) IF Stub Bus Breaker Cubicle Relays (Type IAC) orange drop - IN, THEN GO TO Step 4.
Based on Focus Brief - Goes to Step 4.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                      Page 32 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
ARP 1K-H4 BOP      4        CHECK RHR AND CC - RESTORED AS NECESSARY Identifies 1-CC-P-1A running.
ARP 1K-H4 BOP      5    PROVIDE NOTIFICATIONS AS NECESSARY:
* OMOC
* Electrical Foreman
* Control Operations
* Shift Supervision Notifies SRO that in addition to previous individuals notified, the Electrical Forman needs to be notified ARP 1K-H4 BOP      6    SUBMIT A CONDITION REPORT Notifies SRO that a CR is required.
ARP 1K-H4 BOP      7  REVIEW TECH SPECS Notifies SRO to Review Tech Specs SRO      The SRO will consult Tech Specs 3.13.A.2 and 3.13.B, and determine that the minimum Operable CC pumps requirement is not met. For 2 Unit operation, 3 CC pumps must be operable, and TS 3.13.B cannot be met, the SRO should identify a TS 3.01, 6 hour clock to HSD, and a 30 hour clock to CSD.
Consult Tech Spec 3.5.A.1 and determine the Minimum Operable RHR pumps requirement is not met. This requires, IAW TS 3.5.B, that a 14 day clock be entered to restore A RHR pump to an Operable condition.
[TRM Table 3.7.9-1; IAW TRM 3.7.9.A, additional 72 hour and 14 day clocks are in effect to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.]
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2012-1        Scenario No.: 4                    Event No.: 5                  Page 33 of 98 Event
 
== Description:==
1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.
Cue: By Examiner.
SRO          Directs STA to review Tech Specs and TRM.
STA          Acknowledge direction to review Tech Specs and TRM. STA will report TRM has been reviewed and discussed with the Shift Manager.
SRO      Contacts the Shift Manager to provide an update on Plant Status, Tech Spec Clocks entered, and request notification of the OMOC and Electrical Foreman.
END EVENT #5
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 6                  Page 34 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
Time        Position                                Applicants Action or Behavior Team      Diagnoses the dropped rod with the following indications/alarms:
Alarms:
* 1G-B5, COMPUTER PRINTOUT ROD CONT SYS.
* 1G-C4, UPPER ION CHAMBER DEVIATION OR AUTO DEFEAT <50%.
* 1G-D4, LOWER ION CHAMBER DEVIATION OR AUTO DEFEAT <50%.
* 1G-E4, NIS PWR RNF CH AVG FLUX DEVIATION.
* 1C-B8 - PRZR LO PRESS
* 1G-H1 - NIS DROPPED ROD FLUX DECREASE > 5% PER 2 SEC
* 1G-H2 - RPI ROD BOTTOM <20 STEPS
* 1G-F8, ROD BANK D WITHDRAWAL.
Indications:
RO
* Outward Rod Motion.
* RCS Temperature and Pressure decrease.
* Flux Variations (radial).
* CERPI indication that Control Rod M-4 is at 0 steps.
In accordance with the immediate actions of 1-AP-1.00 (Rod Control System Malfunction) the RO will place Control Rods in MANUAL to stop the outward rod motion.
RCS pressure <2205 psig places the unit in a 2 hour clock iaw TS. 3.12.F.1 (and COLR) - it is expected that the SRO will track this clock (entry/exit times).
0-AP-1.00 SRO        Enters 0-AP-1.00 (Rod Control System Malfunction).
SRO        CAUTION prior to Step 1:
* If Tave decreases below 530 &deg;F, 1-E-0, Reactor Trip or Safety Injection, must be implemented.
RO        [1] CHECK FOR EITHER OF THE FOLLOWING:
* Continuous rod withdrawal
* Continuous rod insertion RO will note that there was a continuous rod withdrawal.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                    Page 35 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
RO/BOP      [2] STOP ROD MOTION
: a. Put ROD CONT MODE SEL switch in MANUAL
: b. Verify rod motion - STOPPED RO will place control rods in MANUAL and note that Rods stopped moving.
0-AP-1.00 SRO        The team will hold a transient brief. During the brief the dropped rod will be discussed.
The RO and BOP will report out critical parameters, as per placard on Main Control Room Bench Board.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
0-AP-1.00 RO
: 3. CHECK ROD MOTION - DUE TO INSTRUMENTATION FAILURE
* First Stage Impulse Pressure
* Tave/Tref
* Nuclear Instrumentation RO will note that an instrumentation failure did not exist. The team will transition to the RNO for Step 3.
0-AP-1.00 RO
: 3. RNO If rod motion due to a dropped rod, THEN GO TO Step 6.
RO will note that dropped rod caused the rod motion.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                    Page 36 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
0-AP-1.00 RO
: 6. CHECK IF ANY ROD DROPPED:
* Annunciator ( )G-H2, RPI ROD BOTTOM  20 STEPS - LIT OR
* Annunciator ( )G-H1, NIS DROPPED ROD FLUX DECREASE  5%
PER 2 SEC - LIT OR
* Rod Bottom Lights - ANY LIT OR
* Any Rod On Bottom light - LIT OR
* Indication of a partially dropped rod in the core The RO will note that they have multiple indications of a dropped rod in the core.
0-AP-1.00 RO
: 7. CHECK REACTOR STATUS PRIOR TO FAILURE - CRITICAL 0-AP-1.00 RO        8. CHECK ONLY ONE ROD AFFECTED 0-AP-1.00 RO
: 9. CHECK REACTOR POWER - GREATER THAN 25%
0-AP-1.00 BOP/RO
: 10. CHECK UNIT CONDITIONS - STABLE 0-AP-1.00 RO
: 11. PLACE ROD CONTROL IN MANUAL 0-AP-1.00 RO/BOP
: 12. CHECK POWER RANGE NIs - ANY DROPPED ROD SIGNAL PRESENT 0-AP-1.00 BOP
: 13. RESET NIS DROPPED ROD SIGNAL IAW ATTACHMENT 4 Note: Attachment 4 of AP-1.00 is located on Page 40.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1          Scenario No.: 4                    Event No.: 6                      Page 37 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
0-AP-1.00 RO
: 14. CHECK ANNUNCIATOR 1G-F8, ROD BANK D WITHDRAWAL - NOT LIT If alarm is LIT, then the RNO will direct the team to initiate Attachment 5 - This attachment follows attachment 4 at the end of this event.
Note: This may not be lit if the ROBOP quickly placed rods in MANUAL when withdrawing or ARP 1G-F8, Bank D Withdrawal, has been completed.
0-AP-1.00 SRO Note prior to Step 15:
* Quadrant power tilt may cause unit ramp requirements to be more restrictive.
0-AP-1.00 SRO
: 15. VERIFY QUADRANT POWER TILT RATIO
* Initiate Attachment 6, QUADRANT POWER TILT CALCULATION
* Review Technical Specification 3.12.B.6 SRO will direct the STA to perform the QPTR in accordance with Attachment 6 and review TS 3.12.
Summary of applicable Tech Specs are found following Step 18.
0-AP-1.00 SRO        Notes prior to Step 16:
* Checking that the unit is operating between Hot Zero Power and Hot Full Power, that there is only one fully dropped (less than 10 steps) control rod, and that all other rods are above the rod insertion limit, checks that adequate SDM exists.
* SDM must be re-verified using 1-OP-RX-001 every 12 hours after the control rod was dropped until the Reactor is shutdown or the rod is declared operable.
0-AP-1.00 SRO
: 16. VERIFY SHUTDOWN MARGIN (WITHIN ONE HOUR)
* The fully dropped rod (less than 10 steps) is the only inoperable rod AND
* All other rods are greater than the Rod Insertion Limit 0-AP-1.00 SRO
: 17. MAKE NARRATIVE LOG ENTRY THAT SDM IS MET
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 6                    Page 38 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
SRO        Caution prior to Step 18:
* Loop T is the most accurate measure of Reactor power with a mis-aligned rod, and must be monitored during the ramp and used as a basis for stabilizing power.
RO        18. CHECK REACTOR POWER - LESS THAN OR EQUAL TO 75%
Step 18 RNO actions:
Do the following:
: a. Reduce Reactor Power to between 70% - 74% within one hour.
: b. Reduce NIS High Flux trip setpoints to less than or equal to 85% within the following four hours.
: c. WHEN Reactor Power has been reduced, THEN GO TO Step 19.
The team will enter AP-23.00 to reduce reactor power.
Note: 0-AP-23.00, Rapid Load Reduction, actions start on page 42.
Evaluators Note: Go to EVENT 7 when the Examiner has seen a sufficient change in power level during the ramp in AP-23.00.
SRO        Applicable Tech Specs for Dropped Rod:
3.12.B.6:
If, except for operation at THERMAL POWER < 50% or for physics and control rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2%, then:
: c. Within 2 hours, either the hot channel factors shall be determined and the power level adjusted to meet the requirement of Specification 3.12.B.1, or
: d. The power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours.
: e. If the QUADRANT POWER TILT exceeds 10%, the power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours.
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 6                    Page 39 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
Applicable Tech Specs for Dropped Rod: (Continued) 3.12.C.3:
Startup and POWER OPERATION may continue with one control rod assembly inoperable provided that within one hour either:
: a. The control rod assembly is restored to OPERABLE status, as defined in Specification 3.12.C.1 and 2, or
: b. the shutdown margin requirement of Specification 3.12.A.3.c is satisfied.
: c. POWER OPERATION may then continue provided that:
: 1) either:
a) power shall be reduced to less than 75% of RATED POWER within one (1) hour, and the High Neutron Flux trip setpoint shall be reduced to less than or equal to 85% of RATED POWER within the next four (4) hours, or b) the remainder of the control rod assemblies in the group with the inoperable control rod assembly are aligned to within 12 steps of the inoperable rod within one (1) hour while maintaining the control rod assembly sequence and insertion limits specified in the CORE OPERATING LIMITS REPORT; the THERMAL POWER level shall be restricted pursuant to Specification 3.12.A during subsequent operation.
: 2) the shutdown margin requirement of Specification 3.12.A.3.c is determined to be met within one hour and at least once per 12 hours thereafter.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                Page 40 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
BOP        ATTACHMENT 4 of AP-1.00 - RESETTING NIS DROPPED ROD SIGNALS Perform the following for each NI with a dropped rod status light lit.
: 1. N41 RESET a)  Place the Power Range Test Switch in RESET.
b)  Check the Dropped Rod Status Light on N41 - NOT LIT.
c)  Return the Power Range Test Switch to NORMAL.
: 2. N42 RESET a)  Place the Power Range Test Switch in RESET.
b)  Check the Dropped Rod Status Light on N42 - NOT LIT.
c)  Return the Power Range Test Switch to NORMAL.
3    N43 RESET a)  Place the Power Range Test Switch in RESET.
b)  Check the Dropped Rod Status Light on N43 - NOT LIT.
c)  Return the Power Range Test Switch to NORMAL.
: 4. N44 RESET a)  Place the Power Range Test Switch in RESET.
b)  Check the Dropped Rod Status Light on N44- NOT LIT.
c)  Return the Power Range Test Switch to NORMAL.
: 5. Check annunciator ( )G-H1, NIS DROPPED ROD FLUX DECREASE >5% PER SEC - NOT LIT
: 6. Check annunciator ( )G-F8, ROD BANK D WITHDRAWAL - NOT LIT
: 7. IF ( )G-F8, ROD BANK D WITHDRAWAL is LIT, THEN initiate Attachment 5.
 
Appendix D                              Required Operator Actions              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 6      Page 41 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.
Cue: By Examiner.
BOP        ATTACHMENT 5 of AP-1.00 - RESPONSE TO ROD BANK D WITHDRAWAL
 
Appendix D                                  Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 6                    Page 42 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
Time        Position                                  Applicants Action or Behavior 0-AP-23.00 TEAM        0-AP-23.00 (RAPID LOAD REDUCTION) Actions SRO      The team will hold a transient brief. During the brief, the upcoming ramp will be discussed.
The RO and BOP will report out critical parameters, as per placard on Main Control Room Bench Board. It is expected that the RO will discuss reactivity parameters associated with the ramp from the pre-planned ramp plans taking in account the conditions presented by the dropped rod.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
The following reactivity plan will be discussed for a ramp to 75%:
* Gallons of boric acid required as per plan - 146 gallons, Rate of 5.8 gpm.
* D control bank end at 197 steps, 1957 gallons PG to stabilize.
* Subtracted from the boration will be the equivalent boron added from the dropped rod - 9.5 gallons for each degree of Tave decrease - this should be about 42 gallons based on a 4.4&deg; temp decrease. This will be subtracted from the initial 146 gallons - therefore, approximately 104 gallons of boric acid are required to be added.
EVALUATOR NOTE: RO Emergency borates for 25 seconds which corresponds to
                        ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.
SRO      Caution Prior to Step 1:
* Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.
Notes Prior to Step 1:
* Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
* When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
* Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
* The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
* For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                  Page 43 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
0-AP-23.00 RO      1. TURN ON ALL PRZR HEATERS
: 2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:
BOP            a) Check turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.
RO            b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5&deg;F.
SRO/BOP          c) Check or place turbine in IMP IN as determined by Shift Supervision The SRO can choose IMP IN or IMP OUT.
d) Adjust SETTER to desired power level BOP e)  Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute) f)  Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) g) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.
SRO      3. CHECK EMERGENCY BORATION - REQUIRED The team may decide to emergency borate after the ramp has progressed to the point that Tave and Tref are matched (or close).
SRO      Note Prior to Step 4:
* Step 4 or Step 5 may be performed repeatedly to maintain Tave and Tref matched, Flux in band, and control rod position above the LO-LO insertion limit.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                    Page 44 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
0-AP-23.00 RO      4. PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:
a) Check or raise CHG flow to greater than 75 gpm b) Transfer the in-service BATP to FAST c) Open ( )-CH-MOV-( )350 d) Monitor EMRG BORATE FLOW
                                        *  ( )-CH-FI-( )110 e)    After required emergency boration, perform the following:
: 1) Close ( )-CH-MOV-( )350
: 2) Transfer the in-service BATP to AUTO
: 3) Restore Charging flow control to normal NOTE: RO Emergency borates for 25 seconds which corresponds to ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.
RO      5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.
SRO      Notes Prior to Step 6:
* If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
* RCS Tave must be maintained less than or equal to 577&deg;F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
* I & C should be contacted to provide assistance with adjusting IRPIs.
RO      6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                    Event No.: 6                Page 45 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
RO      *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.
BOP      8. MONITOR STEAM DUMPS FOR PROPER OPERATION 0-AP-23.00 SRO      9. NOTIFY THE FOLLOWING:
* Energy Supply (MOC)
* Polishing Building
* Chemistry
* OMOC SRO      10. EVALUATE THE FOLLOWING:
* EPIP applicability
* VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.
[VPAP-2802 and EPIP are not applicable for this event.]
SRO      11. CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR When reactor power has decreased >15%, then chemistry will be notified.
END EVENT #6
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                    Event No.: 6                  Page 46 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
Time        Position                              Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO      1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
RO      2. Adjust 1-CH-YIC-1113 to desired total gallons RO      3. Adjust 1-CH-FC-1113A to desired flow rate.
RO      4. Place the MAKE-UP MOD SEL switch in the BORATE position.
RO      5. Place the MAKE MODE CNTRL switch in the START position.
RO      6. Check proper valve positions.
RO      7. Adjust boration rate using 1-CH-FC-1113A, as necessary.
RO      8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.
a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.
b) Enter N/A for the remaining steps in this Attachment.
Attachment 5 is on the next page RO      9. Check controllers for Primary Grade water and Boric Acid are set correctly.
RO      10. Place the MAKE-UP MODE SEL switch in the AUTO position.
RO      11. Place the MAKE-UP MODE CNTRL switch in the START position.
RO      12. Notify Shift Supervision of blender status.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 6                  Page 47 of 98 Event
 
== Description:==
Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.
Cue: By Evaluator.
Time        Position                              Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions
: 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
: 2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
: 3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
: 4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
: 5. Place the MAKE-UP MODE CNTRL switch in the START position.
: 6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
: 7. Check proper valve positions.
: 8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position
: 9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
: 10. Check or place the control switches in the AUTO position.
: 11. Check controllers for Primary Grade water and Boric Acid are set correctly.
: 12. Place the MAKE-UP MODE SEL switch in the AUTO position.
: 13. Place the MAKE-UP MODE CNTRL switch in the START position.
: 14. Notify Shift Supervision of blender status.
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 7                  Page 48 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
Time        Position                                  Applicants Action or Behavior Team      Diagnose the failure based on the following:
Alarms:
1E-B10, LOSS OF COOL FLOW PWR > P8, RED 1E-A3, RC LOOP 1C LO FLOW CH 1 1E-B3, RC LOOP 1C LO FLOW CH 2 1E-C3, RC LOOP 1C LO FLOW CH 3 Indications:
Low flow indication on C loop, CH-1, CH-2, CH-3 Reactor - Critical RO            Attempt to Trip the Reactor by pressing BB-1 and BB-2 Reactor Trip Pushbuttons.
GO TO FR-S.1 Critical Task: CT-1: DRP-049 E-12, Insert negative reactivity into the core by at least one of the following methods before completing the Immediate Action Steps of FR-S.1. Insert Control Rods in auto or manual within 30 seconds of the onset of the ATWS event.
Critical Step Start Time: ________________
1-FR-S.1 CAUTION: RCPs should not be tripped with Reactor power greater than 5%.
RO      [ 1]          VERIFY REACTOR TRIP:                Verify or place control rods in Auto.
a) Manually trip Reactor b) Check the following:
* All Rods On Bottom light - LIT
* Reactor Trip and Bypass Breakers -
OPEN
* Neutron Flux - DECREASING RO Identifies Reactor NOT Tripped, Performs RNO Action 1-FR-S.1 RO      [2]      MANUALLY TRIP THE TURBINE:
RO presses Both Turbine Trip Pushbuttons, Simultaneously.
* Verify all turbine stop valves - CLOSED
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 49 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-FR-S.1 RO      [3]      VERIFY CONTROL RODS - INSERTING IN AUTO AT GREATER THAN 48 STEPS /
MINUTE Critical Task Stop Time: ____________________
RO/BOP                Manually insert control rods.
When Rod Speed lowers, places Rods in MANUAL, and inserts Rods.
4    VERIFY AFW PUMPS RUNNING:
SRO a) MD AFW pumps - RUNNING BOP b) TD AFW pump - RUNNING IF NECESSARY BOP BOP check MD / TD AFW Pumps Running.
SRO 1-FR-S.1 SRO      5    INITIATE EMERGENCY BORATION OF RCS:
a) Verify CHG flow - GREATER THAN 75 GPM RO            Check CHG FLOW > 75 gpm.
b) Align boration path:
SRO                1) Put BATP in FAST RO            Places 1-CH-P-2A, A BAST Recirc Pump, in FAST.
SRO                2) Open 1-CH-MOV-1350 RO            Places control switch 1-CH-MOV-1350 in OPEN.
SRO                3) Verify emergency borate flow RO            Checks Flow on 1-CH-FI-1110 rises to 110 gpm.
SRO            c) Check PRZR pressure - LESS THAN 2335 PSIG RO            Checks RCS Pressure < 2335 psig using RCS NR or WR Pressure.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 50 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-FR-S.1 SRO      *6 CHECK IF SI INITIATED:                          GO TO Step 8 RO
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3
* A-F-4 Identifies SI NOT initiated, SRO GOES TO STEP 8.
1-FR-S.1 SRO      8          CHECK IF THE FOLLOWING TRIPS HAVE OCCURRED:
RO                  a) Reactor trip b) Turbine trip SRO            Directs BOP to contact Service Building Operator to locally open Unit 1 Reactor Trip Breakers.
NOTE: Two (2) Minutes will elapse from the time an Operator is dispatched to open the Reactor Trip breakers until the Simulator Operator Opens the breakers.
Based on Time Critical Operator Action.
1-FR-S.1 NOTE: If adverse CTMT conditions have been exceeded, the Gamma-Metrics Excore Neutron Monitor system (Source and Wide Ranges) should be used to monitor neutron flux for the duration of the event.
                        *9 CHECK REACTOR - SUBCRITICAL SRO a) Check power range channels - LESS THAN 5% [Gamma-Metrics Wide Range Power - LESS THAN 5%]
RO            Identifies Reactor Power < 5%.
b) Check Intermediate range channels - NEGATIVE STARTUP RATE [Gamma-Metrics Wide Range Power - DECREASING]
RO            Identifies negative SUR on IR Channels.
SRO            c) GO TO Step 18
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 51 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-FR-S.1 CAUTION:        Boration should be continued to obtain adequate shutdown margin during subsequent actions.
SRO      18 RETURN TO PROCEDURE AND STEP IN EFFECT SRO Announces Transition to E-0.
SRO            Directs Reactor Operator to perform E-0 Immediate Actions Steps.
1-E Reactor Trip or Safety Injection RO      [1] CHECK REACTOR TRIP:
a)  Manually trip reactor Pushes the reactor trip push buttons.
b)  Check the following:
* All Rods On Bottom light - LIT
* Reactor trip and bypass breakers - OPEN
* Neutron flux - DECREASING RO      [2] CHECK TURBINE TRIP:
RO            a)  Manually trip the turbine Pushes the turbine trip push buttons.
b)  Verify all turbine stop valves - CLOSED c)  Isolate reheaters by closing MSR steam supply SOV
* 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)
Identifies that Output Breakers did open RO      [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED
 
Appendix D                                  Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                    Page 52 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
[4] CHECK IF SI INITIATED:
RO            a)  Check if SI is actuated:
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3 SI INITIATED - TRAIN A
* A-F-4 SI INITIATED - TRAIN B RO      RO will determine that SI has NOT occurred and perform step 4a RNO actions:
4a RNO Check if SI is required or imminent as indicated by any of the following:
* Low PRZR pressure
* High CTMT pressure
* High steamline differential pressure
* High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.
RO reports Immediate Actions of E-0 are complete, SI not in service or required, and recommends transition to ES-0.1.
After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.
SRO      SRO will lead a brief using the brief checklist.
The RO will provide critical parameters using the Brief placard.
The BOP will provide critical parameters using the brief placard.
The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
The SRO will direct the BOP to perform ES-0.1, Transient AFW Control, Attachment 5 of ES-0.1, while the RO and SRO continue with ES-0.1.
Note: Attachment 5 of ES-0.1 is located at the End of this Section.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 53 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
1-ES-0.1 NOTE: Team may elect to secure the C RCP.
NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM SRO      GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.
                        *1 CHECK RCS TEMPERATURE CONTROL RO            a) Check RCPS - ANY RUNNING Reports all three RCPs running, C with abnormally low flow.
b) Monitor RCS Average Temperature
: 1) STABLE AT 547&deg;F OR RO            2) TRENDING TO 547&deg;F Reports RCS temperature stable at 547 &deg;F.
1-ES-0.1 SRO      2    CHECK FW STATUS:
a) Check RCS Average temperatures - LESS THAN 554&deg;F RO            Identifies RCS Temperature < 554 &deg;F b) Check Feed REG valves - CLOSED RO            Identifies all FRVs closed.
c) Close SG FW isolation MOVs
* 1-FW-MOV-154A
* 1-FW-MOV-154B
* 1-FW-MOV-154C RO/BOP          Close 1-FW-MOV-154 A / B / C d) Check AFW pumps - RUNNING
* Motor Driven AFW pumps
* TD AFW pump
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 54 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
BOP            Identifies MD / TD AFW pump running.
e) Check total AFW flow - GREATER THAN 540 GPM (350 GPM W/O RCPs)
BOP            Identifies AFW flow > 540 GPM (IAW band given by SRO) f) Check emergency buses - BOTH ENERGIZED RO            Identifies emergency buses energized.
g) Control feed flow to maintain narrow range level between 22% and 50%
BOP            Acknowledges direction to control AFW flow to obtain band.
1-ES-0.1 SRO      3        CHECK CHARGING IN SERVICE RO            Provides CH flow value and trend to SRO.
Note: If not already implemented, go to Event #8.
1-ES-0.1 SRO      4    CHECK CC SYSTEM STATUS:
a) Check SW to CC HXs - IN SERVICE RO            Identifies two (2) CC headers flowing to CC HXs.
b) Check CC pumps - AT LEAST ONE RUNNING RO            Identifies 1-CC-P-1A running.
1-ES-0.1 SRO      5    CHECK PRZR LEVEL CONTROL:
a) Check PRZR level - GREATER THAN 15%
RO            Reports PRZR level and trend to SRO.
b) Check letdown - IN SERVICE RO            Reports Letdown flow and trend to SRO.
 
Appendix D                                  Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 7                  Page 55 of 98 Event
 
== Description:==
RC Loop C Tc disc falls in, Valid First-out, FR-S.1.
Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.
Time        Position                                Applicants Action or Behavior ES-0.1, Attachment 5 BOP      1    Maintain minimum AFW flow of 540 gpm with RCP(s) in service until one SG Narrow Range level is greater than 12%.
ES-0.1, Attachment 5 BOP      2    Maintain minimum AFW flow of 350 gpm with NO RCPs running, until one SG Narrow Range level is greater than 12%.
Throttles AFW to band provided by SRO.
ES-0.1, Attachment 5 NOTE: AFW to idle loop(s) (RCP secured), should be throttled to prevent depressurization of the SG and subsequent Header / Line SI. AFW flow between approximately 60 gpm and 100 gpm should be adequate to prevent a Header / Line SI.
BOP      3    When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50% by throttling AFW Isolation MOVs:
* SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
* SG B, 1-FW-MOV-151C and 1-FW-MOV-151D
* SG C, 1-FW-MOV-151A and 1-FW-MOV-151B ES-0.1, Attachment 5 BOP      4. Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves:
Emergency Bus H deenergized:  1-FW-141  1-FW-156  1-FW-171 Emergency Bus J deenergized:  1-FW-140  1-FW-155  1-FW-170 Identifies Bus H and J not deenergized.
End EVENT #7
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                  Event No.: 8                      Page 56 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
Time        Position                              Applicants Action or Behavior Team      Identify Failure based on the following:
Alarms:
1B-F3, SFGDS AREA SUMP HI LEVEL 1C-B-8, PRZR LO PRESS 1C-D8, PRZR LO LEVEL 1D-E5, CHG PP TO REGEN HX HI-LO FLOW RMA-D6, VENT STACK #2PART ALERT/HI RMA-D7, VENT STACK #2 NORM RNG GAS ALERT/HI Indications:
Lowering PRZR Level Rising CH flow NOTE: SRO may direct manual safety injection and return to E-0 due to degrading plant conditions.
1-AP-16.00 SRO      Direct RO to perform the Immediate Actions of 1-AP-16.00.
1-AP-16.00 RO      NOTE:
* If SI Accumulators are isolated, 1-AP-16.01, SHUTDOWN LOCA, should be used for guidance.
* RCS average temperature has a direct impact on pressurizer level.
[1]      MAINTAIN PRZR LEVEL:
* Isolate Letdown Closes 1-CH-LCV-1460 A / B
* Control Charging flow Takes Manual control of 1-CH-FCV-1122 and raises CH Flow.
RO          Reports that CH flow at maximum value and PZR level decreasing.
SRO          Direct RO to Re-perform the Immediate Action Steps of E-0, and Safety Inject on Step 4.
1-E-0 RO      [1]      CHECK REACTOR TRIP:
1-E-0
 
Appendix D                              Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                    Event No.: 8                      Page 57 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
RO      [2]      CHECK TURBINE TRIP:
1-E-0
[3]      CHECK BOTH AC EMERGENCY BUSES - ENERGIZED 1-E-0 RO      [4]      CHECK IF SI INITIATED:
a) Check if SI is actuated:
* LHSI pumps - RUNNING
* SI annunciators - LIT
* A-F-3
* A-F-4 b) Manually initiate SI Report SI has been initiated, SI flow to the core, 1-E-0 Immediate Actions with SI complete.
1-E-0 SRO      Will Check off the Immediate Action Steps of 1-E-0.
SRO will conduct a commensurate Brief. Ensure the Team agrees that a LOCA outside of containment is in progress. Poll the Team as to any higher priority than continuing actions for a LOCA outside of containment.
SRO closes the brief.
Directs BOP to perform Attachments 1, 2, and 3 of 1-E-0. Attachment 1, 2, and 3 located in Event 9.
Continues with 1-E-0 with RO.
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                  Event No.: 8                    Page 58 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
Time        Position                                Applicants Action or Behavior 1-E-0 RO      Identify RCS Subcooling < 30 &deg;F and SI flow indicated to all three loops.
SRO      Using 1-E-0 Continuous Actions Page:
: 1. RCP TRIP CRITERIA Trip all RCPs if BOTH conditions listed below occur:
: a. Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS
: b. RCS Subcooling - LESS THAN 30&deg;F [85&deg;F]
RO          Checks RCP Trip Criteria exist.
SRO          Directs RO to Trip all RCPs.
: 2. MINIFLOW RECIRC CRITERIA
: a. CLOSED - When RCS pressure is less than 1275 psig [1475 psig] AND RCP Trip Criteria are met (RCPs OFF).
RO          Identifies Criteria are met.
SRO          Direct RO to close mini-flow recirc valves.
CT-2: Critical Task: E 1.2. Trip all RCPs within 5 minutes of reaching RCP Trip Criteria. (WOG E-1-C).
CT-2: Start Time: _________.        CT-2: Stop Time: _________.
Note: Examiner will be notified by Simulator Operator when RCS Subcooling reaches 35&deg;F and Lowering for CT-2 Monitoring.
SRO      *6. CHECK RCS AVERAGE TEMPERATURE
* STABLE AT 547&deg;F OR
* TRENDING TO 547&deg;F
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 8                    Page 59 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
SRO      7. CHECK PRZR PORVs AND SPRAY VALVES:
a) PRZR PORVs - CLOSED b) PRZR spray controls
* Demand at Zero (or)
* Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN NOTE: Seal injection flow should be maintained to all RCPs.
SRO      *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:
a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO      Two or three Charging pumps will be running and flowing to the RCS.
b) RCS subcooling - LESS THAN 30&deg;F [85&deg;F]
RCS subcooling will be less than 30 &deg;F c) Stop all RCPs d) RCS pressure - LESS THAN 1275 psig [1475 PSIG]
e) Close CHG pump miniflow recirc valves:
* 1-CH-MOV-1275A
* 1-CH-MOV-1275B
* 1-CH-MOV-1275C Mini-flow recirc valves closed.
SRO      9. CHECK IF SGs ARE NOT FAULTED:
* Check pressures in all SGs a)  STABLE OR INCREASING AND b)  GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.
 
Appendix D                                Required Operator Actions                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 8  Page 60 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
SRO      10. CHECK IF SG TUBES ARE NOT RUPTURED:
* Condenser air ejector radiation - NORMAL
* SG blowdown radiation - NORMAL
* SG MS radiation - NORMAL
* TD AFW pump exhaust radiation - NORMAL
* SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER 11 CHECK RCS - INTACT INSIDE CTMT SRO
* CTMT radiation - NORMAL
* CTMT pressure - NORMAL
* CTMT RS sump level - NORMAL Reports RCS intact in side CTMT.
RO SRO      12 CHECK RCS - HAS BEEN MAINTAINED INTACT OUTSIDE CTMT a) Radiation Monitors - NORMAL
* MGPI vent-vent
* Auxiliary Building Control Area RO          Reports MGPI Vent-Vent in Alarm b) Sump annunciators - NOT LIT
* VSP-F-4
* B-D-1
* B-D-2
* B-F-3 Step 12 RNO Determine cause of abnormal conditions.
IF the cause is a loss of RCS inventory outside CTMT, THEN GO TO 1-ECA-1.2, LOCA OUTSIDE CONTAINMENT.
RO          Reports conditions caused by LOCA outside CTMT SRO          Transitions to ECA-1.2.
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 8                        Page 61 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
Time        Position                                Applicants Action or Behavior 1-ECA-1.2 SRO          Performs a commensurate brief. Ensures Team assessment confirms event in progress is a LOCA outside CTMT. Polls Team concerning any abnormal condition that needs to be addresses of a higher priority than isolating the LOCA outside CTMT. When any issues are addressed, SRO closes brief and continues with ECA-1.2.
1-ECA-1.2 CAUTION: Depending on break location, higher than normal dose levels should be expected in the Auxiliary Building and the Safeguards after a LOCA outside CTMT.
SRO      1    VERIFY PROPER VALVE ALIGNMENT:
a) Locally unlock and close the following breakers:
* 1H1-2N 8A for 1-SI-MOV-1890A
* 1J1-2E 8B for 1-SI-MOV-1890B
* 1H1-2N 9A for 1-SI-MOV-1890C Directs the BOP to contact the Shift Manager/Desk SRO and have an operator briefed and dispatched to remove tags and close the breakers for 1-SI-MOV-1890 A / B / C.
NOTE: Booth will time compress this action when SM/Desk SRO contacted.
b) LHSI to hot legs - CLOSED
* 1-SI-MOV-1890A
* 1-SI-MOV-1890B When Valves Energized, the valves indicate closed.
c) SI accumulator test valves - CLOSED
* HCV-SI-1850A
* HCV-SI-1850B
* HCV-SI-1850C
* HCV-SI-1850D
* HCV-SI-1850E
* HCV-SI-1850F When Checked, Valves Indicate closed.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1      Scenario No.: 4                  Event No.: 8                    Page 62 of 98 Event
 
== Description:==
LOCA outside of Containment upstream 1-SI-MOV-1890C.
Cue: By Evaluator.
1-ECA-1.2 NOTE: The SRO is expected to have a Focus Brief prior to this step. The SRO will bring the BOP into the discussion concerning the expected response of the RCS SRO          when 1-SI-MOV-1890C is closed. If closure of this valves isolates the RCS break, RCS pressure and LHSI flow is expected to increase. If the break remains isolated, RCS pressure and LHSI flow will remain the same or decrease. The SRO will complete the brief and continue ECA-1.2.
2  TRY TO IDENTIFY AND ISOLATE BREAK:
a) Close LHSI to cold legs RO
* 1-SI-MOV-1890C Team          Shortly after closure of 1-SI-MOV-1890C, the Team should identify that RCS pressure and LHSI flow is increasing.
Critical Task:
CT-3: WOG ECA-1.2A, Isolate the LOCA outside containment before transition out of ECA-1.2, or cavitation of any LHSI pump. SPS- Isolate LOCA outside SRO      containment before transition out of ECA-1.2 (PSA).
RO          b) Check RCS pressure - INCREASING RO will identify RCS increasing.
c) Place LHSI pumps in PTL RO          Places LHSI pumps in PTL.
SRO          d) Close LHSI pump suctions from RWST
* 1-SI-MOV-1862A
* 1-SI-MOV-1862B Closes 1-SI-MOV-1862A / B.
e) GO TO 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT SRO Transitions to 1-E-1.
CRITICAL TASK STOP TIME ____________________
END EVENT 8                        END of Scenario 4
 
Appendix D                                Required Operator Actions                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                Event No.: 9          Page 63 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
Time        Position                              Applicants Action or Behavior ATTACHMENT 1 OF E-0 BOP      1. CHECK FW ISOLATION:
* Feed pump discharge MOVs - CLOSED
* 1-FW-MOV-150A
* 1-FW-MOV-150B
* MFW pumps - TRIPPED
* Feed REG valves - CLOSED
* SG FW bypass flow valves - DEMAND AT ZERO
* SG blowdown TVs - CLOSED BOP      2. CHECK CTMT ISOLATION PHASE I:
* Phase I TVs - CLOSED Identifies 1-CV-TV-150A, 1-CH-TV-1204A OPEN, Closes valves
* 1-CH-MOV-1381 - CLOSED
* 1-SV-TV-102A - CLOSED
* PAM isolation valves - CLOSED
* 1-DA-TV-103A
* 1-DA-TV-103B BOP      3. CHECK AFW PUMPS RUNNING:
a)  MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY
 
Appendix D                                Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                      Event No.: 9            Page 64 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
Attachment 1 of E-0 BOP      4. CHECK SI PUMPS RUNNING:
* CHG pumps - RUNNING
* LHSI pumps - RUNNING Manually Starts 1-SI-P-1A.
BOP      5. CHECK CHG PUMP AUXILIARIES:
* CHG pump CC pump - RUNNING
* CHG pump SW pump - RUNNING
: 6. CHECK INTAKE CANAL:
BOP
* Level - GREATER THAN 24 FT
* Level - BEING MAINTAINED BY CIRC WATER PUMPS
: 7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:
a)  Check if ANY of the following annunciators - HAVE BEEN LIT
* E-F-10 (High Steam Flow SI)
* B-C-4 (Hi Hi CLS Train A)
BOP
* B-C-5 (Hi Hi CLS Train B)
Identifies annunciators not lit and goes to step 8.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 9                Page 65 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
BOP      *8 CHECK IF CS REQUIRED:
a)  CTMT pressure - HAS EXCEEDED 23 PSIA 8, a) RNO          Do the following:
: 1) IF CTMT pressure has exceeded 17.7 psia, THEN check or align the following valves:
Identifies CTMT pressure remains at normal pressure
: 2) GO TO Step 10.
Attachment 1 of E-0 BOP      *10. BLOCK LOW PRZR PRESS SI SIGNAL:
a)    Check PRZR pressure - LESS THAN 2000 psig b)    Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c)    Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.
BOP      *11. BLOCK LOW TAVE SI SIGNAL:
Step may not be performed at this time (if Tave is greater than 543&deg;F).
a)  Check RCS Tave - LESS THAN 543&deg;F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c)  Verify Permissive Status light F LIT
 
Appendix D                                Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 9                Page 66 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
NOTE:
* CHG pumps should be run in the following order of priority: C, B, A.
* Subsequent SI signals may be reset by re-performing Step 12.
BOP      12. CHECK SI FLOW:
a)  HHSI to cold legs - FLOW INDICATED
* 1-SI-FI-1961 (NQ)
* 1-SI-FI-1962 (NQ)
* 1-SI-FI-1963 (NQ)
* 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c)  Reset SI.
d) Stop one CHG pump and out in AUTO Attachment 1 of E-0 e)  RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:
: 1) Verify reset or reset SI.
: 2) Stop one LHSI pump and put in AUTO.
BOP      13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]
BOP      14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.
BOP      15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next Page of this guide)
Depending on timing, this attachment may have already been completed.
 
Appendix D                                Required Operator Actions                                    Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                    Event No.: 9                      Page 67 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
BOP      16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2.
Unit 2 Operator will state that Unit 2 is at 100% power (if asked)
Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 9                    Page 68 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
Time        Position                              Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 BOP      NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.
ATTACHMENT 2 of 1-E-0 BOP      1. Check opened or open CHG pump suction from RWST MOVs.
* 1-CH-MOV-1115B
* 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 BOP      2. Check closed or close CHG pump suction from VCT MOVs.
* 1-CH-MOV-1115C
* 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 BOP      3. Check running or start at least two CHG pumps. (listed in preferred order)
* 1-CH-P-1C
* 1-CH-P-1B
* 1-CH-P-1A ATTACHMENT 2 of 1-E-0 BOP      4. Check opened or open HHSI to cold legs MOVs.
* 1-SI-MOV-1867C
* 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 BOP      5  Check closed or close CHG line isolation MOVs.
* 1-CH-MOV-1289A
* 1-CH-MOV-1289B
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 9                    Page 69 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
ATTACHMENT 2 of 1-E-0 BOP      6. Check closed or close Letdown orifice isolation valves.
* 1-CH-HCV-1200A
* 1-CH-HCV-1200B
* 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 BOP      7. Check opened or open LHSI suction from RWST MOVs.
* 1-SI-MOV-1862A
* 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 BOP      8. Check opened or open LHSI to cold legs MOVs.
* 1-SI-MOV-1864A
* 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 BOP      9. Check running or start at least one LHSI pump.
* 1-SI-P-1A
* 1-SI-P-1B ATTACHMENT 2 of 1-E-0 BOP      10. Check High Head SI flow to cold legs indicated.
* 1-SI-FI-1961
* 1-SI-FI-1962
* 1-SI-FI-1963
* 1-SI-FI-1943 or 1-SI-FI-1943A ATTACHMENT 2 of 1-E-0 BOP      11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.
* Alternate SI to Cold legs
* Hot leg injection End of Event 9 -. End of Scenario 4
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 70 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 71 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 72 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 73 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                              Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4                  Event No.: 9                      Page 74 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
Unit 2 will prompt BOP: MCR Boundary DP is the same as DP indicated on Unit 2 Ventilation Panel.
Unit 2 will prompt BOP: Unit 2 remains operating at 100%
power.
Unit 2 will assume responsibility for the Attachment action from this point.
 
Appendix D                              Required Operator Actions                      Form ES-D-2 Op-Test No.: Surry 2014-1        Scenario No.: 4              Event No.: 9            Page 75 of 98 Event
 
== Description:==
BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.
Cue: Active Failures.
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 76 of 98 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                        Required Operator Actions            Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1              Event No.: N/A Page 77 of 98 FOLDOUT PAGES FOR REFERENCED PROCEDURES
 
Appendix D                                  Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                                Page 78 of 98 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:
Recall IC -264 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.
Ensure the Delta T Selector Switch is in the Channel II Position.
Ensure PRZR Level Recorder on Channel II.
Open the monitor window and add the following points to it:
* asp_ao_off
* CC_579 set at 0.38 Enter the following MALFUNCTIONS:
Trigger Malfunction                Delay    Ramp        Trigger  Value  Final      Type (Auto or Manual)
RC4802 PRZR PRESS CONT                    10        10            1    0        1          MAN XMTR FAILURE (445)
MS1305 SG B STM PRESSURE                  10        0            3    0        1          MAN TRNSMTR MS-PT-485 FAILURE CH2101 VCT LEVEL                          10        0            5    0        1          MAN TRANMITTER LT-1115 FAILS CC0302 CC PUMP 1-CC-P-1B                  10        0            7  FALSE    TRUE          MAN OVERCURRENT TRIP CC0802 CC-P-1B BKR 15J10                    0        0            7  FALSE    TRUE          MAN MECHANICALLY STUCK CLOSED RD1236 DROPPED RCCA, M-4,                  10        0            9  FALSE    TRUE          MAN CONTROL BANK C RD17 ATWS, WITH MANUAL RX                  0        0          11  FALSE    TRUE          MAN TRIP PB DEFEATED SI1502 SI COLD LEG HDR LEAK                10        0          13    0        40          MAN UPSTRM MOV-SI-890C SI1603 FAIL CHECK VALVES SI-              10        0          13  FALSE    TRUE          MAN 85 SI1606 FAIL CHECK VALVE SI-                10        0          13  FALSE    TRUE          MAN 243 LOOP C (LHSI)
SI2402 SI RELAY SI2A FAILS TO              0        0          30  FALSE    TRUE          MAN ACTUATE SI2405 SI RELAY SI5A FAILS TO              0        0          30  FALSE    TRUE          MAN ACTUATE CC1801 DISABLE CCP1A AUTO                  0        0          30  FALSE    TRUE          MAN START Enter the following Remote Functions:
 
Appendix D                        Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1              Scenario No.: 4                            Page 79 of 98 SIMULATOR OPERATORS GUIDE Remotes                            Set Condition                          Trigger SW_15J9_RF 4KV Stub                      TRIP, 20 Sec TD                            7 Bus BKR 15J9 Control Switch RCMOV595 RC-MOV-                  100 to 30, 0 Ramp, 10 Sec TD                    11 595 C Loop Cold Leg Isol SIMOV890A_BKR SI-                            CLOSED                                21 MOV-1890A LHSI To HOT Legs SIMOV890B_BKR SI-                            CLOSED                                22 MOV-1890B LHSI To HOT Legs SIMOV890C_BKR SI-                            CLOSED                                23 MOV-1890C LHSI To Cold Legs RX_RTA_OPEN                                TRUE                                16 RX_RTB_OPEN                                TRUE                                17 AAC_SMS_MODE OFF                                OFF                                30 AAC DG LOCAL MODE SWITCH POSITION EL12, SW_25J10_RF, Bkr                          PTL                                30 25J10 Control Switch, 1-CC-P-1D TRIGGER                  TYPE                                DESCRIPTION 1                  MAN      Przr Press Cont Xmtr Failure (445) Fails High 3                  MAN      SG B Stm Pressure Trnsmtr MS-FT-485 FAILS High 5                  MAN      VCT Level Transmitter LT-1115 Fails High OVERCURRENT Trip 1-CC-P-1B, BREAKER Stuck Closed, 15J9 7                  MAN Breaker Trips Open
 
Appendix D                    Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1            Scenario No.: 4                                Page 80 of 98 SIMULATOR OPERATORS GUIDE TRIGGER              TYPE                            DESCRIPTION 9                  MAN      Dropped RCCA, M-4, Control Bank C 11                  MAN      RC-MOV-595 C Loop Cold Leg Isol Disc Falls Into Flow Stream 11                  MAN      ATWS, WITH MANUAL RX TRIP PB DEFEATED SI Cold Leg HDR Leak Upstrm MOV-SI-890C, With Check Valves 13                  MAN Stuck Open
 
Appendix D                                Required Operator Actions                                  Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                                    Page 81 of 98 SIMULATOR OPERATORS GUIDE Verify the following control room setup:
Place the simulator in RUN and verify normal 100% power operation indications.
Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:
Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).
Verify Ovation System operating.
Reset ICCMs.
Verify Component Switch Flags.
Verify Brass Caps properly placed.
Verify SG PORVs set for 1035 psig.
Verify Rod Control Group Step Counters indicate properly.
Verify Ovation CRT display.
Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)
Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:
AP-53.00            AP-1.00            AP-23.00                    AP-16.00 E-0                  ECA-1.2            1-OPT-RX-001                  AP-1.00, Att 6 (3)
OP-CH-007                                Reactivity Sheet OP-ZZ-002 Verify Reactivity Placard is current.
Verify ALL PINK MAGNETS are accounted for.
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                                  Page 82 of 98 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.
Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.
If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.
In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.
Assign operating positions.
Ask for and answer questions.
 
Appendix D                                Required Operator Actions                                Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                                    Page 83 of 98 SIMULATOR OPERATORS GUIDE Conduct shift turnover:
The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.
Unit conditions have been stable at approximately 100% power since the last refueling outage.
All systems and crossties are operable with the following exception:
* AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.
IAW TRM 3.7.9.A, 72 hour clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
* 1-CC-P-1D is tagged out for maintenance. 72 hour and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
Unit #2 is at 100% power with all systems and crossties operable.
Shift orders are to maintain 100% power on Unit #1.
The last shift performed two 35 gallon dilutions followed by a manual makeup for training.
A BAST at 8.0 W/%.
PSA is Green.
When the team has accepted the shift, proceed to the Session Conduct Section.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 4                                Page 84 of 98 SIMULATOR OPERATORS GUIDE Session Conduct:
* Ensure conditions in Simulator Set-up are established.
* Ensure Trigger 30 is active prior to team entering the simulator.
* Verify Exam Security has been established and ASP_AO_OFF = True.
EVENT 1          Deleted EVENT 2          1-RC-PT-1145 Fails High, 1-AP-31.00/0-AP-53.00 When cued by examiner, implement Trigger #1.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of 1-RC-PT-1445. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00/AP-31.00.
* If contacted, acknowledge review of VPAP-2802 and EPIP SU6.1 review required.
* If contacted, will take responsibility for writing the CR.
STA:
* If contacted, will acknowledge the failure of 1-RC-PT-1445. The individual(s) contacted will also acknowledge (but not confirm/deny) any TS LCOs.
* If asked, the STA will review VPAP-2802, TRM Section 3.3, and SU6.1 review complete and discussed with Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Field Operators:
No feedback required for this failure.
 
Appendix D                              Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                              Page 85 of 98 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:
* If contacted, will acknowledge instrumentation failure and commence investigations.
Unit 2 Operator:
If Contacted, acknowledge the failure of 1-RC-PT-1445.
Role play as other individuals as needed.
 
Appendix D                                  Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                              Page 86 of 98 SIMULATOR OPERATORS GUIDE EVENT 3          Steam Pressure Fails High, B SG. 0-AP-53.00.
When cued by examiner, implement Trigger #3.
Operations Supervisor/Management:
* If contacted, will acknowledge that Failure of 1MS-PT-1485, Channel III, B SG, Steam Pressure. The individual(s) contacted will also acknowledge any TS LCOs.
* If asked, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into AP-53.00.
STA:
* If contacted, will acknowledge the Failure of 1MS-PT-1485, Channel III, B SG, Steam Pressure. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
* When asked, STA reports the failed channel is a RG 1.97 variable.
* When asked, SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
* When contacted, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Field Operators:
No feedback required.
 
Appendix D                            Required Operator Actions                        Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                            Page 87 of 98 SIMULATOR OPERATORS GUIDE Maintenance/ Work Week Coordinator:
* If contacted, will have I&C brief on placing the failed channel in trip.
Unit 2:
* If contacted, will acknowledge Failure of 1-MS-PT-1485, Channel III, B SG, Steam Pressure.
Role-play as other individuals as needed.
 
Appendix D                                Required Operator Actions                          Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                              Page 88 of 98 SIMULATOR OPERATORS GUIDE EVENT 4          Failure of VCT Level Channel LT-1115 High. 0-AP-53.00.
When Evaluator ready: Implement Trigger #5.
Operations Supervisor/Management:
* If contacted, will acknowledge the failure of 1-CH-LT-1115 high.
STA:
* If contacted, will acknowledge the failure of 1-CH-LT-1115 high.
* If asked, The STA will report that the failed channel is a Reg. Guide 1.97 variable.
* If asked, SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
* After directed, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
* If contacted, will take responsibility for writing the CR.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
Maintenance/ Work Week Coordinator:
* If contacted, will acknowledge the failure and commence investigations.
Field Operators: (Wait 4 minutes from time of direction to report).
* If contacted, to check the status of 1-CH-LT-1115 locally, report no obvious abnormal condition with the transmitter.
Unit 2:
* If contacted, will acknowledge the failure of 1-CVH-LT-1115 high.
Role-play as other individuals as needed.
 
Appendix D                              Required Operator Actions                              Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 4                                  Page 89 of 98 SIMULATOR OPERATORS GUIDE EVENT 5          Overcurrent trip 1-CC-P-1B with breaker stuck Shut, 15J9 trip open.
When cued by examiner, implement Trigger #7. If the Team decides to trip the reactor on this event, consult the examiner and actuate Trigger #11 when first Reactor Trip button pressed.
Operations Supervisor/Management:
* If contacted, will acknowledge the fault on of 1-CC-P-1B, the failure of the breaker to open, and the trip of breaker 15J9. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.
* If contacted, will take responsibility for writing the CR.
* If contacted, will acknowledge entry into ARP.
Unit 2 Operator:
* If asked: 1-CC-P-1C is running, and CC cross-ties are open.
STA:
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, will acknowledge any TS information.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
* If asked, The STA will report that TRM review is complete and TRM requirements have been discussed with the Shift Manager.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                                Page 90 of 98 SIMULATOR OPERATORS GUIDE Field Operator:
* When contacted, report that 15J10 breaker for 1-CC-P-1B has a timed overcurrent drop on A phase. 1-CC-P-1A breaker, 15H10, has no abnormalities.
* When contacted, report that 15J9 breaker has a timed overcurrent drop on all three phases.
* If contacted, report as Aux Bldg Operator that there are no abnormalities locally with 1-CC-P-1A and 1-CC-P-1B.
Role play as other individuals as needed.
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                    Scenario No.: 4                                Page 91 of 98 SIMULATOR OPERATORS GUIDE EVENT 6                Dropped Rod C Bank Group 1. 1-AP-1.00, 0-AP-23.00.
When Examiner ready, Actuate Trigger #9.
Operations Supervisor/Management:
* If contacted, will acknowledge the dropped rod and the need to ramp at 1%/minute to 70 - 74%
power.
* If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC, the Shift Manager will direct a 1%/minute ramp rate.
* If contacted, will take responsibility for writing the WR and CR.
STA:
* If asked, the STA will perform a shutdown margin calculation.
* If asked, the STA will perform a QPTR. See AP-1.00, Attachment 6, attached.
* If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
* If asked, the STA will acknowledge the need to borate and use rods (will acknowledge the team review of pre-planned reactivity plans and OP-RX-010, if performed). If asked to perform the OP-RX-010 review, the STA will state that he is not able to at this time.
* When contacted, SRO directs STA to review VPAP-2802. The STA reports that review is complete and has been discussed with the Shift Manager.
Unit Two:
* If contacted, all conditions on U2 are normal.
Field Operators:
 
Appendix D                            Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                  Scenario No.: 4                                  Page 92 of 98 SIMULATOR OPERATORS GUIDE
* If contacted, Will perform actions as directed (i.e., may be asked to read bank overlap counter-RD 2).
I&C:
* If requested by MCR to reset the bank overlap - use RD2 drawing to set as requested.
Maintenance/Work Week Coordinator:
* If contacted, will acknowledge the failure and commence investigations.
Role play as other individuals as needed.
 
Appendix D                              Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 4                                  Page 93 of 98 SIMULATOR OPERATORS GUIDE EVENT 7          RC Loop C disc falls, Valid First-Out, FR-S.1 When Evaluator has seen a sufficient change in power, Actuate Trigger #11.
Operations Supervisor/Management:
* If contacted, will acknowledge the reactor trip failure and entry into FR-S.1, E-0, and ES-0.1.
* If contacted, will acknowledge direction for local opening of reactor trip breakers. After two (2) minutes, use Trigger 16 (A RT breaker) and Trigger 17 (B RT breaker).
* If contacted, will take responsibility for writing the WR and CR.
* If contacted, SRO requests that tags be cleared and breakers closed for 1-SI-MOV-1890A / B /
C, use Triggers 21, 22, and 23 to perform close the breakers for the MOVs.
Field Operators:
* If directed, field operators will acknowledge direction for local opening of reactor trip breakers.
After two (2) minutes, use Trigger 16 (A RT breaker) and Trigger 17 (B RT breaker).
* If contacted, SRO requests that tags be cleared and breakers closed for 1-SI-MOV-1890A / B /
C, use Triggers 21, 22, and 23 to perform close the breakers for the MOVs.
Role play as other individuals as needed.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                        Scenario No.: 4                                Page 94 of 98 SIMULATOR OPERATORS GUIDE EVENT 8          LOCA Outside Containment Upstream 1-SI-MOV-1890C.
When Evaluator is ready, implement Trigger # 13.
When RCS Subcooling reaches 35&deg;F and lowering, notify the Lead Examiner, for monitoring CT-2.
1-SI-MOV-1890A / B/ C can be energized when directed using Triggers 21, 22, and 23. 2 minutes to transit to valve, when directed; wait 1 minute between Triggers to energize MOV.
Operations Supervisor/Management:
* If contacted, will acknowledge the reactor trip failure, completion of FR-S.1, completion of E-0 Immediate Actions, and transition to ES-0.1.
* If contacted, will take responsibility for writing the WR and CR.
Unit 2 Operator:
* If directed to respond to radiation alarms on the radiation alarm panel, silence the alarms when and report the alarm to the Unit 1 SRO.
* When FP alarms occur, acknowledge alarms.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
* When contacted by BOP, Chilled Water has been throttled IAW the Caution prior to Step 10 of Attachment 3. MCR boundary D/P indicates the same value as Unit 2 ventilation panel D/P gauges. Unit 2 will assume responsibility for Attachment 3 when last page is reached (SFP monitoring).
* When directed, to read Unit 1 A/E, Blowdown, Main Steam and TDAFW radiation, report as pre-event, no trend.
Field Operators: Perform with a two minute delay to transit to the valve breaker; 1 minute between Triggers to energize MOVs.
* If directed, field operators will remove tags and close breakers for 1-SI-MOV-1890A / B / C.
 
Appendix D                                Required Operator Actions                            Form ES-D-2 Op-Test No.: Surry 2014-1                      Scenario No.: 4                                Page 95 of 98 SIMULATOR OPERATORS GUIDE Role play as other individuals as needed.
EVENT 9          BOP Failures.
Operations Supervisor/Management:
* If contacted, will take responsibility for writing the WR and CR.
Unit 2 Operator:
* When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
* If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
* When directed, to read Unit 1 A/E, Blowdown, Main Steam and TDAFW radiation, report as pre-event, no trend.
Field Operators: Role play as necessary to support the Teams actions.
The scenario will end upon entering 1-E-1 or at the lead examiners discretion}}

Latest revision as of 04:57, 5 February 2020

301 Section 10
ML16089A389
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/22/2016
From:
Division of Nuclear Materials Safety II
To:
Virginia Electric & Power Co (VEPCO)
References
Download: ML16089A389 (293)
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Text

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Facility: Surry Power Station Scenario No.: 1 Op-Test No.: 2014-001 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Unit 1 and 2 at 100% power; MOL.

  • A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Turnover: The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Event Malf. Event Event No. No. Type* Description 1 RCMOV_5 N BOP Test Cycle Pressurizer PORV, Block Valve breaker will trip when re-35_BKR, N SRO opened Open TS SRO 2 RC4903, I RO PRZR Level Transmitter Fails Low, requiring IAs of AP-53.00 to control

-.2 DEG CH flow.

TS SRO 3 FW1803, I BOP Feed Flow Channel fails high requiring manual FRV control, IAs of AP-

+1 DEG 53.00 TS SRO 4 SD0201 C BOP Loss of High Pressure Drain, AP-18.00 5 R RO R SRO Ramp to 75% power IAW AP-23.00 N - BOP C RO 6 RC2402 C SRO Steam Generator Tube Leak B SG at approximately 74 gpm. AP-16.00, E0.

Auto Actions of Air Ejector Hi Rad do not function, BOP manually aligns.

AS02, C - BOP A/E RM Annunciator Response Procedure.

AS05 RC5601 Reactor Coolant Pumps trip on electrical power swap to Reserve Station RC5602 Service Transformers (30 seconds after reactor trip).

RC5603 7 RC2402, M - All SGTL B SG escalates to Design Basis rate (800 gpm) in ES-0.1. AP-79%, 710 16.00, Manual SI, E-0, E-3.

gpm, 60 sec ramp 8 PCV455C M - All PZR PORV 1-RC-1455C will not open when switch placed in open - Go

_OPEN, to ECA-3.3 OFF

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 9 SI2409 C BOP BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-SI2505 100A/B not close.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Event 1: PT-18.6 I, PZR Block Valve Stroke Test. (N- BOP/SRO)

The Team will pre-brief this evolution prior to entering the Simulator. Upon entry of the Team to the Simulator, the Scenario brief will be given, Questions answered, and the Team allowed ~ 5 minutes to become acclimated to the Simulator Environment.

When the BOP closes 1-RC-MOV-1535, 1-RC-PCV-1456 block valve, and attempts to re-open 1-RC-MOV-1535, a series of triggers actuate to trip the power supply breaker to 1-RC-MOV 1535.

Verifiable Action(s):

1) BOP will close 1-RC-MOV-1535 and time the stroke.
2) RO/BOP will place the 1-RC-MOV-1456 PORV control switch in the close position following Tech Spec review.

Technical Specifications:

The SRO will review Tech Specs (3.1.A.6.d) and determine a one (1) hour clock exists to place 1-RC-PCV-1456 in manual (switch to close); and a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to return the block valve to an OPERABLE status, or be in HSD in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and RCS temperature <350°F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

This Event sets up entry into ECA-3.3, SGTR without Pressure Control; Major Event later in the Scenario.

Event 2: PRZR level Upper Channel Fails Low (-.2 DEG) PRZR level on selected Upper Channel fails to ~34%. (I - RO, TS - SRO). ARP 1C-D8, PRZR LO Level.

The RO will diagnose the failure based on CH to Regen HX Hi/Low flow alarm (Annunciator 1D-E5) or identification of CH flow increasing and PZR level Channel III decreasing.

Verifiable Actions(s):

1) The RO will place CH flow in Manual and control PRZR level at setpoint IAW AP-53.00, Loss of Vital Instrumentation/Controls.
2) BOP will select an operable channel on the pressurizer level recorder.
3) The RO will defeat the failed channel IAW AP-53.00, and return CH flow to automatic when normal PRZR level restored.

Technical Specifications:

1) The SRO will Review Tech Specs and determine a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to place the Failed Channel in trip (TS 3.7, Table 3.7-1, item 9 (Pressurizer High Water Level), Operator Action 7. With the number of OPERABLE Channels less than the Total number of channels; place the failed channel in trip in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, allowable to bypass the channel for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance, if requirements not met reduce power to less than P-7 (10%) within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1

2) TS-Table 3.7-6, item 14, Pressurizer Level, 2 Channels required, condition met.

(Referred by check of CEP 99-0029, RG 1.97).

TRM Actions:

1) TRM section 3.3.2, Table 3.3.2-1, Pressurizer Level Channel 1-RC-LI-1461.

Condition A applies, Implement a Fire Watch in cable vault and tunnel and the emergency switchgear room of the affected Unit (Unit 1) IAW TRM Section 5.2 (Hourly) within 14 days and restore the failed channel in 60 days. (Usually an STA Function to identify, may be performed as a follow-up).

Reg. Guide 1.97:

1) CEP-99-0029, Reg. Guide 1.97 Operability/Functionality, Reportability and Alternate Indications, Attachment 1, Post Accident Monitoring Equipment, A-13 variable, 2 channels required, Condition is met. Refers to TS Table 3.7-6. (Usually an STA Function to identify - could be covered as a follow-up).

Event 3: Feed Flow Channel III, B SG fails high. (I - BOP, TS - SRO)

BOP will diagnose the failure based upon alarms and indications received and take the Immediate Actions of AP-53.00. The Team will implement AP-53.00, Loss of Vital Instrumentation/Controls and shift SGWLC input to Channel IV for B SG. The BOP will restore B SG NR level to program.

Verifiable Action(s):

1) BOP will place the B FRV in manual and regain control of B SG NR level.
2) RO will defeat the failed channel.
3) BOP will return the B FRV to automatic.

Technical Specifications:

Tech Spec Table 3.7-1

1) Item 17, Low steam generator water level with steam flow/feedwater flow mismatch, Operator Action 6.
2) With the number of OPERABLE Channels less than the TOTAL number of channels, operation may continue if the failed channel is placed in trip in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the channel may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance, if conditions not satisfied in the time permitted, be in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Technical Requirements Manual. Reg. Guide 1.97:

1) The TRM Section 3.3, Appendix R Instrumentation unaffected; and RG 1.97 requires one channel of Feed Flow indication per steam generator and no further actions are required are by this failure.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Event #4: Loss of the HP Heater Drain Pump (1-SD-P-1A) (C - BOP)

The BOP will diagnose the failure based upon alarms and indication received. The Team will initiate AP-18.00, Loss of HP Heater Drain Pump/ Network 90 failure Verifiable Actions:

1) The BOP will place the tripped High Pressure Drain pump control switch in PTL.
2) Reduce Turbine Load as necessary to maintain reactor power less than 100% using the valve position limiter or using Turbine Manual (approximately 50 MW reduction required).

Event 5: Power Reduction to less than 75% power using AP-23.00, Rapid Load Reduction. (R - RO, R - SRO, N - BOP)

The SRO will lead a Team Brief where the reactivity plan will be discussed to reduce reactor power to less than 75% power in order to restore the Polishing Building to service. The RO and SRO will be credited with a Reactivity Manipulation and the BOP with a Normal Evolution.

Verifiable Action(s):

1) RO will manipulate control rods to control delta flux and/or Tave.
2) RO will manipulate CVCS controls to Emergency Borate.
3) RO will manipulate CVCS control to establish a normal boration to assist in Tave control.
4) BOP will manipulate Turbine Controls to establish power reduction.

Event #6: Steam Generator Tube Leak B Steam Generator. Failure of Auto actions of A/E RM. Trip of all RCPs on electrical transfer to RSSTs. (C - RO, C - BOP)

When the Evaluation Team is satisfied with the Reactivity manipulation, the event will be triggered. A SGTL of approximately 74 gpm will initiate requiring the RO to perform the actions of 1-AP-16.00 to quantify the leakrate. The A/E RM will go into High alarm due to the primary to secondary leakage; the BOP will manually align A/E discharge to containment IAW A/E RM ARP. When the RCS leakrate is identified as greater than 50 gpm, the RO will trip the reactor and perform the Immediate Actions of 1-E-0.

Verifiable Actions:

1) RO will isolate LD flow and place charging flow in manual to quantify leakrate.
2) BOP will respond to failure of auto actions on A.E RM High alarm by swapping A/E discharge to containment.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Event #7: SGTR in B SG, approximately 710 gpm. (M - ALL)

When the evaluation Team is ready, a SGTR in the B SG will be implemented. The RO will re-assess RCS leakage in response to alarms and indications received. The RO will determine that RCS leakage exceeds the capacity of a single CH pump, and the Team will return to E-0 and manually initiate SI.

The SRO will perform a commensurate brief and continue with E-0. While the RO and SRO continue with E-0, the BOP will be directed to perform E-0 Attachments 1 through 3.

Verifiable Actions:

1) RO will increase CH flow in manual per Immediate Action Steps of 1-AP-16.00, Excessive RCS Leakage to determine if RCS leakage is greater than the capacity of a single CH pump.
2) RO re-perform High Level Steps of E-0, and manually Safety Inject on Step 4 of 1-E-0.
3) BOP will perform actions of Attachments 1 through 3 of E-0. BOP Failures in E-0 Attachments: 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not auto close, 1-VS-MOD-103A not auto close, 1-MS-TV-109 and 1-DA-TV-100A/B will not auto close (Listed as Event 9).

Critical Task:

1) SPS E G: LHSI pumps will not undergo significant degradation while operating under very low flow conditions during the onset of a SBLOCA (implicit in SBLOCA analysis). Operators will secure one LHSI pump as directed by Emergency Operating Procedures to prevent pump damage while on recirculation. Secure one LHSI pump within 30 minutes of initiation of SI (KOA). NOTE: If the BOP Fails to Start 1-SI-P-1B, Critical Task becomes Not Applicable.
2) WOG E-3 -- A: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs. Example: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs (KOA).

KOA: For the design basis tube rupture, isolate the ruptured SG from the atmosphere/Turbine building within 30 minutes. Note: The 30 minute criteria in the CT is ONLY for the design basis tube rupture.

Event #8: SGTR with Loss of Pressure control. (M - All)

The Team continues through the EOP progression E-0 to E-3.

After the Team has completed the rapid cooldown of E-3 and moves to the Depressurization steps, the Team will be presented with the inability to depressurize the RCS (No RCPs - No Spray available), 1 PZR PORV inoperable, and the last Pzr PORV not responding to placing the control switch in Open. This will require the Team to Transition to ECA-3.3, SGTR without Pressure Control.

When ECA-3.3 is entered, it is expected that the ruptured SG level will be > 73% NR leading to Team moving to Step 6, Check If SI Can Be Terminated.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Verifiable Actions:

1) RO will isolate AFW flow to the Ruptured SG.
2) BOP will reset SI and secure A CH pump and one of the running LHSI pumps.

(Discretionary CT - within 30 minutes).

3) RO will manipulate steam dump controls for rapid cooldown.
4) RO/BOP will block SI signals when conditions established.
5) RO will manipulate SI/CVCS control to terminate SI, establish CH flow, and restore letdown flow.

Classification:

Follow-up Classification question for SGTR: Alert FA-1.1.

The Scenario is terminated at Lead Evaluator discretion or at Step 11 of ECA-3.3, Check If CS Should Be Stopped (CH and LD flow have been re-established).

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Initial Conditions: Unit 1 and 2 Operating at 100%.

Turnover: The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Pre-load malfunctions: (Trigger 30s) o SI2409 SI RELAY CI1A FAILS TO ACTUATE o SI2505 SI RELAY SI5B FAILS TO ACTUATE o AS02 DISABLE SV-TV-102 OPEN o AS05 DISABLE SV-TV-103 CLOSE o AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

o AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

Turnover:

Unit 1 and 2 at 100% power; MOL.

A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon dilutions followed by a manual makeup for training.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Turnover: Team will perform PT-18.6I, PZR Block Valve Stroke Test. The performance of this procedure has been analyzed based on the current plant configurations and the PRA indicates green.

Event Malf. #s Severity Instructor Notes and Required Feedback 1 RCMOV_53 Open Test Cycle Pressurizer PORV, Block Valve breaker will trip when re-opened.

5_BKR, 2 RC4903, -.2 DEG PRZR Level Transmitter Fails Low, requiring IAs of AP-53.00 to control CH flow. 0-AP-53.00.

3 FW1803, +1 DEG Feed Flow Channel fails high requiring manual FRV control, IAs of AP-53.00 4 SD0201 True Loss of High Pressure Drain, AP-18.00 5 N/A N/A Ramp to 75% power IAW AP-23.00

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 6 RC2402 8% Steam Generator Tube Leak B SG at approximately 74 gpm. AP-16.00, E0.

AS02, Auto Actions of Air Ejector Rad Mon on High alarm do not function, BOP manually AS05 aligns. A/E RM Annunciator Response Procedure.

RC5601 RC5602 Reactor Coolant Pumps trip on electrical power swap to Reserve Station Service RC5603 TRUE Transformers (30 seconds after reactor trip).

7. RC2402 88%, 60 SGTL B SG escalates to Design Basis rate (710 gpm) in AP-24.01. AP-16.00, sec ramp Manual SI, E-0, E-3.

Failure of Auto Air Ejector to re-align on A/E RM High Alarm.

AS02/03 8 PCV455C OFF PZR PORV 1-RC-1455C will not open when switch placed in open - Go to ECA-

_OPEN, 3.3 PCV455C ON

_CLOSE 9 SI409 TRUE BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.

SI2505 Scenario Objectives:

A. Given a failure of 1-RC-MOV-1535 to re-open during performance of 1-PT-18.6I, PZR Block Valve Stroke Test, Implement the Applicable Tech Spec LCO.

B. Given a pressurizer level channel deviation, respond IAW 0-AP-53.00 to the failure.

C. Given a High Failure of SG Feed Flow Channel II on B SG, take action IAW 0-AP-53.00 to control SG level, and apply the applicable Tech Spec LCOs for the failure.

D. Given a trip of the running High Pressure Drain pump, ramp the Unit 1 <75% IAW 1-AP-18.00 and 0-AP-23.00.

E. Given a SG Tube Leak, respond IAW 1-AP-16.00 to quantify the leak rate, trip Unit 1, and perform the Immediate Action Steps of 1-E-0, Reactor Trip or Safety Injection.

F. Given a Design Basis SG Tube Rupture, respond IAW 1-E-0, and 1-E-3, Steam Generator Tube Rupture.

G. Given the Failure of 1-RC-PCV-1445C to open to depressurize the RCS, transition to 1-ECA-3.3, Steam Generator Tube Rupture without Pressurizer Pressure Control.

H. Given SI relay failures, manually align components IAW E-0, Attachment 1, 2, and 3.

SHIFT TURNOVER INFORMATION OPERATING PLAN:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance. Expected to be returned to services in 3 days. Per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training. A BAST concentration is 8.0 w/%.

Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, PZR Block Valve Stroke Test. Performance of this procedure has been authorized and has been PSA analyzed for current plant conditions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 1 Page 10 of 92 Event

Description:

Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.

Cue: By Examiner.

Note: An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.

The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.

A facility representative will be present for consultation with the Evaluation Team, as needed.

Time Position Applicants Action or Behavior 1-PT-18.6I SRO/BOP NOTE - Team will pre-brief this evolution prior to entering the simulator. Initial Conditions and Precautions and Limitations will be completed before entering the simulator.

BOP Verify closed or close PRZR PORV 1-RC-PCV-1456.

Verify key switch for PRZR PORV 1-RC-PCV-1456 OVPRESS BOP Mitigating System is in DISABLE.

Verify PRZR PORV Block Valve 1-RC-MOV-1535 is open.

BOP Stroke PRZR PORV Block Valve 1-RC-MOV-1535 through one complete cycle, timing valve movement in each direction. Time from signal initiation to complete valve travel.

BOP Valve closes and fails to reopen.

SRO Refer to Technical Specification 3.1.A.6 for required action

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 1 Page 11 of 92 Event

Description:

Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.

Cue: By Examiner.

SRO Refer to Technical Specification 3.1.A.6 for required actions.

With one block valve inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve to operable status or place the associated PORV in manual. In addition, restore the block valve to operable status in the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or, be in at least HSD within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature to < 350°F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

BOP Places 1-RC-PCV-1456 in CLOSE.

SRO Start 72 Hour Clock to repair Block Valve.

SRO Direct RO/BOP to notify Service Building Operator to check status of 1H1-2S 6A breaker for 1-RC-MOV-1535.

RO/BOP Contact Service Building Operator to check status of 1-RC-MOV-1535 Breaker.

RO/BOP When notified by field operator that 1H1-2S 6A. Breaker is tripped, report information to the Team using a Focus Brief.

SRO Notify Shift Manager of Block Valve failure and suspension of PT performance.

Request Electrical Maintenance support to investigate breaker trip.

SRO Exit 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> clock to place 1-RC-PCV-1456 in manual.

SRO Perform brief to update Team on Technical Specification requirements. Brief driven by brief card and placards.

END of Event #1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 2 Page 12 of 92 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior RO Diagnoses failure of 1-RC-LI-1461 with the following indications/alarms:

Alarms:

  • CH Flow rises on 1-CH-FI-1122A to ~109 gpm
  • PRZR Level on 1-RC-LI-1461 lowers to 34%

In accordance with the immediate actions of AP-53.00 the RO will take manual control of pressurizer level control by placing 1-CH-FV-1122 in manual and lowering charging flow to maintain program level (per AP-53.00).

SRO Enters 0-AP-53.00, Loss of Vital Instrumentation / Controls.

RO [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL Checks 1-RC-LI-1459, Pressurizer Level Channel 1, and 1-RC-LI-1460, Pressurizer Level Channel 2 are NORMAL.

RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-CH-FV-1122 in manual and raises charging flow.

SRO Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.

SRO will provide a band for control of PRZR level with CH flow in MANUAL.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Step 3, AP-53.00 RO VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO will identify that reactor power is less than 100% using PCS Display of Core Thermal Power.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 2 Page 13 of 92 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

  • PRZR Level Control, Step 11.

RO The RO will identify that 1-RC-LI-1461 has failed.

Step 11, AP-53.00 SRO 11. CHECK PRZR LEVEL CONTROL CHANNELS - NORMAL RO Responds NO, 1-RC-LI-1461 Abnormal.

SRO 11 a) RNO 1) Place either of the following in MANUAL:

  • 1-CH-FC-1122C, CHG FLOW CNTRL, OR
  • 1-CH-LC-1459G, PRZR LEVEL CNTRL RO Responds 1-CH-FC-1122 in MANUAL SRO 11 a) RNO 2) Control PRZR Level at Program Level.

RO Responds Maintain PRZR Level at program +/- band set by SRO SRO 11 a) RNO 3) Move PRZR Level - CH SEL switch to Defeat the failed channel.

RO/BOP Transfers CH SEL switch to 1 / 2 Position.

SRO 11 a) RNO 4) Check or place recorder 1-RC-LR-1459 on an operable channel.

BOP Checks or adjusts PRZR Level Recorder to 1-RC-LI-1459 or 1-RC-LI-1460.

SRO 11a) RNO 5) Refer to Tech Spec 3.7-1, Item 9 and Table 3.7-6, Item 13.

TS 3.7, Table 3.7-1, item 9; Operator Action 7. Number of Operable channels one less than Total number of channels: Place Inoperable channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, allowed to bypass channel for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance, If conditions not met within allowed time, reduce power to less than P-7 in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

TS Table 3.7-6m Item 13: Required Number of channels to meet function = 2.

11 a) RNO 6) Refer to Attachment 3.

SRO hands Attachment 3, Pressurizer Level Control diagram to RO/BOP for SRO review.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 2 Page 14 of 92 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

Step 11, AP-53.00, Continued:

SRO Step 11 b) Check Pressurizer Heaters - Energized.

RO Checks Required Pressurizer Heaters energized, and reports that Pressurizer heaters are energized.

SRO Step 11 c) Check Letdown - IN SERVICE.

RO Reports Letdown in service.

SRO Step 11 d) Check PRZR level control - IN AUTOMATIC.

RO Reports pressurizer level control in MANUAL.

SRO Step 11 d) RNO When pressurizer level restored to program level, un-saturate 1-CH-LC-1459G, PRZR LEVEL CNTRL. Place 1-CH-FCV-1122 in automatic.

RO Acknowledges direction and notifies SRO when pressurizer level returned to AUTOMATIC.

Step 13, AP-53.00 SRO SRO recalls NOTE 2 Prior to Step 4 and goes to Step 13 of AP-53.00.

SRO Step 13 Check Calorimetric - Functional IAW 1-OPT-RX-001, Attachment 4.

RO/BOP Checks Calorimetric unaffected by this failure, and reports to the SRO.

Step 14, AP-53.00 SRO CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-RC-LI-1461 is a Reg. Guide 1.97 component.

STEP 15, AP-53.00 SRO REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that the Reg. Guide 1.97 Review is complete and has been reviewed with the Shift Manager.

[CEP 99-0029 requires two channels of pressurizer level indication and refers to TS Table 3.7-6.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 2 Page 15 of 92 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

STEP 16, AP-53.00 SRO Review the following:

  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO determines that TS Table 3.7.1, Item 9 is applicable (72-hours to place the channel in trip). SRO determines that 3.1.A.5 is not applicable since pressurizer heaters did not de-energize and that Table 3.7-6 item 1 is Not Applicable.

SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

[TRM Section 3.3, Condition A, requires a Fire Watch be established in the Cable Vault and Tunnel and Emergency Switchgear Room of the affected Unit within 14 days, and restore the instrument to Functional status in 60 days. Hourly Fire Watch Requirement established in TRM Section 5.2. NO VPAP-2802 requirement for this failure.]

Step 17, AP-53.00 SRO CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS The team will identify that no new additional failures exist (i.e., all failures have already been addressed), proceed to the RNO section, and this will direct the team to Step 19.

Step 19, AP-53.00 SRO PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC
  • I&C END EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 16 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior BOP Diagnoses failure FT-1487 with the following indications/alarms:

Alarms:

Indications:

  • Step increase in 1B SG Feed Flow indication CH-3
  • decrease in 1B SG Feed Flow indication CH-4
  • decreasing level on B SG.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS Step 1, AP-53.00 BOP [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies Channel IV indication for feed flow is NORMAL.

Step 2, AP-53.00 BOP [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and increases demand (FF >

SF) to restore level to program using Channel IV indication.

SRO Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.

SRO will provide a band for control of B SG level with B FRV in MANUAL.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 17 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

Step 3, AP-53.00 SRO

  • VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Checks Reactor Power < 100% using PCS Calorimetric. Due to restoration of FF on 1B SG, power increase may be noted. As required, the SRO may direct the BOP to reduce turbine load to prevent exceeding 100% Calorimetric power.

Note: 0-AP-53.00, Attachment 7 Actions are contained at the end of this section starting on page 20.

Step 4, AP-53.00, Notes SRO NOTE: When the affected instrument/controller malfunction has been addressed by this procedure, recovery actions may continue at Step 13.

Step 4, AP-53.00 SRO DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

RO/BOP Identifies 1B SG Feed Flow affected.

SRO Goes to Step 7.

Step 7, AP-53.00 SRO CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.

SRO CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS - NORMAL

  • Steam Pressure
  • Steam Flow
  • Feed Flow

Step 7. RNO, AP-53.00 IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level Control system has failed, THEN do the following:

BOP a) Place the associated Feed Reg Valve in MANUAL.

BOP Verifies B SG MFRV controller, 1-FW-FCV-1488, in manual BOP b) Control SG level at program level (44%, a band will be given).

BOP Verifies B SG NR level is returning to program level.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 18 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

RO c) Select the redundant channel for affected SG(s)

RO Selects Channel IV Feed Flow for B SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV)

BOP d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.

BOP Places B SG FRV controller, 1-FW-FCV-1488, in automatic control.

Step 6, RNO, AP-53.00 (Continued)

SRO Perform follow-up actions:

a) Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.

If asked the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.

b) Refer to the following Tech Spec 3.7 items:

SRO

  • Table 3.7-1, 12 and 17
  • Table 3.7-2, 1.c, 1.e, and 3.a
  • Table 3.7-3, 2.a, and 3.a
  • Table 3.7-6, 15 and 16 Determines Table 3.7-1 item 17, is applicable (place channel in trip w/in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).

SRO c) Refer to Attachment 1.

d) IF no other instrumentation failure exists, THEN GO TO Step 13.

Step 13, AP-53.00 SRO 13. Review OPT-RX-001, Rx Power Calorimetric using PCS computer program, Attachment 4, to determine operability of calorimetric and need to perform OPT-RX-007, Shift Average Power Calculation.

RO Determines that OPT-RX-001 is NOT impacted and OPT-RX-007 will NOT need to be performed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 19 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

Step 13, RNO, AP-53.00 SRO a) Initiate ( )-OPT-RX-007, SHIFT AVERAGE POWER CALCULATION, as necessary.

Note: The Team will determine that the Calorimetric Program is functional based on a recent change to 1-OPT-RX-001, Calorimetric, Attachment 4.

Step 14, AP-53.00 SRO 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 14 if not Reg. Guide 1.97)

SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-FW-FT-1487 is a Reg. Guide 1.97 component.

Step 15, AP-53.00 SRO 15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 requirements have been reviewed with the Shift Manager.

[Reg. Guide 1.97 requires one channel of Feed Flow indication per steam generator and no further actions are required.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 20 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

SRO 16 REVIEW THE FOLLOWING:

  • VPAP-2802, NOTIFICATIONS AND REPORTS

STA The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

[VPAP-2802 - no requirement associated with the failure, No TRM requirements for this failure].

SRO 17. CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS Goes to Step 19 SRO 19. PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC
  • I&C END OF EVENT 3 0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 1 IF a rise in Reactor Power is caused by secondary transient, THEN GO TO Step 2.

IF a rise in Reactor Power is caused by primary transient, THEN GO TO Step 6.

NOTE: During secondary transient conditions, the most reliable indications of Reactor Power are Core T and Power Range NI. These indications should be used as the basis for Reactor Power until stable conditions have been reestablished.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 21 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 2 Mitigate a rise in Reactor Power caused by secondary transients by lowering steam demand or Turbine load as follows:

a) Reduce the Turbine Setter by an appropriate amount.

b) Place the Load Rate Selector thumbwheel to 1% / min.

c) Depress the GO pushbutton.

3 IF Turbine load can NOT be reduced using Operator Auto, THEN lower Turbine load using the Valve Position Limiter.

4 IF Turbine load still can NOT be reduced, THEN do the following.

a) Push the Turbine Manual pushbutton.

b) Check Turbine controls in Manual.

c) Depress the GV down pushbutton to reduce GV position.

NOTE: The CALCALC 10 minute Average Power will lag actual Reactor Power following a transient, and may continue to rise even after core thermal power has been reduced to less than 100%.

5 Check Reactor Power reduced to less than 100%.

  • Power Range NI power.
  • Core T power
  • CALCALC Instantaneous power (if reliable)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 22 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 6 Mitigate a rise in Reactor Power caused by primary transients as follows. Enter N/A for Steps 6 through 9 if NOT applicable.

a) Place the Rod Control Selector switch in Manual.

b) Insert control rods.

NOTE: The CALCALC 10 minute Average Power will lag actual Reactor Power following a transient, and may continue to raise even after core thermal power has been reduced to less than 100%.

7 Check Reactor Power reduces to less than 100%.

  • Power Range NI power.
  • Core T power
  • CALCALC Instantaneous power (if reliable) 8 IF necessary, THEN initiate a normal boration to control Flux.
9. WHEN Tave and Tref are within 1°F, THEN place control rods in Auto.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 4 Page 23 of 92 Event

Description:

Loss of High Pressure Drain Pump, 1-AP-18.00.

Cue: By Evaluator BOP Diagnose the trip of the High Pressure Drain Pump, 1-SD-P-1A based on the following indications:

  • 1H-G5/6/7 SG 1A/1B/1C LVL ERROR Step 1, AP-18.00 SRO Enter 1-AP-18.00 CHECK HP HEATER DRAIN PUMP STATUS:

SRO a) Check HP Heater Drain Pump - TRIPPED OR NOT PROVIDING SUFFICIENT FLOW BOP Reports that 1-SD-P-1, HP Heater Drain pumps tripped.

SRO b) Place pump control Switch in PTL BOP Places 1-SD-P-1A control switch in PTL Step 2, 1-AP-18.00 SRO CHECK REACTOR POWER - GREATER THAN OR EQUAL TO 75%

RO/BOP Reports reactor power at 100%

Step 3, AP-18.00 SRO START THIRD CONDENSATE PUMP AS REQUIRED BY PLANT CONDITIONS BOP Starts 1-CN-P-1A and verifies Proper Operation.

Step 4, AP-18.00 SRO NOTE: With unit at 100% power, Turbine load should be decreased approximately 50 MW.

REDUCE TURBINE LOAD AS NECESSARY TO MAINTAIN LOOP Ts -

LESS THAN 100%

  • Use Valve Position Limiter OR
  • Reduce Turbine load using Turbine Manual BOP Using Guidance of NOTE preceding the Step, Turbine load will be reduced.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 4 Page 24 of 92 Event

Description:

Loss of High Pressure Drain Pump, 1-AP-18.00.

Cue: By Evaluator Step 5, 1-AP-18.00 SRO NOTE: Ramping to 75% allows the Condensate Polishing Building to be placed fully in service.

COMMENCE RAMP TO 75% POWER IAW 0-AP-23.00, RAPID LOAD REDUCTION Step 6, 1-AP-18.00 SRO

  • USE CONTROL RODS AND CHEMICAL SHIM TO MAINTAIN FLUX IN BAND Step 7, 1-AP-18.00 SRO MONITOR MAIN FEED REG VALVE RESPONSE - MAINTAINING SG LEVEL IN BAND BOP Acknowledges Step direction.

SRO Initiate AP-23.00, Rapid Load Reduction END EVENT #4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 25 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior AP-23.00, Rapid Load Reduction SRO The team will hold a transient brief. During the brief the upcoming ramp will be discussed.

The RO and BOP will report critical parameters, as per placard on Main Control Room Bench Board. It is expected that the RO will discuss reactivity parameters associated with the ramp from the pre-planned ramp plan.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

The following reactivity plan will be discussed for a ramp to 75%:

  • Gallons of boric acid required as per plan - 146 gallons
  • D control bank end at 197 steps
  • 5.8 gpm Boric Acid Flow, average rate during ramp.
  • 1957 gallon PG required to stabilize at 75% power.
  • The Team will discuss duration of Emergency Borate at start of Ramp, and remaining boron to be added via normal boration flowpath.

NOTE: RO Emergency borates for 25 seconds which corresponds to ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.

Step 1, 0-AP-23.00 SRO Caution Prior to Step 1:

  • Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.

Notes Prior to Step 1:

  • Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
  • When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
  • Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
  • The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
  • For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 26 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Step 1, 0-AP-23.00 RO TURN ON ALL PRZR HEATERS.

Step 2 0-AP-23.00 INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:

BOP a) Check turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter. If turbine is on limiter; reduce setter an appropriate amount, set load rate thumbwheel to 2% (or higher), press GO.

When Turbine limiter light OFF, press HOLD button.

RO b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5°F.

BOP c) Check or place turbine in IMP IN or IMP OUT as determined by Shift Supervision The SRO chooses IMP IN.

BOP d) Adjust SETTER to desired power level BOP e) Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute)

BOP f) Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button)

BOP g) Reduce Turbine Valve Position Limiter as load decreases Periodically reduce the limiter setpoint during the ramp.

Step 3, 0-AP-23.00 SRO CHECK EMERGENCY BORATION - REQUIRED RO Reports Emergency Boration required.

Step 4, 0-AP-23.00 SRO NOTE: Step 4 or Step 5 may be performed repeatedly to maintain Tref and Tave matched, Flux in band, and control rod position above the LO-LO insertion limit.

RO Acknowledges NOTE.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 27 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Step 4, 0-AP-23.00 SRO PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:

RO a) Check or raise CHG flow to greater than 75 gpm RO b) Transfer the in-service BATP to FAST RO c) Open 1-CH-MOV-1350 for required time (~25 seconds)

RO d) Monitor EMRG BORATE FLOW

  • ( )-CH-FI-( )110 e) After required emergency boration, perform the following:

RO 1) Close 1-CH-MOV-1350 RO 2) Transfer the in-service BATP to AUTO

3) Restore Charging flow control to normal.

Step 5, 0-AP-23.00 RO ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.

Step 6, 0-AP-23.00, NOTES SRO NOTES:

  • If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
  • RCS Tave must be maintained less than or equal to 577°F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
  • I & C should be contacted to provide assistance with adjusting IRPIs.

Step 6, 0-AP-23.00 RO/BOP CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG Step 7, 0-AP-23.00 RO

  • CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 28 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Step 8, 0-AP-23.00 BOP MONITOR STEAM DUMPS FOR PROPER OPERATION Step 9, 0-AP-23.00 SRO NOTIFY THE FOLLOWING:

  • Energy Supply (MOC)
  • Polishing Building
  • Chemistry
  • OMOC Step 10, 0-AP-23.00 SRO EVALUATE THE FOLLOWING:
  • VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.

[VPAP-2802 and EPIP are not applicable for this event.]

Step 11, 0-AP-23.00 SRO CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR.

When reactor power has decreased >15%, then chemistry will be notified.

END EVENT #5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 29 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Adjust 1-CH-YIC-1113 to desired total gallons RO 3. Adjust 1-CH-FC-1113A to desired flow rate.

RO 4. Place the MAKE-UP MOD SEL switch in the BORATE position.

RO 5. Place the MAKE MODE CNTRL switch in the START position.

RO 6. Check proper valve positions.

RO 7. Adjust boration rate using 1-CH-FC-1113A, as necessary.

RO 8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.

a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.

b) Enter N/A for the remaining steps in this Attachment.

Attachment 5 is on the next page RO 9. Check controllers for Primary Grade water and Boric Acid are set correctly.

RO 10. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 11. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 12. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 30 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.

RO 3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.

RO 4. Place the MAKE-UP MODE SEL switch in the MANUAL position.

RO 5. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.

RO 7. Check proper valve positions.

RO 8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1113B in the AUTO position RO 9. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 10. Check or place the control switches in the AUTO position.

RO 11. Check controllers for Primary Grade water and Boric Acid are set correctly.

RO 12. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 13. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 14. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 31 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Time Position Applicants Action or Behavior Team Diagnose SGTL B SG based on the following:

Alarms:

  • RM-G8 CNDSR AIR EJECTOR ALERT/FAILURE
  • RM-H8 1-SV-RI-111 HIGH Indications:
  • Increasing trend on 1-MS-RR-193, Control Room N16 Trend Recorder, from Normal to 200 GPD.

SRO Direct Unit to Perform Annunciator Response Procedure for A/E Alert and High Alarms.

Note: Unit 2 Operator will perform ARP for A/E RM Alarms. Unit 2 will hand Page 3 and 4 of RM-H8 ARP to BOP to check Auto Actions complete; following E-0 Team Brief.

Verification of ARP RM-H8, A/E RM High Alarm RM-H8, Step 6 BOP NOTE: On a high alarm, air ejector gaseous effluent is diverted from vent stack to containment.

CHECK AUTOMATIC ACTIONS - VALVES POSITIONED AS FOLLOWS:

  • 1-SV-TV-103 - CLOSED Identifies 1-SV-TV-103 Open, places control switch in close.
  • 1-SV-TV-102 - OPEN Identifies 1-SV-TV-102 Closed, places control switch in open.

RM-H8, Step 7 BOP CHECK AIR EJECTOR VENT TO CTMT VV - OPEN

  • 1-SV-TV-102A Identifies 1-EV-RV-102A open Report to SRO that A/E manually aligned to containment.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 32 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

1-AP-16.00 SRO Direct the RO to perform the Immediate Action Steps of 1-AP-16.00.

Step 1, 1-AP-16.00 RO NOTE:

  • RCS average temperature has a direct impact on pressurizer level.

[ 1 ] ___ MAINTAIN PRZR LEVEL:

RO

  • Isolate Letdown Close 1-CH-LCV-1460A and 1-CH-LCV-1460B
  • Control Charging flow Place 1-CH-FCV-1122, CH Flow Control Valve, in Manual Monitor CH Flow on 1-CH-FI-1122 Identify RCS leak rate less than the capacity of a single CH pump Continue adjustment of CH flow to quantify leak rate to determine if reactor trip required Step 1, 1-AP-1600 SRO Upon report of completion of Immediate Action Step of 1-AP-16.00, Perform a commensurate brief; continue to Step 2 of 1-AP-16.00.

Step 2, 1-AP-16.00 SRO CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING

  • PRZR level
  • PRZR pressure
  • RCS subcooling RO Report that PRZR Level, Pressure, and Subcooling Stable RO continues actions to quantify leakrate Step 3, 1-AP-16.00 SRO PLACE THE FOLLOWING COMPONENTS IN OFF:

RO

  • CTMT sump pumps Places 1-DA-P-4B control switch on OFF
  • CTMT vacuum pumps Places 1-CV-P-1A control switch in OFF

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 33 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 4, 1-AP-16.00 SRO NOTE: Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.

SRO CHECK REACTOR TRIP - REQUIRED

  • Leak rate - GREATER THAN 50 GPM OR
  • Adequate makeup not being provided by blender RO Reports RCS leak rate greater than 50 gpm.

NOTE: Due to transient on RCS caused by Ramp for previous event, exact quantification of leak rate may be difficult.

Step 5, 1-AP-16.00 SRO ALIGN CHG PUMP SUCTION TO RWST a) Open 1-CH-MOV-1115B and 1-CH-MOV-1115D RO Opens CH pump Suction MOVs from RWST, 1-CH-MOV-1115B/D b) Close 1-CH-MOV-1115C and 1-CH-MOV-1115E Closes CH pump Suction from VCT MOVs, 1-CH-MOV-1115C/E Step 6, 1-AP-16.00 SRO GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 34 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

1-E Reactor Trip or Safety Injection RO [1] CHECK REACTOR TRIP:

a) Manually trip reactor Pushes the reactor trip push buttons.

b) Check the following:

  • All Rods On Bottom light - LIT
  • Neutron flux - DECREASING RO Reports Reactor Tripped at completion of Step 1. SRO Acknowledges.

RO [2] CHECK TURBINE TRIP:

RO a) Manually trip the turbine Pushes the turbine trip push buttons.

b) Check all turbine stop valves - CLOSED c) Isolate reheaters by closing MSR steam supply SOV

  • 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)

RO Reports Turbine Tripped at completion of Step 2. SRO Acknowledges.

RO [3] VERIFY BOTH AC EMERGENCY BUSES - ENERGIZED RO Reports Both AC Emergency Buses Energized at completion of Step 3. SRO acknowledges.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 35 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

RO [4] CHECK IF SI INITIATED:

a) Check if SI is actuated:

  • LHSI pumps - RUNNING
  • A-F-3 SI INITIATED - TRAIN A
  • A-F-4 SI INITIATED - TRAIN B RO will determine that SI has not occurred and perform step 4a RNO actions:

RO 4a RNO Check if SI is required or imminent as indicated by any of the following:

  • Low PRZR pressure
  • High steamline differential pressure
  • High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.

RO reports SI is not in service or required; Immediate Actions of E-0 are complete; recommend transition to ES-0.1 after completion of Step 4. SRO Acknowledges.

After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0 and announce a transition to ES-0.1. After the immediate actions are verified, the team will conduct a brief.

During the Brief RO/BOP reports that ALL RCPs are tripped.

Team Identify 1B SG experiencing a Large SG Tube Leak.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal, with the exception of the alarms already received. He will also state that containment conditions and the electrical conditions are as you see them (or as reported by the RO/BOP).

If not previously performed, Unit 2 Operator will Provide BOP/SRO with ARP pages Unit 2 for A/E RM High alarm for verification of Auto Actions.

Establish priorities at Brief End, RO:

SRO

  • Complete verification of A/E High Alarm auto actions.
  • Contact Service Building Operator to check status of RCP breakers.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 36 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

SRO When Brief is complete Announce Transition to ES-0.1, Reactor Trip Response, Read the First NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.

Transitions to 1-AP-24.01 Step 1, 1-AP-24.01 SRO CAUTION: If the leak rate increases to 150 gpm, 1-E-0, Reactor Trip or Safety Injection, must be implemented.

NOTE:

  • Procedure 1-ES-0.1, Reactor Trip Response, must not be performed when implementing this procedure.
  • Refer to Attachment 8 for guidance on transient AFW control.

CHECK SI - IN SERVICE RO Identifies NO not required. Team Goes To Step 3.

Note: Attachment 8 actions are start on Page 40.

Step 3, 1-AP-24.01 SRO CHECK CONDENSATE POLISHING BUILDING - BYPASSED RO Identifies Polishing Building bypassed Step 4, 1-AP-24.01 SRO CHECK ALL AC BUSSES - ENERGIZED BY OFFSITE POWER RO Identifies all AC Buses energized by off-site power by:

  • Checks breakers 15H8/15J8 closed
  • Station Service buses energized using Voltage/Current indications on Benchboard.
  • Checks for Abnormal Electrical System alarms on K Annunciator Panel.

Step 5, 1-AP-24.01 SRO

  • CHECK PRZR LEVEL - GREATER THAN 22%

RO Reports actual pressurizer level and trend.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 37 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 6, 1-AP-24.01 SRO CHECK FW STATUS:

a) Check RCS Average temperatures - LESS THAN 554°F RO Identifies RCS Tave less than 554°F b) Check Feed REG valves - CLOSED RO Identifies FRVs closed c) Close SG FW isolation MOVs

  • 1-FW-MOV-154A
  • 1-FW-MOV-154B
  • 1-FW-MOV-154C RO/BOP Closes SG FW Isolation MOVs d) Check AFW pumps - RUNNING
  • Motor Driven AFW pumps
  • TD AFW pump RO/BOP Identifies MD and TD AFW Running e) Check total AFW flow - GREATER THAN 540 GPM (350 W/O RCPs)

RO/BOP Identifies AFW flow indicated f) Check emergency buses - BOTH ENERGIZED RO Identifies Emergency buses energized g) Control feed flow to maintain narrow range level between 22% and 50%

BOP Acknowledges control of SG level when returned to NR scale.

Step 7, 1-AP-24.01 SRO CHECK PCS POINTS USING GROUP 80 REVIEW OR MAIN STEAM P & ID:

  • R1RM204C, RI-MS-124
  • R1RM205C, RI-MS-125
  • R1RM206C, RI-MS-126 RO/BOP Checks points for abnormal indication.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 38 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 8, 1-AP-24.01 SRO IDENTIFY AFFECTED SG(S):

  • Unexpected rise in any SG narrow range level OR
  • High radiation from any SG MS line monitor OR
  • High radiation from any SG blowdown line OR
  • High radiation from any SG sample OR
  • High radiation from any SG N-16 monitor RO/BOP Identifies rise in B SG NR level Step 9, 1-AP-24.01 SRO
  • CHECK AFFECTED SG LEVEL:

a) Narrow range level - GREATER THAN 12%

BOP Acknowledges when B SG NR Level > 12%, perform substep b).

b) Stop feed flow to affected SG(s)

BOP Isolates AFW flow to B SG, by closing 1-FW-MOV-151 C / D.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 39 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 10, 1-AP-24.01 SRO ISOLATE AFFECTED SG(S):

a) Adjust affected SG PORV controller setpoint to 1035 psig BOP Checks B SG PORV setpoint at 1035 psig b) Check affected SG PORV - CLOSED BOP Identifies B SG PORV closed c) Check blowdown TVs from affected SG - CLOSED RO Identifies B SG BD TVs closed.

d) Locally close steam supply valve to TD AFW pump:

  • 1-MS-87 for SG A
  • 1-MS-120 for SG B
  • 1-MS-158 for SG C BOP Directs Service Building operator to close 1-MS-120.

e) Close SG FW Isolation MOV, 1-FW-MOV-154A, B, or C BOP Identifies 1-FW-MOV-154B closed f) GO TO Step 13

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 40 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 1, AP-24.01, Attachment 8 BOP Maintain minimum AFW flow of 540 gpm with RCP(s) in service until one SG Narrow Range level is greater than 12%.

Checks AFW ~1050 gpm Step 2, AP-24.01, Attachment 8 Maintain minimum AFW flow of 350 gpm with NO RCPs running, until one SG BOP Narrow Range level is greater than 12%.

Throttles AFW to SGs per Step 2 to flow rate established by SRO or ~ 120 gpm per SG using 1-FW-MOV-151 A through F control switches.

Step 3, AP-24.01, Attachment 8 BOP NOTE: AFW to idle loop(s) (RCP secured), should be throttled to prevent depressurization of the SG and subsequent Header / Line SI. AFW flow between approximately 60 gpm and 100 gpm should be adequate to prevent a Header / Line SI.

Identifies NOTE as not applicable for this event.

When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50% by throttling AFW Isolation MOVs:

  • SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
  • SG B, 1-FW-MOV-151C and 1-FW-MOV-151D
  • SG C, 1-FW-MOV-151A and 1-FW-MOV-151B Identifies need to monitor flow rate as SG NR level recovers.

Step 4, AP-24.01, Attachment 8 BOP Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves:

Identifies Step as not applicable.

Contact Service Building operator to check status of RCP breakers.

BOP When contacted the Service Building operator will report no abnormalities with the RCP breakers, but the Speed Sensing Panel appears to be malfunctioning.

Performs a Focus Brief to apprise the other Team members of RCP status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 41 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

SG Tube Leak escalates to 710 gpm Tube Rupture RO Diagnose SG Tube Rupture by:

RCS Pressure decrease.

Pressurizer Level decrease.

Manually raise CH flow to maximum.

Identify pressurizer level decreasing.

Report to SRO that Safety Injection is required.

Re-Perform High Level Steps, 1 through 3 of E-0.

Manually Initiate Safety Injection.

Check Annunciator 1A-F3, SI Initiated Train A - LIT Check Annunciator 1A-F4, SI Initiates Train B - LIT Check LHSI Pumps Running.

Report to SRO Immediate Actions of E-0 with SI Complete.

Critical Task 2) Isolate steam release from ruptured SG within 30 Minutes START Time: _____________

SRO The team will hold a transition brief. During the brief it will be identified that SI was initiated and the SGTL has degraded into a SGTR.

The SRO will set priorities:

RO - Continue with SRO in performance of E-0 to E-3.

BOP - Perform Attachment 1 through 3 of E-0.

Step 5, E-0 SRO/BOP Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained under last section of Event 9).

SRO/RO SRO may direct the RO to perform Attachment 10 of 1-E-0 for Ruptured SG Isolation and AFW Control. This may or may not be initiated at any time during the performance of E-0. Attachment 10 actions are contained at the end of this section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 42 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 6, E-0 RO

  • CHECK RCS AVERAGE TEMPERATURE
  • STABLE AT 547°F OR
  • TRENDING TO 547°F The team will identify that RCS temperature is decreasing. The team should attribute this to the injection of SI into the RCS and AFW flow to the SGs. It is acceptable for the team to enter the RNO portion of this step and perform the applicable steps (summarized below):

Stop dumping steam Reduce AFW flow to the SG Close MSTVs if cooldown continues Step 7. E-0

7. CHECK PRZR PORVs AND SPRAY VALVES:

RO a) PRZR PORVs - CLOSED b) PRZR spray controls

  • Demand at Zero (or)
  • Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN Step 8, E-0 SRO NOTE: Seal injection flow should be maintained to all RCPs.
  • CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

RO a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.

b) RCS subcooling - LESS THAN 30°F [85°F]

RCS subcooling will NOT be less than 30 °F RNO for the step is to go to step 9.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 43 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 9, E-0 RO CHECK IF SGs ARE NOT FAULTED:

  • Check pressures in all SGs a) STABLE OR INCREASING AND b) GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.

Step 10, E-0 RO CHECK IF SG TUBES ARE NOT RUPTURED:

  • Condenser air ejector radiation - NOT NORMAL
  • SG blowdown radiation - NOT NORMAL
  • SG MS radiation - NORMAL
  • TD AFW pump exhaust radiation - NORMAL
  • SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO should observe B SG NR level going up uncontrollably.

SRO RNO: GO TO 1-E-3, STEAM GENERATOR TUBE RUPTURE.

SRO The team will hold a transition brief. During the brief it will be identified that B SG is ruptured, current isolation status of the ruptured SG and that the team is transitioning to 1-E-3.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified alarms. He will also state that containment conditions and the electrical conditions are as you see them.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 44 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

BEGIN Step 1, 1-E-3:

NOTE: Seal injection flow should be maintained to all RCPs.

  • CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

RO a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO will identify that two charging pumps are running.

b) RCS subcooling - LESS THAN 30°F [85°F]

RO will identify that RCS subcooling is greater than 30°F RNO is to go to step 2 Step 2, E-3 IDENTIFY RUPTURED SG(s):

  • Unexpected rise in any SG narrow range level SRO OR
  • High radiation from any SG MS line monitor OR
  • High radiation from any SG blowdown line OR
  • High radiation from any SG sample Team identifies B SG NR level rising unexpectedly.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 45 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 3, E-3 SRO CAUTION:

  • If the TD AFW pump is the only available source of feed flow, steam supply to the TD AFW pump must be maintained from at least one SG.
  • At least one SG must be maintained available for RCS cooldown.
3. ISOLATE RUPTURED SG(s):

RO a) Adjust ruptured SG PORV controller setpoint to 1035 psig b) Check ruptured SG(s) PORV - CLOSED c) Verify blowdown TVs from ruptured SG(s) - CLOSED d) Locally close steam supply valve(s) to TD AFW pump:

  • 1-MS-120 for B SG If 1-MS-120 not closed iaw attachment 10 of 1-E-0, then a field operator will be dispatched to close it at this time.

e) Close ruptured SG(s) MSTV (B)

Partial completion of the critical task (WOG E-3A) to isolate the SG is accomplished by performance of this step. KOA: For the design basis tube rupture, isolate the ruptured SG from the atmosphere/Turbine building within 30 minutes.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 46 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 4, E-3 SRO CAUTION: If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless needed for RCS cooldown.

  • CHECK RUPTURED SG LEVEL:

a) Narrow range level - GREATER THAN 12% [18%]

b) Stop feed flow to ruptured SG(s)

RO Identifies B SG level >12%, closes 1-FW-MOV-151C/D to isolate AFW Flow c) Check ruptured SG AFW MOVs auto-open signal - DEFEATED Identifies auto-open signal not defeated, SRO goes to Step 4 c) RNO NOTE: BOP may have performed the following IAW Attachment 10.

1) Select the ruptured SG AFW MOVs using the following switches:

RO

  • H TRAIN DISABLE SELECTOR SWITCH
  • J TRAIN DISABLE SELECTOR SWITCH
2) Defeat the auto-open signal for the selected MOVs by placing the following key switches in the DISABLE SELECTED position:
  • H TRAIN AUTO OPEN ENABLE SWITCH
  • J TRAIN AUTO OPEN ENABLE SWITCH Step 5, E-3 SRO CAUTION: Major steam flow paths from the ruptured SG(s) should be isolated before initiating RCS cooldown.

CHECK RUPTURED SG(S) PRESSURE - GREATER THAN 350 PSIG RO Identifies B SG pressure ~ 1000 psig.

Step 6, E-3 SRO

  • CHECK LOW PRZR PRESS SI SIGNAL - BLOCKED
  • Permissive Status light C LIT RO Identifies PSL C2 NOT LIT.

SRO WHEN PRZR pressure less than 2000 psig, THEN do the following:

a) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block.

b) Check Permissive Status light C LIT.

NOTE: BOP may have completed this action in E-0, Attachment 1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 47 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 7, E-3 SRO CHECK LOW TAVE SI SIGNAL - BLOCKED

  • Permissive Status light F LIT RO Identifies PSL F1 NOT LIT.

SRO WHEN Tave less than 543°F, THEN do the following:

a) Turn both HI STM FLOW & LO TAVG OR LP switches to block.

b) Check Permissive Status light F LIT.

NOTE: BOP may have completed this action in E-0, Attachment 1.

Step 8, E-3 SRO CAUTION:

  • Flow on each Main Steamline should be kept less than 1.0 x 106 PPH to prevent Main Steamline isolation during RCS cooldown with the Steam Dumps.
  • If no RCPs are running, RCS cooldown and depressurization may cause a false Integrity Status Tree indication on the ruptured loop. The Cold Leg indication on the ruptured loop should be disregarded until after the performance of Step 36.

NOTE: RCP trip criteria does NOT apply after initiation of an operator controlled cooldown.

INITIATE RCS COOLDOWN:

a) Determine required core exit temperature (ONE TIME):

SRO/BOP Concur Target CETC temperature 485 °F if SG pressure between 901 and 1000 psig, or 495° if SG pressure between 1001 and 1085 psig.

Step 8, E-3, Continued RO b) Place Steam Dump Mode Select switch in Steam Pressure mode c) Check RCS Tave - LESS THAN 543°F RO d) Place the STM DUMP CNTRL switch in BYP INTLK and then return to ON e) Check Bypass Status light D LIT RO f) Dump steam to condenser from intact SG(s) at maximum rate g) Check CETCs - LESS THAN REQUIRED TEMPERATURE SRO When RCS Temperature < 543°F, SRO will direct the block of HSF SI and check of PSL F1 LIT.

When RCS pressure < 2000 psig, SRO will direct the block of Low Pressure/Header-to-Line SI Signal, and check the PSL C2 LIT.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 48 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

RO Performs the Block of SI Signals and check of PSLs when directed.

h) Stop RCS cooldown RO When target CETC Temperature reached, RO throttles back on steam dumps.

i) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE SRO SRO will direct a band for control of CETC temperature.

Step 9, E-3 SRO CHECK INTACT SG LEVELS:

a) Any narrow range level - GREATER THAN 12% [18%]

b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%

RO/BOP Adjust AFW to restore A and C SG NR Level to 22-50%.

Step 10, E-3 SRO CAUTION: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure decreases to less than 2335 psig.

  • CHECK PRZR PORVs AND BLOCK VALVES:

a) Power to PRZR PORV block valves - AVAILABLE b) PRZR PORVs - CLOSED c) PRZR PORV block valves - AT LEAST ONE OPEN Step 11. E-3 SRO RESET BOTH TRAINS OF SI RO Push SI Reset Pushbuttons. SI previously reset.

Step 12, E-3 SRO RESET CLS:

a) Check CTMT pressure - HAS EXCEEDED 17.7 psia RO Report No, CTMT has not exceeded 17.7 psia.

RNO a) GO TO Step 13.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 49 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 13, E-3 SRO CHECK INSTRUMENT AIR AVAILABLE:

a) Check annunciator B-E NOT LIT RO Report Yes, B-E-6 Not Lit.

b) Check at least one CTMT IA compressor - RUNNING

  • 1-IA-C-4A or 1-IA-C-4B RO Report Yes, 1-IA-C-4A running c) Check 1-IA-TV-100 - OPEN RO Report Yes, 1-IA-TV-100 open.

Step 14, E-3 SRO ALIGN CONDENSER AIR EJECTOR TO CTMT:

a) Check the following:

  • 1-SV-TV-102 - OPEN
  • 1-SV-TV-103 - CLOSED RO Reports valves in required position. Valves Manually Aligned by BOP on A/E RM auto failure during Event 6.

b) Open the following valve:

  • 1-SV-TV-102A RO/BOP Opens 1-SV-TV-102A.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 50 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 15, E-3 SRO CAUTION: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.

  • CHECK IF LHSI PUMPS SHOULD BE STOPPED:

a) Check LHSI pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST RO Reports 1 LHSI pump running with suction aligned to RWST.

b) RCS pressure - GREATER THAN 250 PSIG [400 PSIG]

RO Reports RCS pressure greater than 250 psig.

c) Stop LHSI pumps and put in AUTO RO Stops running LHSI pump and places in AUTO.

Step 16, E-3 SRO CHECK IF RCS COOLDOWN SHOULD BE STOPPED:

a) Check CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP Reports CETCs < required temperature b) Stop RCS cooldown RO/BOP Reports RCS Coodown stopped.

c) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP Reports that RCS temperature being maintained in required band.

Step 17, E-3 SRO CHECK RUPTURED SG(s) PRESSURE - STABLE OR INCREASING BOP Reports B SG pressure stable.

Step 18. E-3 SRO CHECK RCS SUBCOOLING BASED ON CETCs - GREATER THAN 50°F [105°F]

BOP Reports indicated subcooling value.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 51 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 19, E-3 SRO DEPRESSURIZE RCS TO MINIMIZE BREAK FLOW AND REFILL PRZR:

a) Check normal spray - AVAILABLE

  • RCP C AND 1-RC-PCV-1455B - BOTH AVAILABLE OR
  • RCPs A and B, AND 1-RC-PCV-1455A - BOTH AVAILABLE RO Identifies No pressurizer spray available, SRO Goes To Step 20.

Step 20, E-3 SRO CAUTION:

  • The PRT may rupture if a PRZR PORV is used for RCS depressurization.

Rupturing the PRT may result in abnormal containment conditions.

  • Cycling of the PRZR PORV should be minimized.

NOTE: The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PRZR level.

DEPRESSURIZE RCS USING PRZR PORV TO MINIMIZE BREAK FLOW AND REFILL PRZR:

a) PRZR PORV - AT LEAST ONE AVAILABLE b) Open one PRZR PORV until ANY of the following conditions satisfied:

(Attachment 4 lists conditions)

  • PRZR level - GREATER THAN 69%

OR

  • RCS subcooling based on CETCs - LESS THAN 30°F [85°F]

OR

  • BOTH of the following exist:
1) RCS pressure - LESS THAN RUPTURE SG(s) PRESSURE
2) PRZR level - GREATER THAN 22% [50%]

RO When Attempt Made to open 1-RC-PCV-1455C, PCV will Not Open.

SRO Transition to ECA-3.3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 52 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

ATTACHMENT 10 of 1-E-0

1. Check SI is in progress. If SI is not in progress, then return to procedure step in effect.

RO/BOP RO/BOP identifies that SI is in progress.

ATTACHMENT 10 of 1-E-0 RO/BOP 2. Identify Ruptured SG by one of the following conditions:

  • Unexpected rise in any SG Narrow Range level
  • High radiation from any SG MS line monitor
  • High radiation from any SG Blowdown line With SRO concurrence identifies B SG as the ruptured SG ATTACHMENT 10 of 1-E-0 RO/BOP 3. Check running or start AFW Pumps, as necessary
  • 1-FW-P-3A
  • 1-FW-P3B
  • 1-FW-P-2 ATTACHMENT 10 of 1-E-0 RO/BOP 4. When ruptured SG Narrow Range level is greater than 12%, then isolate feed flow to ruptured SG by closing SG AFW Isolation MOVs:
  • SG B, 1-FW-MOV-151C and 1-FW-MOV-151D RO/BOP closes 1-FW-MOV-151C/D when SG level is greater than 12% Narrow Range.

Completion of Critical Task: WOG - A; Isolate feed flow into and steam flow from ruptured SG before a transition is made to ECA-3.1. STOP Time: _________.

ATTACHMENT 10 of 1-E-0 RO/BOP 5. Select the ruptured SG AFW MOVs using the following switches:

  • H TRAIN DISABLE SELECTOR SWITCH
  • J TRAIN DISABLE SELECTOR SWITCH

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 53 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

RO/BOP ATTACHMENT 10 of 1-E-0

6. Disable the auto-open signal for the selected MOVs by placing the following keyswitches in the DISABLE SELETED position:
  • H TRAIN AUTO OPEN ENABLE SWITCH
  • J TRAIN AUTO OPEN ENABLE SWITCH ATTACHMENT 10 of 1-E-0 RO/BOP CAUTION: At least one SG must be maintained available for RCS heat sink.
7. Locally close steam supply valve to the TD AFW pump:
  • 1-MS-120 RO/BOP directs field operator to close 1-MS-120.

The field operator will acknowledge the requirement to close 1-MS-120. The field operator will later report that 1-MS-120 is closed.

ATTACHMENT 10 of 1-E-0 RO/BOP 8. Control Feed Flow to the SG IAW the following requirements:

  • Minimum AFW flow is 350 gpm with SI initiated, until one SG Narrow Range level is greater than 12%
  • When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50%.
  • SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
  • SG C, 1-FW-MOV-151A and 1-FW-MOV-151B End EVENT #7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 8 Page 54 of 92 Event

Description:

1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.

Time Position Applicants Action or Behavior 1-ECA-3.3 Actions SRO 1. CHECK RUPTURED SG(S) NARROW RANGE LEVEL - LESS THAN 75%

[73%]

RO Reports that B SG Level is greater than 75%.

1. RNO - GO TO Step 6 SRO 6. CHECK IF SI CAN BE TERMINATED:

a) Check RCS subcooling based on CETCs - GREATER THAN 30°F [85°F]

RO/BOP Identifies that RCS subcooling is greater than 30°F.

b) Check secondary heat sink:

  • Total feed flow to SGs - GREATER THAN 350 GPM [450 GPM]

AVAILABLE OR

  • Narrow range level in at least one intact SG - GREATER THAN 12%

[18%]

RO/BOP Identifies A and C SG NR level >12% OR identify >350 gpm flow Available.

c) Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs RVLIS INDICATION Running Full Range Dynamic Range 0 GREATER THAN 63%

1 GREATER THAN 36%

2 GREATER THAN 51%

3 GREATER THAN 82%

RO/BOP Identify that RVLIS Full Range is Greater than 63%.

d) Check any ruptured SG narrow range level - INCREASING IN AN UNCONTROLLED MANNER OR OFFSCALE HIGH BOP BOP will identify that B SG Level is Off-Scale High.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 8 Page 55 of 92 Event

Description:

1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.

SRO 7. STOP ALL BUT ONE CHG PUMP AND PUT IN AUTO RO Secure one of the running charging pumps SRO 8. ISOLATE HHSI TO COLD LEGS:

a) Verify the following:

RO 1) CHG pump suctions from RWST - OPEN

  • 1-CH-MOV-1115B
  • 1-CH-MOV-1115D
2) Check CHG pump miniflow recirc valves - OPEN
  • 1-CH-MOV-1275A
  • 1-CH-MOV-1275B
  • 1-CH-MOV-1275C
  • 1-CH-MOV-1373 b) Close HHSI to Cold Leg:
  • 1-SI-MOV-1867C RO
  • 1-SI-MOV-1867D
  • 1-SI-MOV-1842 SRO 9. ESTABLISH CHARGING FLOW:

a) Close CHG flow control:

RO

  • 1-CH-FCV-1122 a) b) Check CHG line isolation - OPEN
  • 1-CH-HCV-1310A c) Open CHG line isolation MOVs RO
  • 1-CH-MOV-1289A
  • 1-CH-MOV-1289B RO d) Establish at least 40 gpm charging flow using CHG flow control

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 8 Page 56 of 92 Event

Description:

1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.

SRO 10. CHECK SI FLOW NOT REQUIRED:

  • RCS subcooling based on CETCs - GREATER THAN 30°F [85°F]
  • Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs RVLIS INDICATION Running Full Range Dynamic Range 0 GREATER THAN 63%

1 GREATER THAN 36%

2 GREATER THAN 51%

3 GREATER THAN 82%

RO Reports Full Range RVLIS >63%.

END Event 8 End Scenario

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 57 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

ATTACHMENT 1 OF E-0 BOP 1. CHECK FW ISOLATION:

  • Feed pump discharge MOVs - CLOSED
  • 1-FW-MOV-150A
  • 1-FW-MOV-150B
  • MFW pumps - TRIPPED
  • Feed REG valves - CLOSED
  • SG FW bypass flow valves - DEMAND AT ZERO
  • SG blowdown TVs - CLOSED BOP 2. CHECK CTMT ISOLATION PHASE I:
  • Phase I TVs - CLOSED
  • 1-CH-MOV-1381 - CLOSED
  • 1-SV-TV-102A - CLOSED
  • PAM isolation valves - CLOSED
  • 1-DA-TV-103A
  • 1-DA-TV-103B BOP will identify 1-DA-TV-100A/B, and 1-MS-TV-109 OPEN and CLOSE them.

BOP 3. CHECK AFW PUMPS RUNNING:

a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 58 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of E-0 BOP 4. CHECK SI PUMPS RUNNING:

  • CHG pumps - RUNNING
  • LHSI pumps - RUNNING BOP starts 1-SI-P-1B 1-SI-P-1B START TIME: _____ (for critical task verification, CT-1)

BOP 5. CHECK CHG PUMP AUXILIARIES:

  • CHG pump CC pump - RUNNING
  • CHG pump SW pump - RUNNING
6. CHECK INTAKE CANAL:

BOP

  • Level - GREATER THAN 24 FT
  • Level - BEING MAINTAINED BY CIRC WATER PUMPS
7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:

a) Check if ANY of the following annunciators - HAVE BEEN LIT

  • E-F-10 (High Steam Flow SI)
  • B-C-4 (Hi Hi CLS Train A)

BOP

  • B-C-5 (Hi Hi CLS Train B)

Identifies annunciators not lit and goes to step 8.

BOP *8. CHECK IF CS REQUIRED:

a) CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 59 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of E-0 BOP *10. BLOCK LOW PRZR PRESS SI SIGNAL:

a) Check PRZR pressure - LESS THAN 2000 psig b) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c) Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.

BOP *11. BLOCK LOW TAVE SI SIGNAL:

Step may not be performed at this time (if Tave is greater than 543°F).

a) Check RCS Tave - LESS THAN 543°F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c) Verify Permissive Status light F LIT NOTE:

  • CHG pumps should be run in the following order of priority: C, B, A.
  • Subsequent SI signals may be reset by re-performing Step 12.

BOP 12. CHECK SI FLOW:

a) HHSI to cold legs - FLOW INDICATED

  • 1-SI-FI-1961 (NQ)
  • 1-SI-FI-1962 (NQ)
  • 1-SI-FI-1963 (NQ)
  • 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c) Reset SI.

d) Stop one CHG pump and out in AUTO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 60 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of E-0 e) RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:

1) Verify reset or reset SI.
2) Stop one LHSI pump and put in AUTO.

1-SI-P-1A or 1B STOP TIME: ______

3) GO TO Step 13.

Critical Task: Secure one LHSI pump within 30 minutes of two LHSI pumps in service. [SPS E-1G, CT-1]

Note: If 1-SI-P-1B was not started on Step 4 of Attachment 1, CT becomes Not Applicable.

BOP 13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]

BOP 14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.

BOP 15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next page of this guide)

Depending on timing, this attachment may have already been completed.

BOP 16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Identify failure of 1-VS-MOD-103A CLOSES the MOD.

Unit 2 Operator will state that Unit 2 is at 100% power (if asked)

Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 61 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Time Position Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 BOP NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.

ATTACHMENT 2 of 1-E-0 BOP 1. Check opened or open CHG pump suction from RWST MOVs.

  • 1-CH-MOV-1115B
  • 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 BOP 2. Check closed or close CHG pump suction from VCT MOVs.
  • 1-CH-MOV-1115C
  • 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 BOP 3. Check running or start at least two CHG pumps. (listed in preferred order)
  • 1-CH-P-1C
  • 1-CH-P-1B
  • 1-CH-P-1A ATTACHMENT 2 of 1-E-0 BOP 4. Check opened or open HHSI to cold legs MOVs.
  • 1-SI-MOV-1867C
  • 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 BOP 5. Check closed or close CHG line isolation MOVs.
  • 1-CH-MOV-1289A
  • 1-CH-MOV-1289B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 62 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

ATTACHMENT 2 of 1-E-0 BOP 6. Check closed or close Letdown orifice isolation valves.

  • 1-CH-HCV-1200A
  • 1-CH-HCV-1200B
  • 1-CH-HCV-1200C RO/BOP will CLOSE 1-CH-HCV-1200A and 1-CH-HCV-1200B ATTACHMENT 2 of 1-E-0 BOP 7. Check opened or open LHSI suction from RWST MOVs.
  • 1-SI-MOV-1862A
  • 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 BOP 8. Check opened or open LHSI to cold legs MOVs.
  • 1-SI-MOV-1864A
  • 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 BOP 9. Check running or start at least one LHSI pump.
  • 1-SI-P-1A
  • 1-SI-P-1B BOP Would have started 1-SI-P-1B as part of attachment 1.

ATTACHMENT 2 of 1-E-0 BOP 10. check High Head SI flow to cold legs indicated.

  • 1-SI-FI-1961
  • 1-SI-FI-1962
  • 1-SI-FI-1963
  • 1-SI-FI-1943 or 1-SI-FI-1943A

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 63 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

ATTACHMENT 2 of 1-E-0 BOP 11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.

  • Alternate SI to Cold legs
  • Hot leg injection

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 64 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 65 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 66 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 67 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

If asked, Unit 2 has throttled Chilled Water flow as required by CAUTION prior to Step 10.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 68 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

If asked, pressure indicated on PDI-118, 116, 215, and 206 equals the pressure indicated on PDI-100/101/200/201 pressure indicators.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 69 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Unit 2 will assume responsibility for this attachment at this point.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 70 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 71 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 72 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 73 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 74 of 92 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:

Recall IC -261 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.

Acknowledge AAC System Alarm on Waste Disposal Panel Open the monitor window and add the following points to it:

  • asp_ao_off
  • MS-120, B Steam Supply to TDAFW Pump Enter the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Type (Auto or Manual)

RC4903 PRZR LEVEL XMTR CH 10 20 1 0.0 -0.2 Manual 3 FAILURE (461)

FW1803 B S/G MN FD FLOW 10 0 3 0.0 1 Manual XMTR FT-1487 FAILS SD0201 HP HTR DRN PP SD-P-1A 10 0 5 FALSE TRUE Manual TRIPS: OVR-CURRENT RC2402 STEAM GENERATOR B 10 60 9 0.0 8 Manual TUBE RUPTURE PCV455C_OPEN PCV-1455C 0 0 11 OFF OFF Manual PRZR RELIEF VALVE OPEN PCV455C_CLOSE PCV-1455C 0 0 11 OFF ON Manual PRZR RELIEF VALVE CLOSE RCMOV535_BKR RC-MOV-535 0 0 16 1 0 AUTO PORV Block Valve RC5601 RC-P-1A BKR 15A3 0 0 17 FALSE TRUE AUTO SPURIOUS TRIP RC5602 SPURIOUS TRIP RCP 1B 0 0 17 FALSE TRUE AUTO RC5603 SPURIOUS TRIP RCP 1C 0 0 17 FALSE TRUE AUTO AS02 DISABLE SV-TV-102 OPEN 0 0 30 FALSE TRUE ACTIVE AS05 DISABLE SV-TV-103 0 0 30 FALSE TRUE ACTIVE CLOSE SI2409 SI RELAY CI1A FAILS TO 0 0 30 FALSE TRUE ACTIVE ACTUATE SI2505 SI RELAY SI5B FAILS TO 0 0 30 FALSE TRUE ACTIVE ACTUATE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 75 of 92 SIMULATOR OPERATORS GUIDE Enter the following EVENT TRIGGERS:

Trigger# EVENT Command Trigger setup to trip 1-RC-MOV1535 breaker when control switch in open to stroke test open time, Event 1.

Trigger 14 sets when 1-RC-MOC-1535 closed. Trigger 15 sets when 1-RC-MOV-1535 control switch taken to open. Trigger 16 set when both Trigger 14 and 15 are TRUE. Trigger 16 implements Remote Function trip of 1-RC-MOV-1535 breaker.

14 "rcmov535 .le. 0.0002" Sets Trigger 14 15 "mov535_open" Sets Trigger 15 16 "et_array(14) .and. et_array(15)" Sets Trigger 16 Trigger setup to trip A, B, C, RCPs when Generator Output breakers open. (EL2 Auto Trigger). Actuates Trigger which implements Malfunction RC5601/5602/5603.

17 ".not. (elg102_bkr(2) .and. Sets Trigger 17 elg1t240_bkr)"

Trigger setup to override 1-RC-LCV-1460A and B control switch to Open to simulate removing PRZR level control output fuses.

20 "chw180<500.0" Set Trigger 20 when Letdown flow < 1 gpm.

21 "chlcv460a_open" Set Trigger 21 when 1-CH-LCV-1460A switch taken to Open.

22 "chlcv460b_open" Set Trigger 22 when 1-CH-LCV-1460B switch taken to Open.

23 "et_array(20) .and. et_array(21)" Sets Trigger 23 when Trigger 20 and 21 are ACTIVE.

Actuates override for 1-CH-LCV-1460A switch in Open 24 "et_array(20) .and. et_array(22)" Sets Trigger 24 when Trigger 20 and 22 are ACTIVE.

Actuates override for 1-CH-LCV-1460B switch in Open Enter the following Remote Functions:

Override Set Condition Trigger AAC_SMS_MODE OFF AAC DG OFF 30 LOCAL MODE SWITCH POSITION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 76 of 92 SIMULATOR OPERATORS GUIDE Enter the following Switch Overrides:

Override Set Condition Trigger Override CH LCV-460A OPEN ON 23 Override CH LCV 460B OPEN ON 24 TRIGGER TYPE DESCRIPTION 1 MAN Fails PZR Level CH III to ~34%.

3 MAN B SG MN Feed Flow Transmitter fails high.

5 MAN Trip running High Pressure Drain Pump Steam Generator Tube Leak, 74 gpm 9 MAN 11 MAN Overrides 1-RC-PCV-1455C control switch Open OFF, Close ON 16 AUTO Open Breaker to 1-RC-MOV-1535 17 AUTO Spurious Trip A/B/C RCPs when Gen. Output Bkrs open 23 AUTO Overrides 1-CH-LCV-1460A control switch Open.

24 AUTO Overrides 1-CH-LCV-1460B control switch Open.

AS02 DISABLE SV-TV-102 OPEN AS03 DISABLE SV-TV-103 CLOSE SI2409 SI RELAY CI1A FAILS TO ACTUATE 30 ACTIVE SI2505 SI RELAY SI5B FAILS TO ACTUATE AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 77 of 92 SIMULATOR OPERATORS GUIDE Verify the following control room setup:

Place the simulator in RUN and verify normal 100% power operation indications.

Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:

Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).

Verify Ovation System operating.

Reset ICCMs.

Verify Component Switch Flags.

Verify Brass Caps properly placed.

Verify SG PORVs set for 1035 psig.

Verify Rod Control Group Step Counters indicate properly.

Verify Ovation CRT display.

Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)

Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:

AP-53.00 AP-18.00 AP-23.00 AP-16.00 E-0 E-3 (2) ECA-3.3 OP-CH-007 Reactivity Sheet OP-ZZ-002 PT-18.6I Verify Reactivity Placard is current.

Verify ALL PINK MAGNETS are accounted for.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 78 of 92 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

Ask for and answer questions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 79 of 92 SIMULATOR OPERATORS GUIDE Conduct shift turnover:

The initial conditions have Unit 1 at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance. In accordance with VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training. A BAST boron concentration is 8.0 w/%.

Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, Pressurizer Block Valve Stroke Test. Performance of PT-18.6I has been authorized and has been PSA analyzed for current plant conditions.

When the team has accepted the shift, proceed to the Session Conduct Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 80 of 92 SIMULATOR OPERATORS GUIDE Session Conduct:

  • Ensure conditions in Simulator Set-up are established.
  • Ensure Trigger 30 is active prior to team entering the simulator.
  • Verify Exam Security has been established and ASP_AO_OFF = True.

EVENT 1 Test Cycle PORV Block Valves, 1-PT-18.6I BOOTH:

30 minutes prior to the beginning of the scenario, provide the team with a copy of 1-PT-18.6I, Pressurizer Block Valve Stroke Test. The team will pre-brief the PT prior to entering the simulator.

Trigger setup to trip 1-RC-MOV1535 breaker when control switch in open to stroke test open time, Event 1. Monitor the following triggers as 1-RC-MOV-1535 is closed/opened.

Trigger 14 sets (becomes Active) when 1-RC-MOC-1535 closed.

Trigger 15 sets (becomes Active) when 1-RC-MOV-1535 control switch taken to open.

Trigger 16 sets when both Trigger 14 and 15 are TRUE.

Trigger 16 implements Remote Function to trip 1-RC-MOV-1535 breaker.

Operations Supervisor/Management/Work Week Coordinator:

  • If contacted, will acknowledge 1-RC-MOV-1535 breaker tripped when the valve was re-opened, suspension of the PT, and Tech Spec Clock identified (1 hour/72 hour).

Field Operator: (3 minute delay from request to answer)

  • If Contacted, as Service Building Operator, to check the status of 1-RC-MOV-1535 breaker, 1H1-2S 6A; report that the breaker has tripped (in the trip free position).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 81 of 92 SIMULATOR OPERATORS GUIDE EVENT 2 PRZR Level Transmitter 1-RC-LI-1461 Fail to 34%, 0-AP-53.00.

When cued by examiner, implement Trigger #1.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00.
  • If contacted, ask for SRO recommendation for performing 1-OP-RP-001, Shift Manager will call back).
  • If contacted, will take responsibility for writing the CR.

STA:

  • If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge (but not confirm/deny) any TS LCOs.
  • If asked, the STA will report that 1-RC-LI-1461 is a Reg. Guide 1.97 component. The STA will also report that review of CEP 99-0029 has been discussed with the Shift Manager.
  • If asked, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Field Operators:

Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge instrumentation failure and commence investigations and/or efforts to place the channel in trip.

Unit 2 Operator:

  • No action for this event.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 82 of 92 SIMULATOR OPERATORS GUIDE EVENT 3 Feed Flow Channel Fails High, 0-AP-53.00.

When cued by examiner, implement Trigger #3.

Operations Supervisor/Management:

  • If contacted, acknowledge feed flow channel failure. The individual(s) contacted will also acknowledge any TS LCOs.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into AP-53.00.
  • If contacted, will ask SRO for recommendation concerning performance 1-OP-RP-001. Shift Manager will call back.

STA:

  • If contacted, will acknowledge feed flow channel failure. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
  • If contacted, will take responsibility for writing the CR.
  • When asked: Failed channel is a RG 1.97 variable.
  • When asked, CEP-0029 has been reviewed and discussed with the Shift Manager. VPAP-2802 and TRM section 3.3 have been reviewed and discussed with the Shift Manager.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Field Operators:

  • Will perform actions as directed.

Maintenance/ Work Week Coordinator:

  • If contacted, will acknowledge the feed flow channel failure and contact I&C to commence preparation to place the failed channel in trip.

Unit 2:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 83 of 92 SIMULATOR OPERATORS GUIDE

  • If contacted, will acknowledge the failure of the feed flow channel.

Role-play as other individuals as needed.

EVENT 4 Loss of HPD, 1-AP-18.00.

When the Evaluator indicates Ready, Activate Trigger #5.

Operations Supervisor/Management:

  • If contacted, will acknowledge the trip of 1-SD-P-1A, and the need to ramp at 1%/minute to 75%

power.

  • If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC, the Shift Manager will direct a 1%/minute ramp rate.

STA:

  • If contacted, will acknowledge the trip of 1-SD P-1A and the need to ramp at 1%/minute to 75%

power.

  • If asked, the STA will acknowledge the need to borate and use rods (will acknowledge the team review of pre-planned reactivity plans and OP-RX-010, if performed). If asked to perform the OP-RX-010 review, the STA will state that he is not able to at this time.
  • After directed, the STA will report that VPAP-2802 has reviewed and discussed with the hift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
  • When contacted: EPIPs have been reviewed with the Shift Manager.

Maintenance/ Work Week Coordinator:

  • If contacted, will acknowledge the failure and notify electrical maintenance to investigate.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 84 of 92 SIMULATOR OPERATORS GUIDE

  • If contacted, will acknowledge the requirements to reduce reactor power.

Field Operators: (Wait three (3) minutes from direction of a local action to the report of local condition found.)

  • If contacted, the condensate polishing building operator will acknowledge the need to ramp the unit.
  • If asked, the condensate polishing building operator acknowledge bypass of the polisher.
  • When contacted, as the Service Building Operator concerning the status of 1-SD-P-1A power supply breaker, 1-EP-BKR-15B6, report that the breaker is open with a timed overcurrent drop on A phase.
  • When contacted, as the Turbine Building Operator to check the status of 1-SD-P-1A, report that there are no apparent abnormalities other than the A HPD pump has tripped and HPD tank high level divert, 1-SD-FCV-107, is diverting to the condenser.

Unit 2:

  • If contacted, will acknowledge the trip of 1-SD-P-1A and the need to ramp at 1%/minute to 75%

power.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 85 of 92 SIMULATOR OPERATORS GUIDE EVENT 5 Ramp to 75%, 0-AP-23.00.

Operations Supervisor/Management:

  • If contacted, will acknowledge Ramp to 75% required due to the loss of 1-SD-P-1A.
  • If contacted, will take responsibility for writing the CR.
  • When contacted: The Shift Manager will review EPIPs for applicability. They are not applicable.

STA:

  • If contacted, will acknowledge the impending ramp to 75% power.
  • If contacted, will take responsibility for writing the WR and CR.
  • When contacted: The STA reports that VPAP-2802 has been reviewed discussed with the Shift manager.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them. STA will acknowledge reactivity plan developed by RO/SRO.

Unit 2 Operator:

  • If notified of Ramp: Acknowledge ramp of Unit 1.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 86 of 92 SIMULATOR OPERATORS GUIDE EVENT 6 SGTL 74 gpm, A/E RM Auto Actions Fail, RCPs Trip on swap to RSST.

When the Evaluator is ready and the Blender is in AUTO, implement Trigger # 9.

Note: It would be preferable to wait until power is <80% to implement this failure to allow for ramp stabilization prior to creating RCS leak to allow the team to assess leakrate with more precision.

Operations Supervisor/Management:

  • If contacted, will acknowledge RCS leakage into the B SG. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.
  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into AP-16.00.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 87 of 92 SIMULATOR OPERATORS GUIDE STA:

  • If contacted, will acknowledge the RCS leakage into the B SG.
  • If asked to calculate the RCS leak rate, state that it is difficult to ascertain at this time, but you will continue to monitor as time permits.
  • If contacted, will take responsibility for writing the WR and CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.

Health Physics:

  • If contacted, will acknowledge B SGTL.

Role play as other individuals as needed.

Operations Supervisor/Management:

  • If contacted, will acknowledge the SGTR on B SG.
  • If contacted, will acknowledge the isolation of B SG (if informed).

Field Operators:

  • If contacted, to report abnormalities on RCPs, report no 86 devices drops apparent on RCP breakers, but the Speed Sensing Panel appears to be malfunctioning; lights blinking on and off.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 88 of 92 SIMULATOR OPERATORS GUIDE EVENT 7 SGTL becomes SGTR (710) gpm). 0-AP-16.00, E-0, E-3.

Notify Examiner when B SG NR level reaches 12%. To increase SGTL to SGTR, double click on RC2402, set DEG at 79%, 60 sec ramp, Insert.

After the SGTR implemented, Actuate Trigger 11 to fail PORV 1455C control switch.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will acknowledge entry into 1-E-0, 1-E-3.
  • If contacted, will acknowledge the SGTR on B SG.
  • If contacted, will acknowledge the isolation of B SG (if informed).

STA:

  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.

Unit Two:

  • If asked, blowdown and air ejector RM readings are [as indicated at the time].
  • If requested, acknowledge RM alarms, and perform ARP actions.
  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
  • If asked: Unit 2 RWST cross-ties are open.
  • If asked: take responsibility to notify HP of B SG PORV lifting.

Field Operators:

  • If contacted, field operators will perform valve manipulations as required:
  • 1-MS-120 - set ms_120 to zero upon request

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 89 of 92 SIMULATOR OPERATORS GUIDE

  • Acknowledge direction to place Number 1 and 2 Turbine Building Sump pumps in OFF locally, and initiate 0-OSP-PL-003, Turbine Building Sump Pump Status Verification.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 90 of 92 SIMULATOR OPERATORS GUIDE EVENT 8 PZR PORV 1-RC-PCV-1455C not open, 1-ECA-3.3.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will acknowledge entry into 1-ECA-3.3.
  • If contacted, will acknowledge the SGTR on B SG.
  • If contacted, will acknowledge the isolation of B SG (if informed).

STA:

  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.

Unit Two:

  • If asked, blowdown and air ejector RM readings are [as indicated at the time].
  • If requested, acknowledge RM alarms, and perform ARP actions.
  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.

Field Operators:

  • If contacted, field operators will perform vale manipulations as required:
  • 1-MS-120 - set ms_120 to zero upon request

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 91 of 92 SIMULATOR OPERATORS GUIDE EVENT 9 BOP Failures, 1-SI-P-1B no auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.

Unit Two:

  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
  • If asked, MRC differential pressure is a found.
  • If asked, Unit 2 has throttled Chilled Water flow IAW E-0, Attachment 3 guidance.

Field Operators:

  • If contacted, field operators will perform valve manipulations as required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 92 of 92 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge the failures and commence investigations.

HP:

  • If contacted, will acknowledge B SGTR.

STA:

  • If asked, will report that he will calculate the time to B fill, time permitting.
  • If contacted, will enter the control room and commence reviewing status trees and prepare for the transient brief (items are reported as you see them or previously reported).
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. Radiological conditions are as indicated. He will also state that containment conditions and the electrical conditions are as you see them.

Role play as other individuals as needed.

The scenario will end upon reaching Step 11 of 1-ECA-3.3 or at the lead examiners discretion.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 Facility: Surry Power Station Scenario No.: 3 Op-Test No.: 2014-001 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Time in Core Life - Middle of Life; Core Cycle - Cycle 26 Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportablility is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
  • A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.

Event Malf. Event Event No. No. Type* Description N - BOP 1 N/A N - SRO Deleted.

2 RC0801, I - RO Failure of Median Tave in the Low Direction, AP-53.00.

-1 Deg 3 I - BOP MS0801, TS - SRO Failure of Steam Flow Channel III Low, A SG. AP-53.00

-1 Deg C - RO 4 EL4902 TS - SRO 1J 4160V emergency Bus Off-site Power Supply Breaker Trips.

Switch Test Button on Main Turbine Control Fails causing the LP Turbine 5 R - RO O/R, TEST_IR R - SRO 1 Intercept and Reheat Stop Valve Closure. AP-23.00 Ramp to N - BOP 71% Power.

L_IIL RC04, RCS leak of 35 gpm. AP-16.00.

6 3.5% Deg C - RO TS- SRO RM0202, 7 +.1 Deg, RM0201, C - BOP Containment Particulate and Gas RM auto actions on High Alarm

+.1 Deg fail to function CA03 CA04 RC0101, 8 .6% Deg M - All SBLOCA. AP-16.00, E-0.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 SETPT 9 for Hi-Hi CLS change to 60 psia.

O/R M - All CLS_AC Hi and HI-HI CLS fail to function, requiring manual alignments of T_TRA C - BOP components, and FR-Z.1 entry.

O/R CLS_AC T_TRB

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
1) Deleted Normal Evolution.

Event #2: Median Tave Fails Low. (I - RO)

The RO will diagnose this failure due to Rod motion and alarms received. The RO will place Rod Control to manual and place charging flow to manual IAW the Immediate Actions Steps of 0-AP-53.00, Loss of Vital Instrumentation/Controls. Following a short brief, the Team will complete AP-53.00.

Verifiable Actions:

1) RO/BOP will place Rod Control in manual to stop outward rod motion.
2) RO will place charging flow in manual and maintain Pressurizer level at program.

Technical Specifications:

1) Should the SRO review Tech Specs, no items will be found.

Technical Requirements Manual/RG 1.97

1) No TRM or RG 1.97 requirements are associated with this failure.

Event #3: Steam Flow Channel III Fails Low on A SG. (I - RO, TS-SRO)

The BOP will diagnose the failure based upon alarms and indications received, place the A FRV in manual to control A SG NR level, and restore SG NR level to program IAW 0-AP-53.00, Loss of Vital Instrumentation/Controls.

The affected channel of Steam Flow will be de-selected and the A FRV returned to automatic.

Verifiable Actions:

1) The BOP will place the A FRV in manual and restore the A SG NR level to program.
2) The RO will de-select the failed channel.
3) The BOP will return the A FRV to automatic.

Technical Specifications:

SRO will Review Technical Specifications and determine:

1) Tech Spec Table 3.7-1, Item 17, Operator Action 6. With the Number of Operable Channels less than the Total Number of channels, Operation may continue provided the channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, The channel may

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 be bypassed for 12 for surveillance testing, and if the requirement cannot be met be in at least Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

2) Tech Spec Table 3.7-2, Item 1.e. High Steam flow in 2/3 steam lines coincident with Low Tavg or low steam line pressure, Operator Action 20. With the number of Operable channels less than the Total number of channels, Operation may continue provided the channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the channel may be bypassed for surveillance for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If these conditions are not satisfied in the time permitted, be in Hot Shutdown in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to < 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3) Tech Spec Table 3.7-3, Item 2a, Steam line Isolation, refers to requirements listed in 2) above.

Technical Requirements Manual/R.G. 1.97.

1) TRM - No requirements listed for this failure in section 3.3.2, Appendix R Instrumentation.
2) RG 1.97 - Attachment 1, D-19 Variable, 1 Channel per SG required.

Event #4: Loss of 1J 4160V Emergency Bus, Breaker 15J8 opens, #3 EDG Starts and Loads on 1J Bus. (C - RO, TS - SRO).

The Team will diagnose the loss of the 1J Emergency Bus and Start and Load of #3EDG on the bus based on alarms and indications received. The SRO will enter 1-AP-10.07, Loss of Unit 1 Power and proceed through the procedure until the end is reached.

Verifiable Actions:

1) BOP/RO will start the B CH pump to provide load to the #3EDG.
2) BOP/RO will secure the A and C CH pumps.
3) RO will place the B CC pump in PTL in order to re-close the J stub bus tie breaker.
4) RO will start A CC pump.

Technical Specifications:

1) The SRO will consult Tech Specs 3.16.B.2 and determine the Unit may be operated for 7 days provided the dependable alternate source can be OPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. SRO will consult with the Shift Manager concerning whether the Dependable alternate source can be Operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
2) SRO may refer to Tech Spec 3.6.I and determine AFW cross-tie clock is not required.
3) SRO will identify 6/30 clock Tech Spec 3.16, while the alignment of running charging pumps is made using 1-AP-10.07, Attachment 4.

Technical Requirements Manual / RG 1.97:

1) No TRM or RG 1.97 requirements are affected by this event. (The identification of TRM items is normally an STA function - follow-up question post-scenario is recommended at Lead Evaluator discretion.)

Event #5: #1 LP Turbine Left Intercept and Reheat Stop Valve Close, (R - RO, R - SRO, N -

BOP)

The RO/BOP will diagnose this failure based Indications received. The Team will initiate AP-53.00/AP-38.00 and determine that a power reduction to 71% is required using 0-AP-23.00, Rapid Load Reduction.

Verifiable Actions:

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3

1) RO will manipulate the CVCS system to Emergency Borate and establish a continuous boration to control RCS Tave during the Turbine Ramp.
2) RO will use control rods to adjust delta flux and assist in RCS Tave control.
3) BOP will operate Turbine controls to reduce turbine load.

Technical Specifications/TRM/RG-1.97:

1) None associated with this Failure.

Event #6: RCS leak of 35 gpm. (C - RO, TS-SRO)

Following completion of the ramp, the RCS leak will be initiated. The RO will perform 1-AP-16.00, Excessive RCS Leakage, Immediate Actions to quantify the leakage.

Verifiable Actions:

1) The RO will isolate letdown and control charging flow in manual to quantify RCS leakage.

Technical Specifications:

1) The SRO should consult Tech Specs Section 3.1.C, RCS leakage, and identify that RCS leakage is in excess of the allowed maximum and enter a second 6/30 clock to be in HSD/CSD.

Event #7: Failure of RM-159/160 auto actions. (C - BOP)

As the Team is responding to the RCS leak, RM-159/160 for containment Particulate and Gas Rad Monitors will alarm. The BOP will respond using the associated ARPs and determine that the auto functions for these RMs have not occurred. The BOP will follow the ARP guidance and swap containment Instrument Air compressor suction to the external source.

Verifiable Actions:

1) The BOP will swap containment instrument air compressors to outside suction by closing 1-IA-TV-101A and 1-IA-TV-101B.

Technical Specifications:

1) The SRO may consult Tech Specs and find no requirement for this failure.

Event #8: SBLOCA. (M - ALL)

The RO will diagnose the increase in RCS leakage due to the alarms and indications received, and re-perform the Immediate Actions of 1-AP-16.00. When leakage is determined to be greater than the capacity of a single CH pump, The RO will trip the reactor, perform the Immediate Actions of E-0, and manually safety inject on Step 4.

Due to the size of the RCS leak, several minutes will elapse before RCP trip criteria are met following the reactor trip.

Verifiable Actions:

1) RO will raise charging flow and determine leakage is beyond the capacity of single charging pump.
2) RO will trip the reactor and perform the Immediate Action Steps of E-0, including manual Safety Injection actuation.

Critical Task:

CT-1: WOG E-1C: Trip all RCPs so that CET temperatures do not become superheated when forced circulation in RCS stops; Trip all

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 RCPs within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).

Event #9: Failure of Hi and Hi-Hi CLS auto and manual actuation The RO and SRO will continue with E-0 actions; the BOP will be assigned to perform Attachments 1, 2, and 3 of E-0. Upon transition to 1-E-1, Loss of Reactor or Secondary Coolant, containment pressure will have increased to the Hi and HI-HI CLS setpoint (~13 minutes following Event initiation), and CLS Train A and Train B pushbuttons overridden OFF will force entry into FR-Z.1 to start Containment Depressurization equipment.

Verifiable Actions:

1) BOP will reset SI, block SI signals when conditions permit, secure one of the three running CH pumps, and secure one of the two running LHSI pumps.
2) RO will throttle AFW to the SGs as directed in E-0.
3) RO will operate the CS pumps and valves to align CS to containment for depressurization in FR-Z.1, Response to High Containment Pressure.
4) BOP will continue manual alignment of valves for Hi and Hi-Hi CLS failure in Attachment 4 of E-0 following transition from FR-Z.1 to 1-E-1.

Critical Task:

CT-2: WOG E-0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (red-path) challenge develops to the CSF. Establish CS flow from at least one CS pump before containment pressure exceeds 60 psia AND at least one RS train before RMT.

Scenario should continue until Lead Evaluator Cue or Step 18 of 1-E-1.

Follow-up Classification: Site Area Emergency FS-1.1.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 Initial Conditions: IC #1 100%, MOL - Cycle 26. The unit has been at 100% power for > 30 days Pre-load malfunctions: (Trigger 30s) o Override Hi CLS Act pushbutton - TRA o Override HI CLS Act pushbutton - TRB o AC_SMS_MODE, OFF, AAC DG LOCAL MODE SWITCH POSITION o RS0901, TRN A HI CLS FAILS TO ACTIVATE o RS0902, TRN B HI CLS FAILS TO ACTIVATE Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

. Unit 1 is at 100% power. All systems and crossties are operable with the following exception:

o AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Turnover:

Unit 1 is at 100% power. All systems and crossties are operable with the following exception:

AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. . IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

  • A BAST 8.0 w/%.

Event Malf. #s Severity Instructor Notes and Required Feedback 1 N/A Deleted 2 RC0801 -1 Deg Failure of Median Tave in the Low Direction, AP-53.00.

3 MS0801 -1 Deg Failure of Steam Flow Channel III Low, A SG. AP-53.00 4 EL4902 TRUE 1J 4160V emergency Bus Off-site Power Supply Breaker Trips.

Switch 5 O/R, Test Button on Main Turbine Control Fails causing the LP Turbine 1 ON TEST_IRL Intercept and Reheat Stop Valve Closure. AP-23.00 Ramp to 71% Power.

_IIL 6 3.5%

RC04 Deg RCS leak of 35 gpm. AP-16.00.

RM0202 +.1 Deg

7. RM0201, +.1 Deg Containment Particulate and Gas RM auto actions on High Alarm fail to CA03 TRUE function.

CA04 TRUE

.6 DEG, 8 RC0101 600 Sec SBLOCA Ramp

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 SETPT for 9 Hi-Hi CLS 60 psia O/R CLS_ACT ACTIVE

_TRA Hi and HI-HI CLS fail to function, requiring manual alignments of components, and FR-Z.1 entry.

O/R CLS_ACT ACTIVE

_TRB Scenario Objectives:

A. Deleted.

B. Given a failure of Median Tave in the Low Direction, respond IAW AP-53.00.

C. Given a failure of the selected Steam Flow channel on the A SG, respond IAW AP-53.00 to take manual control of the A FRV, control A SG NR level and return the A FRV to automatic.

D. Given the trip of the off-site power supply breaker to the 1J 4160V Bus and the subsequent start and load of #3 EDG on the bus, respond IAW AP-10.07 to restart/verify proper loads on the 1J bus.

E. Given the malfunction of the 1RL/1LL test pushbutton, respond IAW AP-53.00, AP-38.00, and AP-23.00 to ramp the Unit to 71 % power.

F. Given an RCS leak of 35 gpm, respond IAW AP-16.00 to quantify the leakrate.

G. Given a containment Gas High RM Alarm, respond IAW ARP to verify/perform the associated automatic actions.

H. Given a SBLOCA inside containment with the failure of Hi-Hi-CLS to actuate, respond IAW E-0 and E-1 to respond to the RCS transient; and restore containment depressurization equipment IAW FR-Z.1.

SHIFT TURNOVER INFORMATION OPERATING PLAN:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1.

The last shift performed two 35 gallon alt dilutions followed by a manual makeup for training.

A BAST at 8.0 W/%. .

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 1 Page 9 of 103 Event

Description:

Swap Running EH Pumps, 1-OP-EH-001, Section 5.6.

Cue: When team ready.

Time Position Applicants Action or Behavior EVENT #1 DELETED.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 10 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

Note: An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.

The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.

A facility representative will be present for consultation with the Evaluation Team, as needed.

Time Position Applicants Action or Behavior Diagnoses failure of median Tave with the following indications/alarms:

Team Alarms:

  • 1H-A4, T AVG > < T REF DEVIATION
  • 1G-F8, ROD BANK D WITHDRAW
  • 1C-C8, PRZR HIGH LEVEL HEATERS ON Indications:
  • Median Tave (recorder and indicator) off-scale low
  • Individual Loop Taves indicating NORMAL
  • Control Rods stepping OUT and reactor power decreasing SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS RO [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL RO identifies individual loop Tave indications are normal

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 11 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION RO takes manual control of the control rods to stop the outward rod motion and also takes manual control of pressurizer level control (1-CH-FCV-1122) to maintain pressurizer level at program.

It should be noted that charging might not be placed in manual until procedurally directed.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

SRO Directs BOP to perform Annunciator Response Procedure 1G-F8.

Completes Brief and continues with AP-53.00.

NOTE: 1G-F8 response located at the end of this section.

SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

  • Median Tave, Step 9 RO Identify that Median Tave has failed LOW.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 12 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

SRO Caution prior to step 9:

CAUTION: Delta flux must be monitored and maintained within band if rods have moved.

Note Prior to Step 9:

NOTE: Depending on the instrumentation failure, the TAVE input to the Steam Dumps may be invalid, causing the Steam Dumps to stay open longer or never open at all.

SRO 9. CHECK LOOP/MEDIAN T/Tave - NORMAL a) Median Tave - NORMAL a) RNO - Do the following:

1) Place ROD CONT MODE SEL switch in MANUAL, as required.

RO will report that Rod Control is already in manual.

2) Take manual control of charging, as necessary to maintain pressurizer level at program.

RO will report that charging flow is in manual or will place charging flow in manual.

3) Refer to Attachment 4 (Describes Tave control system)
4) If no other instrumentation failure exists, then go to step 13.

Goes to Step 13 0-AP-53.00 SRO 13. CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001 RO Checks 1-OPT-RX-001, Attachment 4, and determines that the Calorimetric program is unaffected.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 13 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE SRO directs STA to review Reg. Guide 1.97. The STA will report that Median Tave is not a Reg. Guide 1.97 component.

13. RNO - GO TO Step 16 SRO 16. Review the following:
  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA reports that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

SRO 17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS RO Reports no other instrument failure exists.

GOES TO STEP 19 SRO 19. PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC

- END -

Note: If Control Rods stepped out greater than 230 steps, the team will perform ARP 1G-F8. 1G-F8 Actions are contained on the next two pages

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 14 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

1G-F8 (Rod Bank D Withdrawal)

BOP 1. CHECK ALARM - ROD DEMAND POSITION GREATER THAN OR EQUAL TO 228 STEPS ON CONTROL BANK D - GP 1 DEMAND POSITION.

Identifies that Bank D is greater than 230 steps.

1G-F8 (Rod Bank D Withdrawal)

BOP

2. PUT ROD CONTROL MODE SEL SWITCH IN MANUAL.

Verifies that Rod Control is in Manual.

1G-F8 (Rod Bank D Withdrawal)

BOP

3. VERIFY ROD MOTION - STOPPED 1G-F8 (Rod Bank D Withdrawal)
4. CHECK BOTH CONTROL BANK D STEP COUNTERS - LESS THAN OR EQUAL TO 230 STEPS.

If less than 230 steps proceed to Step 5.

RNO -

a) Step rods out to make both Bank D Step Counters equal. (Group step counters must be equalized by stepping out only, to prevent Rod Group Sequence Error).

Steps Rods out as needed to equalize group step counters.

b) Reset Bank D Step Counters to 230 steps.

Uses a stylus to reset the Bank D Step Counters to 230 steps.

1G-F8 (Rod Bank D Withdrawal)

BOP NOTE:

Rods may have to be stepped in as many as two steps below the fully withdrawn position to clear Annunciator 1G-F8.

5. STEP CONTROL BANK D RODS IN AS NECESSARY TO CLEAR 1G-F8, ROD BANK D WITHDRAW.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 15 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

BOP 1G-F8 (Rod Bank D Withdrawal)

6. POSITION CONTROL BANK D RODS AS DETERMINED BY SHIFT SUPERVISION 1G-F8 (Rod Bank D Withdrawal)

BOP NOTE:

Both group step counters for Control Bank D should be the same before performing Step 7.

7. LOCALLY CHECK THE BANK OVERLAP COUNTER - AT 384 PLUS CURRENT CONTROL BANK D DEMAND POSITION.

Contacts a field operator to determine the bank overlap counter.

384 + 228 = 612 Field operator will report bank overlap position as indicated on the simulator.

1G-F8 (Rod Bank D Withdrawal)

BOP

8. NOTIFY SHIFT SUPERVISION END OF EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 16 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior Diagnoses failure 1-MS-FT-1474 with the following indications/alarms:

BOP Alarms:

Indications:

  • Step decrease in 1A SG Steam Flow indication CH-III
  • Decreasing level on A SG.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS BOP [1] VERIFY REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies Channel IV indication for steam flow is NORMAL.

BOP [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of A SG feed reg valve and increases demand (FF >

SF) to restore level to program.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 17 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

Note: Based on the feed flow > steam flow mismatch established by the BOP, Calorimetric power may exceed 100% during restoration of A SG NR level to program.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

SG Steam Flow, Step 7 BOP States A Steam Flow affected.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 18 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.

SRO 7. CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS -

NORMAL

  • Steam Pressure BOP
  • Steam Flow
  • Feed Flow

BOP Step 7. RNO IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level BOP Control system has failed, THEN do the following:

a) Place the associated Feed Reg Valve in MANUAL.

RO Verifies A SG MFRV controller, 1-FW-FCV-1478, in manual b) Control SG level at program level (44%, a band will be given).

BOP Verifies A SG NR level is returning to program level.

c) Select the redundant channel for affected SG(s)

RO Selects Channel IV Steam Flow for A SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV).

d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.

BOP Places A SG FRV controller, 1-FW-FCV-1478, in automatic control

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 19 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

SRO Step 7. RNO (Continued)

Perform follow-up actions:

a) Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.

b) Refer to the following Tech Spec 3.7 items:

  • Table 3.7-1, 12 and 17
  • Table 3.7-2, 1.c, 1.e, and 3.a
  • Table 3.7-3, 2.a, and 3.a Determines Table 3.7-1 item 17, 3.7-2 item 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).

c) Refer to Attachment 1.

d) IF no other instrumentation failure exists, THEN GO TO Step 13.

SRO 13. Review OPT-RX-001, Rx Power Calorimetric using PCS computer program, Attachment 4, to determine operability of calorimetric and need to perform OPT-RX-007, Shift Average Power Calculation.

SRO/RO determines that OPT-RX-001 is NOT impacted and OPT-RX-007 will NOT need to be performed.

If it appears that the SRO/RO will take action to perform 1-OPT-RX-007, the Unit 2 Operator will state that he will perform 1-OPT-RX-007.

Note: Lead Evaluator must concur with Unit 2 action to perform 1-OPT-RX-007.

SRO 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 14 if not Reg. Guide 1.97)

SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-MS-FT-1474 is a Reg. Guide 1.97 component.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 20 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

SRO 15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report review of CEP 99-0029 is complete and has been reviewed with the Shift Manager.

[CEP 99-0029 requires one channel of steam flow indication per SG, with channel available, no further action is required.]

SRO 16. Review the following:

  • TS 3.7 Determines Table 3.7-1 item 17, 3.7-2 item 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).
  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

SRO 17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS BOP Reports no additional failure exists SRO GOES TO Step 19 SRO 19. PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC

- END EVENT #3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 21 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 1-AP-10.07 TEAM Diagnose the failure based on the following:

Alarms:

1K-B8, UPS SYSTEM 1B TROUBLE 1K-D5, CC PP 1B IN LOCAL CONTROL OR OL TRIP 1K-E7, CC PPS DISCH HDR LO PRESS 1B-G5, INST AIR DRYER TROUBLE Indications:

  1. 3 EDG Start and Load on 1J 4160 V Bus.

1-CC-P-1B GREEN and AMBER Breaker Indication Lights LIT.

1-AP-10.07 SRO SRO will hold a Transient Brief and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Directs the BOP to review ARPs for Lit annunciators, SRO/RO will continue with 1-AP-10.07.

Directs RO/BOP to contact Service Building Operator to check local status of Breaker 15 J8.

Completes Brief and continues with AP-10.07.

Step 1, 1-AP-10.07 SRO NOTE:

  • If both units are affected, local actions should be coordinated.
  • The AAC Diesel Generator will automatically start if an undervoltage occurs on Transfer Buses D and F.
  • With Degraded Voltage or Undervoltage on 2J Bus, or a loss of Unit 2B DC Bus, Breaker 15J3 will not close automatically, except with a valid Unit 1 SI signal.
1. CHECK UNIT - BLACKOUT HAS OCCURRED
  • Transfer Buses D and F - DEENERGIZED AND
  • All Station Service Buses - DEENERGIZED RO Reports Blackout has not occurred.

SRO GOES TO Step 39.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 22 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 39, 1-AP-10.07 SRO 39 CHECK THE FOLLOWING BREAKERS - ANY OPEN:

  • 15J8 RO Reports Breaker 15J8 Open.

Step 40, 1-AP-10.07 SRO 40 CHECK 4160V EMERGENCY BUSES - BOTH ENERGIZED RO Reports both Emergency Buses Energized.

Step 41, 1-AP-10.07 SRO 41 CHECK SI OR HI HI CLS - NOT ACTUATED RO Reports SI or HI HI CLS NOT Actuated Step 42, 1-AP-10.07 SRO CAUTION: To prevent overload of EDG 1, the UV trip of 1-CH-P-1A should NOT be reset if 1-CH-P-1C is running on the normal feeder AND the UV trip of 1-CH-P-1C (Normal) should NOT be reset if 1-CH-P-1A is running.

NOTE: A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading..

NOTE: The CHG pumps powered from the 1H Bus receive an auto-start signal when the 1J Bus is deenergized.

42 INITIATE ATTACHMENT 4 TO ALIGN EMERGENCY BUS LOADS TO PREVENT EDG OVERLOADING SRO Directs BOP to perform Attachment 4 of 1-AP-10.07.

Note: Attachment 4 actions listed at the end of this section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 23 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 43, 1-AP-10.07 SRO 43 GO TO STEP 45 Step 45, 1-AP-10.07 SRO NOTE: At least one method of communications should be established before commencing local actions.

45 CHECK COMMUNICATIONS CAPABILITY:

  • Gaitronics OR
  • Station Radios RO Reports Gaitronics and / or Station Radios Available.

Step 46, 1-AP-10.07 SRO 46 CHECK EDG - HAS REENERGIZED AFFECTED EMERGENCY BUS

  • 15H3 - CLOSED OR
  • 15J3 - CLOSED RO Reports 15J3 Breaker closed.

Step 47, 1-AP-10.07 SRO 47 RESTORE EMERGENCY BUS STUB BUS:

a) Put CC PUMP control switch in PTL RO Places 1-CC-P-1B control switch in PTL.

b) Put RHR PUMP control switch in PTL RO Checks 1-RH-P-1B in PTL.

c) Locally close Stub Bus feeder breakers on energized Emergency Buses

  • 15H9 SRO Directs RO to contact Service Building Operator to Close 15J9.

RO Contacts Service Building Operator to Close breaker 15J9 When local report of Breaker 15J9 closed, RO holds Focus Brief to inform the Team, and checks Annunciator 1K-H4 Clear.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 24 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 48, 1-AP-10.07 SRO CAUTION:

  • When the EDG is the only source of power to an Emergency Bus, the associated Component Cooling Pump should NOT be in service if a HI-HI CLS is in progress.
  • Restrictions on CC pump operation do NOT apply below RCS temperature of 350°F.

48 CHECK CC PUMPS - AT LEAST ONE RUNNING RO Reports No CC Pumps running on Unit 1.

SRO Holds Team brief to discuss the start of 1-CC-P-1A. Since CC system is cross-tied and the CC header is pressurized, throttling the CC pump discharge valve prior to start is unnecessary. Team will concur and the brief closed.

SRO Direct RO to Start 1-CC-P-1A.

RO Makes Gaitronics Announcement and Starts 1-CC-P-1A.

Step 49, 1-AP-10.07 SRO 49 PLACE STANDBY CC PUMP IN AUTO-AFTER-STOP SRO Direct RO to Place 1-CC-P-1B in Auto after Stop.

RO Places 1-CC-P-1B in AUTO.

Evaluator Note: At Evaluator discretion, the next Event (Event 5) may be initiated at this time.

Step 50, 1-AP-10.07 SRO 50 CHECK RHR - WAS IN SERVICE RO Reports RHR NOT in service.

SRO GOES TO Step 52.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 25 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 52, 1-AP-10.07 SRO CAUTION:

  • If a HI-HI CLS has occurred on Unit 1, 1-FC-P-1A must not be started on EDG 1 if 1-CS-P-1A is running.
  • If a HI-HI CLS has occurred on Unit 2, 1-FC-P-1B must not be started on EDG 2 if 2-CS-P-1A is running.

NOTE:

52 CHECK SFP COOLING - EITHER PUMP RUNNING RO Reports 1-FC-P-1B Running Step 53, 1-AP-10.07 SRO 53 CHECK INTAKE CANAL LEVEL - STABLE OR INCREASING RO Reports Intake Canal Level 29 feet and Stable.

Step 54, 1-AP-10.07 SRO NOTE: If two CHG pump CC pumps or two CHG pump SW pumps are running, one pump should be secured and placed in AUTO.

54 CHECK CHG PUMP AUXILIARIES:

  • CHG pump CC pump - RUNNING
  • CHG pump SW pump - RUNNING RO Reports 1-CC-P-2A and 1-SW-P-10A Running.

Step 55, 1-AP-10.07 SRO 55 CHECK SEMI-VITAL BUS - POWER HAS BEEN INTERRUPTED RO Reports Semi-Vital Bus Power has not been interrupted.

SRO GOES TO Step 57 Step 57, 1-AP-10.07 SRO 57 CHECK BOTH PRZR PORV BLOCK VALVES - ENERGIZED RO Reports Both PRZR Block Valves energized

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 26 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 58, 1-AP-10.07 SRO 58 CHECK CC TO EXCESS LETDOWN HX - NOT TRIPPED

  • FI-CC-109 RO/BOP Reports FI-CC-109 Flow is Approximately 160 gpm and Stable.

Step 59, 1-AP-10.07 SRO 59 CHECK IA SYSTEM ANNUNCIATORS - NOT LIT:

  • 1B-G5, INST AIR DRYER TRBL

SRO Directs BOP to review the ARPs for the lit annunciators.

BOP Directs Turbine Building Operator to investigate cause for alarms in IA System.

Step 60, 1-AP-10.07 SRO 60 CHECK UNIT CONDITIONS a) PRZR level - STABLE b) PRZR pressure - STABLE c) RCS TAVE - STABLE RO Reports Parameter normal with no abnormal trends.

Step 61, 1-AP-10.07 SRO 61 CHECK VENTILATION FANS - OPERATING

  • Auxiliary BLDG Central
  • Safeguards BOP Reports Auxiliary Building Central and Safeguards fans operating normally

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 27 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 62, 1-AP-10.07 NOTE: Any MCR Chiller that was operating prior to the loss of power will have tripped and the compressor will not automatically restart. The Chiller must be shutdown and then restarted IAW 0-OP-VS-006, Control Room and Relay Room Ventilation System.

SRO 62 CHECK THE FOLLOWING MCR VENTILATION EQUIPMENT -

OPERATING:

  • One Control Room Chiller (Two Control Room Chillers if SI initiated on either unit AND any MCR or ESGR temperature indicator greater than 84°F)

BOP Reports 1-VS-E-4C and 1-VS-E-4E Running.

SRO

  • One Unit 1 Control Room AHU
  • One Unit 2 Control Room AHU

Step 63, 1-AP-10.07 SRO 63 CHECK CRDM FANS - THREE RUNNING BOP Reports Three CRDM Fans Running Step 64, 1-AP-10.07 SRO 64 CHECK CONTAINMENT AIR RECIRC FANS - THREE RUNNING BOP Reports three fans running.

Step 65, 1-AP-10.07 SRO CAUTION:

  • If a HI-HI CLS has occurred on Unit 1, 1-FC-P-1A must not be started on EDG 1 if 1-CS-P-1A is running.
  • If a HI-HI CLS has occurred on Unit 2, 1-FC-P-1B must not be started on EDG 2 if 2-CS-P-1A is running.

NOTE:

65 CHECK SFP COOLING - EITHER PUMP RUNNING RO Reports 1-FC-P-1B Running

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 28 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 66, 1-AP-10.07 SRO 66 CHECK AFW MOVS - BOTH TRAINS ENERGIZED BOP Reports all AFW MOVs energized.

Step 67, 1-AP-10.07 SRO 67 CHECK BORIC ACID ALIGNMENT:

  • One Tank in service
  • One BATP in service BOP Reports 1-CH-P-2A running and aligned to the A BAST.

Step 68, 1-AP-10.07 SRO 68 CHECK CVCS HEAT TRACING PRIMARY AND BACKUP PANELS - ALL ENERGIZED

  • Primary panels 2A1, 2A2, and 2A3 - powered from 1H 480V Bus RO Reports heat tracing panels energized.

Step 69,1-AP-10.07 NOTE: The N-16 and MGPI Radiation Monitors are powered from Breaker 1H1 4B2 or 2H1-1-2D-2 depending on the position of throw-over switch 1-EP-TRS-DB-101 located near MCC 1H1-1.

SRO 69 CHECK RADIATION MONITORS - OPERABLE

  • No sample pump deenergized
  • No flow faults
  • No monitors deenergized
  • Annunciator 0-RMA-C5, PROCESS VENT RAD MON TRBL - NOT LIT
  • Annunciator 0-RMA-D5, VENT STACK #2 RAD MON TRBL - NOT LIT BOP Reports sample pumps energized, No flow faults, No monitors deenergized.

Reports Annunciators 1A-C3, RMA-C5, RMA-D5 - not LIT.

Step 70, 1-AP-10.07 NOTE: The CTMT Particulate and Gas Rad Monitor skids are powered from 1MR1A, Breaker 43, which is supplied from 480V MCC 1C1-2. These monitors are required to comply with Tech Spec 3.1.C.1.

SRO 70 LOCALLY CHECK CTMT PARTICULATE AND GAS RAD MONITOR -

OPERABLE (SKID/ SAMPLE PUMP ENERGIZED) (IF MCC 1C1-2 CONFIRMED TO BE DEENERGIZED, NO NEED TO CHECK LOCALLY)

SRO Directs BOP to dispatch Aux Building Operator to check local RM skid.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 29 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 71, 1-AP-10.07 SRO 71. ___ CHECK SW SUPPLY MOVS - ALL ENERGIZED RO Reports SW MOVS energized.

Step 72, 1-AP-10.07 SRO 72 CHECK TECH SPEC LCOS:

  • Tech Spec 3.16 SRO The SRO will consult Tech Specs 3.16.B.2 and determine the Unit may be operated for 7 days provided the dependable alternate source can be OPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. SRO will consult with the Shift Manager concerning whether the Dependable alternate source can be Operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SRO may refer to Tech Spec 3.6.I and determine AFW cross-tie clock is not in effect.

SRO will identify 6/30 clock Tech Spec 3.16, while the alignment of running charging pumps is made using 1-AP-10.07, Attachment 4.

SRO will brief the Team on Tech Spec requirements.

Step 73, 1-AP-10.07 CAUTION: If any EDG has operated below 570 KW for three days, additional loading will be required to prevent exhaust system souping. Refer to Attachments 7 and 8.

SRO 73 CHECK 4160V EMERGENCY BUS 1H - ENERGIZED FROM OFFSITE POWER

  • 15F1 - CLOSED
  • 15H8 - CLOSED RO/BOP Reports 15F1 and 15H8 breakers closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 30 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 74, 1-AP-10.07 CAUTION:

  • Shift Supervision should direct the loading of EDG 3 to 1J or 2J Emergency Bus to best support plant recovery.
  • If any EDG has operated below 570 KW for three days, additional loading will be required to prevent exhaust system souping. Refer to Attachments 7 and 8.

NOTE:

  • The RSS transformer cooling fans, heaters, and load tap changer controls are powered from 1J1-1-3B2 or 2J1-1-4A2 depending on position of the throwover switch near 1-SA-TK-2 in Unit 1 Turbine BLDG basement. The switch shall be aligned to an energized bus.
  • Until the throwover switch is aligned to an energized bus, the RSST load tap changers are inoperable. Tech Spec 3.16.B.2 should be reviewed for required actions.

SRO 74 CHECK AC EMERGENCY BUS 1J - ENERGIZED FROM OFFSITE POWER

  • 15D1 - CLOSED
  • 15J8 - CLOSED RO/BOP Reports breaker 15D1 closed, breaker 15J8 Open.

Step 74, RNO Do the following:

a) IF 1J Bus energized from EDG 3, THEN do the following:

1) Monitor EDG 3 parameters IAW Attachment 8.

SRO SRO Directs RO/BOP to contact Service Building Operator to monitor #3 EDG using Attachment 8 of 1-AP-10.07.

2) Continue efforts to restore normal Emergency Bus power.
3) WHEN cause of power loss identified and corrected, THEN initiate 0-AP-10.08, STATION POWER RESTORATION.

Step 75, 1-AP-10.07 SRO 75. ___ CHECK ANY STATION SERVICE BUS - DEENERGIZED:

  • 15A1 and 15A2 - OPEN OR
  • 15B1 and 15B2 - OPEN OR
  • 15C1 and 15C2 - OPEN BOP Reports All Station Service Buses energized.

SRO Step 75, RNO IF ALL 480V Station Service Buses are energized, THEN GO TO Step 97.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 31 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 97, 1-AP-10.07 SRO 97 NOTIFY THE FOLLOWING:

  • OMOC
  • Electrical Foreman SRO Notifies Shift Manager that 1-AP-10.07 complete and request notification to OMOC, STA, and Electrical Foreman be made.

Attachment 4 of 1-AP-10.07 on next page.

END EVENT #4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 32 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Time Position Applicants Action or Behavior Step 1, Attachment 4, 1-AP-10.07 BOP CAUTION: An EDG can NOT initially be loaded to greater than 1300 KW prior to an SI or HI HI CLS, with the exception of loads that will trip when a HI HI CLS occurs, or loads which are running yet assumed to start on a HI HI CLS.

CAUTION: Total EDG load shall not exceed 2750 KW.

NOTE:

  • The purpose of this Attachment is to limit EDG loading so that a subsequent HI HI CLS actuation will not overload the EDG.
  • EDG load must be monitored closely during pump operations.
  • A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading.

BOP

1. IF EDG 1 is the sole source of power to Emergency Bus 1H, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.

Identifies #1 EDG NOT the sole source to 1H Emergency Bus and GOES TO Step 2.

Step 2, Attachment 4, 1-AP-10.07 BOP NOTE: A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading.

Notifies SRO of 6/30 hour TS 3.16 clock in effect until 1-CH-P-1B running on #3 EDG.

BOP

2. IF EDG 3 is the sole source of power to Emergency Bus 1J, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.
a. Check running or start 1-CH-P-1B or 1-CH-P-1C on Emergency Bus 1J IAW Shift Supervision direction.

BOP Starts 1-CH-P-1B with concurrence of SRO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 33 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 2, Attachment 4, 1-AP-10.07 BOP b. IF a CHG pump can NOT be started on Emergency Bus 1J, THEN do the following. Otherwise, enter N/A.

Enters N/A for substeps b.1, b.2, and b.3.

c. Check or place the remaining CHG pump supplied from Emergency Bus 1J in PTL.

Identifies 1-CH-P-1C (Alternate) in PTL.

d. IF Emergency Bus 1H is supplied by offsite power, and 1-CH-P-1A or 1-CH-P-1C is running, THEN stop CHG pump(s) supplied from Emergency Bus 1H and place in Auto.

RO/BOP Confer with SRO and secures 1-CH-P-1A and 1-CH-P-1C.

e. Determine Emergency Bus 1J load limit IAW the following equation, where (x) equals the total of the KW ratings of all RUNNING equipment from the table below.
  • ___________ + 1300 KW = _________________

(x) EDG Load Limit BOP BOP will write 100 in the (x) blank, and write 1400 in the EDG Load Limit blank.

f. IF existing EDG load is greater than the limit calculated in Substep e.

above, THEN reduce EDG load to less than or equal to the calculated load.

BOP will identify ~950kW load on #3 EDG.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 34 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 3. Attachment 4, 1-AP-10.07 BOP 3. Notify Auxiliary Building Operator to increase monitoring of CHG pump lube oil temperature.

BOP contacts the Aux Building Operator to monitor CHG pump lube oil temperature Step 4, Attachment 4, 1-AP-10.07 BOP 4. Increasing monitoring of CHG pump bearing temperatures using the Plant Computer system.

BOP will monitor CHG pump bearing temperatures using the Plant Computer system.

BOP returns the Attachment to the SRO and provides a short brief of Attachment results.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 35 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

Time Position Applicants Action or Behavior Team Identify the failure of the Test Button based on the following:

Alarms:

PCS Alarm for MSR Indications:

~ 9 MW step decrease indicated on MW Videographic Recorder.

0.2 °F increase in RCS Tave Test 1RL 1IL Button on turbine control panel 1RL CLOSED indicating light LIT on turbine control panel 1IL CLOSED indicating light LIT on turbine control panel.

Note: Team may directly enter 1-AP-38.00 (see page 39).

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS NOTE: SRO may directly enter AP-38.00, MAIN STEAM SYSTEM CONTROL MALFUNCTION. See Page 39.

BOP [1] VERIFY REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies Valve Position Indications are NORMAL.

BOP [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP Identifies no controls need to be placed in Manual.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 36 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

Turbine Valve Position, Step 10 BOP Reports #1 LP Turbine Left Intercept and Reheat Stop Valves are closed.

CAUTION: If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.

SRO 10. ___ CHECK STEAM SYSTEM CONTROLS - NORMAL

  • Turbine Controls
  • Turbine Valve Positions
  • Turbine Monitoring Lights BOP Reports Turbine Valve positions are abnormal.

SRO Initiates AP-38.00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 37 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

Time Position Applicants Action or Behavior Step 1, 1-AP-38.00 SRO 1 CHECK STEAM DUMP VALVES - CLOSED BOP Reports Steam Dump Valves closed / normal.

Step 2, 1-AP-38.00 SRO 2 CHECK SG PORVS - CLOSED BOP Reports SG PORVs closed Step 3, 1-AP-38.00 SRO 3 CHECK THE FOLLOWING CONDITIONS:

  • Reactor power - LESS THAN OR EQUAL TO 100%
  • Turbine load - NORMAL BOP Reports reactor power < 100%

RO Reports Turbine Load NOT Normal SRO Stabilize Reactor power and Turbine load less than 100% using Attachment 2.

NOTE: No Actions required in Attachment 2 for this event.

Step 4, 1-AP-38.00 NOTE: The power reductions required by Step 4 are intended for failures causing full or partial closure of a control valve, or if valve closure is required for maintenance.

SRO 4 CHECK MAIN TURBINE AND MSR STEAM CONTROL VALVES:

a) MSR Steam supply MOVs and FCVs - NORMAL BOP Report MSR MOVs and FCVs normal.

b) Turbine Governor Valves and Stop Valves - NORMAL BOP Report Turbine GVs and SVs normal.

c) Reheat Stop and Intercept Valves - NORMAL BOP Report Reheat Stop and Intercept Valves ABNORMAL RNO c) Reduce Reactor power to less or equal to 71% IAW 0-AP-23.00, RAPID LOAD REDUCTION, OR 1-OP-TM-005, UNIT RAMPING OPERATIONS.

SRO INITIATES 0-AP-23.00 to reduce load to less than 71%.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 38 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

RO Reactivity control during AP-23.00 Ramp:

146 gallons of Boric Acid needed to reduce power to 71%. 50 gallons added during Emergency Boration, leaving 96 gallons to be added using normal boration at an average rate of 5.8 gpm. Control Bank D rod height at end of ramp 197 Steps.

Gallons of PG to be added to stabilize at end of ramp 1957.

SRO Completes Brief and continues with AP-23.00.

EVALUATOR NOTE: RO Emergency borates for 25 seconds which corresponds to

~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.

SRO Caution Prior to Step 1:

  • Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.

Notes Prior to Step 1:

  • Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
  • When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
  • Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
  • The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
  • For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.

0-AP-23.00 RO 1. TURN ON ALL PRZR HEATERS

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 39 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:

BOP a) Verify turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.

RO b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5°F.

SRO/BOP c) Verify or place turbine in IMP IN or IMP OUT as determined by Shift Supervision The SRO can choose IMP IN or IMP OUT.

BOP d) Adjust SETTER to desired power level e) Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute) f) Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) g) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.

SRO 3. CHECK EMERGENCY BORATION - REQUIRED The team may decide to emergency borate after the ramp has progressed to the point that Tave and Tref are matched (or close).

SRO Note Prior to Step 4:

  • Step 4 or Step 5 may be performed repeatedly to maintain Tave and Tref matched, Flux in band, and control rod position above the LO-LO insertion limit.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 40 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

0-AP-23.00 RO 4. PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:

a) Verify or raise CHG flow to greater than 75 gpm b) Transfer the in-service BATP to FAST c) Open ( )-CH-MOV-( )350 (~25 seconds) d) Monitor EMRG BORATE FLOW

  • ( )-CH-FI-( )110 e) After required emergency boration, perform the following:
1) Close ( )-CH-MOV-( )350
2) Transfer the in-service BATP to AUTO
3) Restore Charging flow control to normal RO 5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.

SRO Notes Prior to Step 6:

  • If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
  • RCS Tave must be maintained less than or equal to 577°F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
  • I & C should be contacted to provide assistance with adjusting IRPIs.

RO 6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG RO *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.

BOP 8. MONITOR STEAM DUMPS FOR PROPER OPERATION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 41 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

0-AP-23.00 SRO 9. NOTIFY THE FOLLOWING:

  • Energy Supply (MOC)
  • Polishing Building
  • Chemistry
  • OMOC SRO 10. EVALUATE THE FOLLOWING:
  • VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.

[VPAP-2802 and EPIP are not applicable for this event.]

SRO 11. CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR When reactor power has decreased >15%, then chemistry will be notified.

END EVENT #5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 42 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Adjust 1-CH-YIC-1113 to desired total gallons RO 3. Adjust 1-CH-FC-1113A to desired flow rate.

RO 4. Place the MAKE-UP MODE SEL switch in the BORATE position.

RO 6. Check proper valve positions.

5. Place the MAKE-UP MODE CNTRL switch in the START position RO RO 7. Adjust boration rate using 1-CH-FC-1113A, as necessary.

RO 8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.

a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.

b) Enter N/A for the remaining steps in this Attachment.

Attachment 5 is on the next page RO 9. Check controllers for Primary Grade water and Boric Acid are set correctly.

RO 10. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 11. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 12. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 43 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions

1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
5. Place the MAKE-UP MODE CNTRL switch in the START position.
6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
7. Check proper valve positions.
8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position
9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
10. Check or place the control switches in the AUTO position.
11. Check controllers for Primary Grade water and Boric Acid are set correctly.
12. Place the MAKE-UP MODE SEL switch in the AUTO position.
13. Place the MAKE-UP MODE CNTRL switch in the START position.
14. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 44 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

Time Position Applicants Action or Behavior Team Diagnoses the failure with the following indications:

Alarms:

  • RM-Q7 - CTMT PART ALERT/FAILURE
  • RM-Q8 - CTMT GAS ALERT/FAILURE
  • RM-R8 - CTMT GAS RM-RI-160 HIGH Indications:
  • 1-DA-P-4A running continuously Unit 2 will perform RM ARPs, but will be unable to perform Auto Action verification.

1-AP-16.00 SRO Direct initiation of 1-AP-16.00, EXCESSIVE RCS LEAKAGE SRO Notes Prior to Step 1:

  • RCS average temperature has a direct impact on pressurizer level.

RO [1] MAINTAIN PRZR LEVEL:

  • Isolate Letdown
  • Control Charging flow RO closes 1-CH-LCV-1460A and 1-CH-LCV-1460B to isolate letdown. The RO will take manual control of 1-CH-FCV-1122 to stabilize pressurizer level.

SRO The team will hold a short transient brief which may simply be stated as An RCS Leak is in progress, are there any other higher priorities? (words to the effect).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 45 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

1-AP-16.00 RO 2. CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING

  • PRZR Level
  • PRZR Pressure
  • RCS Subcooling Identifies all parameters are stable under the control of the operator. Team should identify RCS leak rate less than 50 gpm.

Note: Due to ramp previously in progress and Tave trend, the RCS leakrate will be more difficult to calculate.

RO 3. PLACE THE FOLLOWING COMPONENTS IN OFF:

  • CTMT vacuum pumps RO will place the Containment Sump and Vacuum Pumps in OFF.

SRO Note Prior to Step 4:

  • Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.

RO *4. CHECK REACTOR TRIP - REQUIRED

  • Leak rate - GREATER THAN 50 GPM OR
  • Adequate makeup not being provided by blender RO will identify that the leak rate is less than 50 gpm. Note: this can be complicated by temperature trend associated with ramp (may take more time).

4., RNO GO to Step 7.

Evaluator Note: If the Team Identifies RCS leakage > 50 gpm and manually trips the reactor, notify the Simulator Operator to Initiate Event #8, SBLOCA).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 46 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

SRO 7 CHECK SECONDARY RADIATION - NORMAL OR STABLE IF THERE IS PRE-EXISTING TUBE LEAK

  • Air Ejector Rad Monitor
  • SG Blowdown Rad Monitors
  • Secondary sample
  • N-16 Rad Monitors Unit 2 Report Unit 1 Air Ejector and Blowdown Rad Monitors - Normal BOP Reports Main Steam, and N-16 Rad Monitor Normal (using PCS)

SRO 8 CHECK RCS LEAK RATE - LESS THAN 10 GPM RO Reports leak rate > 10 GPM SRO Step 8 RNO Do the following:

a) Initiate unit shutdown IAW the appropriate operating procedure.

b) Control charging flow and seal injection to maintain PRZR level.

c) Evaluate EPIP applicability

[TS 3.1.C, RCS Operational Leakage. The following specifications are applicable to RCS operational LEAKAGE whenever Tavg (average RCS temperature) exceeds 200°F (200 degrees Fahrenheit).

1. RCS operational LEAKAGE shall be limited to:
a. No pressure boundary LEAKAGE
3. If RCS pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within the limit specified in 3.1.C.1.d, the unit shall be brought to HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.]

SRO 9 CHECK UNIT CONDITIONS

  • PRZR level - STABLE OR INCREASING
  • PRZR pressure - STABLE OR INCREASING
  • Tave - STABLE RO Reports PRZR Level, Pressure and RCS Tave Stable.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 47 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

SRO 10 CHECK LETDOWN LEAK - INDICATED BOP

  • Aux Bldg radiation - HIGH
  • CTMT radiation - HIGH RO/BOP
  • Local Report of leak RO
  • Leak rate decrease following isolation in Step 1 RO
  • Abnormal Letdown flow indication prior to isolation in Step 1 RO
  • Non-Regenerative HX tube leak - INDICATED BOP
  • CC Surge Tank level - INCREASING Unit 2
  • CC Activity - INCREASING All indication checked for leak identification are NO SRO Goes to Step 12 12 CHECK RCS LEAKRATE WITH LETDOWN SECURED - REDUCED 12 RNO Do the following:

a) Return letdown to service IAW the following, if desired:

  • Normal letdown, IAW Attachment 2 OR
  • Excess letdown, IAW 1-OP-CH-006, SHIFTING LETDOWN b) GO TO Step 15.

[TS 3.1.C, RCS Operational Leakage. The following specifications are applicable to RCS operational LEAKAGE whenever Tavg (average RCS temperature) exceeds 200°F (200 degrees Fahrenheit).

1. RCS operational LEAKAGE shall be limited to:
a. No pressure boundary LEAKAGE
3. If RCS pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within the limit specified in 3.1.C.1.d, the unit shall be brought to HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 48 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

END OF EVENT #6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 7 Page 49 of 103 Event

Description:

Containment particulate and gas RM fail, no Auto Actions.

Cue: Initiated by Event 6.

Time Position Applicants Action or Behavior 1-RM-R8 Actions BOP NOTE: BOP will be handed Steps 3 and 4 of ARP to verify auto actions of CTMT GAS High alarm.

BOP 3 VERIFY CTMT PURGE SYS - ISOLATED a) CTMT PURGE SUP - CLOSED

  • 1-VS-MOV-100A
  • 1-VS-MOV-100B
  • 1-VS-MOV-100C
  • 1-VS-MOV-100D BOP will verify Purge valves closed on the Unit 1 Ventilation Panel by observing RED and GREEN lights extinguished, and GREEN magnet over Shut position indicating light signifying Valve Closed.

b) CTMT PURGE SUP fans - STOPPED

  • 1-VS-F-4A
  • 1-VS-F-4B BOP will identify Purge Supply Fans secured by observing RED and GREEN indicating lights extinguished.

c) CTMT PURGE BYP valve - CLOSED

  • 1-VS-MOV-101 BOP 4 VERIFY CTMT IA SYSTEM ALIGNMENT:
  • 1-IA-TV-101A - CLOSED
  • 1-IA-TV-101B - CLOSED Identifies 1-IA-TV-101A / B Open by observing position indicating lights on Unit 1 Vertical board RED Light LIT.

Step 4 RNO Manually Align Valves BOP will close the valves by depressing and holding the GREEN indicating light until only the GREEN indicating light is lit.

NOTE: When either 1-IA-TV-101A / B are closed, 1-IA-AOV-103 will open (checked in Step 5 below).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 7 Page 50 of 103 Event

Description:

Containment particulate and gas RM fail, no Auto Actions.

Cue: Initiated by Event 6.

BOP 5 CHECK CTMT IA COMPR OUTSIDE SUCT - OPEN

  • 1-IA-AOV-103 BOP will observe 1-IA-AOV-103 OPEN by observing RED position indicating light LIT.

End EVENT #7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 51 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior Team Diagnose escalation of RCS Leak by the following:

Alarms:

1C-B8, PRZR LO PRESS 1B-A3, CTMT SUMP HI LVL Indications:

Lowering RCS Pressure PRZR Level decreasing SRO Direct RO to re-perform Immediate Actions of AP-16.00.

RO [1] MAINTAIN PRZR LEVEL:

  • Isolate Letdown
  • Control Charging flow RO checks 1-CH-LCV-1460A and 1-CH-LCV-1460B closed.

The RO will increase flow using 1-CH-FCV-1122 to control PRZR level.

SRO The team will hold a short transient brief which may simply be stated as An RCS Leak is in progress, are there any other higher priorities? (words to the effect).

1-AP-16.00 SRO 2. VERIFY THE FOLLOWING PARAMETERS - STABLE OR INCREASING

  • PRZR Level
  • PRZR Pressure
  • RCS Subcooling Identifies all parameters are stable under the control of the operator. Team should identify RCS leak rate greater than 50 gpm.

NOTE: SRO may direct RO to manually trip the reactor and safety inject at this point due to degrading plant parameters.

RO 3. PLACE THE FOLLOWING COMPONENTS IN OFF:

  • CTMT vacuum pumps RO will check the Containment Sump and Vacuum Pumps in OFF.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 52 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

SRO Note Prior to Step 4:

  • Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.

SRO *4. CHECK REACTOR TRIP - REQUIRED

  • Leak rate - GREATER THAN 50 GPM OR
  • Adequate makeup not being provided by blender RO will identify that the leak rate is greater than 50 gpm.

SRO 5 ALIGN CHG PUMP SUCTION TO RWST a) Open 1-CH-MOV-1115B and 1-CH-MOV-1115D b) Close 1-CH-MOV-1115C and 1-CH-MOV-1115E RO Evaluator Note: Team may or may not manually align these valves depending on timing.

SRO 6 GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION SRO Directs RO to trip the reactor, perform E-0, and Manually Safety Inject on Step 4.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 53 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior 1-E Reactor Trip or Safety Injection RO [1] CHECK REACTOR TRIP:

a) Manually trip reactor Pushes the reactor trip push buttons.

b) Check the following:

  • All Rods On Bottom light - LIT
  • Neutron flux - DECREASING RO [2] CHECK TURBINE TRIP:

RO a) Manually trip the turbine Pushes the turbine trip push buttons.

b) Verify all turbine stop valves - CLOSED c) Isolate reheaters by closing MSR steam supply SOV

  • 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)

RO [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 54 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

[4] CHECK IF SI INITIATED:

RO a) Check if SI is actuated:

  • LHSI pumps - RUNNING
  • A-F-3 SI INITIATED - TRAIN A
  • A-F-4 SI INITIATED - TRAIN B RO 4b) Manually initiate SI The RO will manually initiate SI at step 4 by pushing both SI pushbuttons.

After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal, with the exception of the alarms already received. He will also state that containment conditions and the electrical conditions are as you see them (or as reported by the RO/BOP).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 55 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

SRO The team will hold a transition brief. During the brief it will be identified that SI was initiated and the RCS leak has degraded into a LOCA.

SRO/BOP 5. Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained the end of Event 8).

SRO/RO SRO may direct the RO to perform Attachment 8 of 1-E-0 for Transient AFW Control, or opt to throttle AFW as part of E-0, Step 6.

RO *6. CHECK RCS AVERAGE TEMPERATURE

  • STABLE AT 547°F OR
  • TRENDING TO 547°F The team will identify that RCS temperature is decreasing. The team should attribute this to the injection of SI into the RCS and AFW flow to the SGs. It is acceptable for the team to enter the RNO portion of this step and perform the applicable steps (summarized below):

Stop dumping steam Reduce AFW flow to the SGs Close MSTVs if cooldown continues

7. CHECK PRZR PORVs AND SPRAY VALVES:

RO a) PRZR PORVs - CLOSED b) PRZR spray controls

  • Demand at Zero (or)
  • Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 56 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

SRO NOTE: Seal injection flow should be maintained to all RCPs.

RO *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.

b) RCS subcooling - LESS THAN 30°F [85°F]

RCS subcooling may or may not be less than 30 °F at this time.

RNO for the step is to go to step 9.

Critical Task:

CT-1: WOG E-1C: Trip all RCPs so that CETC temperatures do not become superheated when forced circulation in RCS stops; Trip all RCPS within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).

NOTE: If RCP trip Criteria are met prior to reaching this Step, the Continuous Actions Page (CAP) contains these criteria. After this Step is read, this step or the CAP can be used for criteria as long as the Team is performing E-0.

RO 9. CHECK IF SGs ARE NOT FAULTED:

  • Check pressures in all SGs a) STABLE OR INCREASING AND b) GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 57 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

SRO 10. CHECK IF SG TUBES ARE NOT RUPTURED:

Unit 2

  • Condenser air ejector radiation - NORMAL Unit 2
  • SG blowdown radiation - NORMAL
  • SG MS radiation - NORMAL
  • TD AFW pump exhaust radiation - NORMAL
  • SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO RO will use PCS indication for MS and TDAFW Exhaust radiation.

Unit 2 will be used to report Condenser A/E and SG Blowdown radiation trend.

SRO 11 CHECK RCS - INTACT INSIDE CTMT

  • CTMT radiation - NORMAL
  • CTMT pressure - NORMAL
  • CTMT RS sump level - NORMAL RO Identify CTMT conditions as abnormal SRO GO TO 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

SRO The team will hold a transition brief. During the brief the SRO will set priorities. The RO and BOP will state the parameters associated with the brief placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified alarms. He will also state that containment conditions and the electrical conditions are as you see them.

The SRO will complete the Brief and continue with E-1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 58 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior Step 1, 1-E-1 SRO NOTE: Criteria for FR-Z.1 Entry may be met at any time during performance of 1-E-1. (FR-Z.1 Actions in Section 9).

1 CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO identify 2 CH pumps running.

b) RCS subcooling - LESS THAN 30°F [85°F]

RO reports actual subcooling.

c) Stop all RCPs RO Stops RCPs if not already tripped.

d) RCS pressure - LESS THAN 1275 PSIG [1475 PSIG]

e) Close CHG pump miniflow recirc valves:

  • 1-CH-MOV-1275A
  • 1-CH-MOV-1275B
  • 1-CH-MOV-1275C RO closes or verifies closed mini-flow recirc valves.

Critical Task:

CT-1: WOG E-1C: Trip all RCPs so that CET temperatures do not become superheated when forced circulation in RCS stops; Trip all RCPs within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).

NOTE: Critical Task copied from E-0 if timing of scenario leads to RCP trip criteria identified on entry to 1-E-1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 59 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

1-E-1 SRO 2 CHECK IF SGs ARE NOT FAULTED:

  • Check pressures in all SGs:
  • STABLE OR INCREASING AND
  • GREATER THAN 100 PSIG RO reports SGs are not faulted.

NOTE: SG pressures may be decreasing due to cooldown. RO may report SG pressure as lowering. The SRO will obtain Team concurrence that SG pressure decrease is related to RCS cooldown not a SG fault. The brief is closed.

1-E-1 SRO *3 CHECK INTACT SG LEVELS:

a) Narrow range level - GREATER THAN 12% [18%]

b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%

1-E-1 SRO 4 CHECK IF SG TUBES ARE NOT RUPTURED:

  • Condenser air ejector radiation - NORMAL
  • SG blowdown radiation - NORMAL
  • TD AFW pump exhaust radiation - NORMAL
  • SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER Unit 2 may be used to report Unit 1 condenser air ejector and blowdown radiation monitor readings.

RO Report MS and TDAFW RM readings using PCS. Identify SG NR levels NOT increasing in an uncontrolled manner.

1-E-1 CAUTION: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure decreases to less than 2335 psig.

SRO *5 CHECK PRZR PORVs AND BLOCK VALVES:

a) Power to PRZR PORV block valves - AVAILABLE RO Report PRZR block valves both available.

b) PRZR PORVs - CLOSED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 60 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

RO Report PRZR PORVs closed.

c) PRZR PORV block valves - AT LEAST ONE OPEN RO Report PRZR block valves both open.

1-E-1 SRO *6. ___ CHECK IF SI FLOW SHOULD BE REDUCED:

a) RCS subcooling based on CETCs - GREATER THAN 30°F [85°F]

RO Reports indicated subcooling.

b) Secondary heat sink:

RO

  • Total feed flow to INTACT SGs - GREATER THAN 350 GPM [450 GPM]

OR

  • Narrow range level in at least one intact SG - GREATER THAN 12% [18%]

RO Reports SGs have adequate level and AFW flow.

RO c) RCS pressure - STABLE OR INCREASING RO Reports RCS pressure decreasing.

SRO RNO a) OR c) GO TO Step 7.

1-E-1 SRO *7 CHECK IF HI HI CLS INITIATED:

  • CS pump(s) - RUNNING OR
  • Any Hi Hi CLS annunciator - LIT NOTE: At this Point CTMT pressure may have increased to the HI and/or Hi-Hi CLS setpoint. The Team should identify that Hi and Hi-Hi CLS do not automatically initiate and take manual action to perform the automatic actions. (FR-Z.1 Actions in Section 9)

When the Team identify that Hi-Hi CLS has not actuated, a transition to FR-Z.1 will be made. When the transition is made Critical Task 2 begins:

CRITICAL TASK:

(Actions for FR-Z.1 will follow 1-E-1, Step 18). Page 77

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 61 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

1-E-1 SRO 8 CHECK SERVICE WATER AVAILABLE:

a) Check Intake Canal level - BEING MAINTAINED BY CW PUMPS RO Reports Intake Canal level is 29 feet and Stable.

b) GO TO Step 12 1-E-1 SRO *12 CHECK IF CS PUMPS CAN BE STOPPED:

a) Check the following:

  • RWST level - LESS THAN 3%

AND

  • CS Pump amps - FLUCTUATING RO Reports actual RWST Level.

RNO a) GO TO Step 14. WHEN the following conditions are met, THEN do Steps 12b through 12f.

  • RWST level - LESS THAN 3%

AND

  • CS Pump amps - FLUCTUATING 1-E-1 SRO CAUTION: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.
  • 14 CHECK IF LHSI PUMPS SHOULD BE STOPPED:

a) Check RCS pressure:

1) Pressure - GREATER THAN 250 PSIG [400 PSIG]

RO Reports RCS pressure > 250 PSIG [400 PSIG]

2) Pressure - STABLE OR INCREASING Reports RCS pressure Lowering.

RNO 2) GO TO Step 15.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 62 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

1-E-1 15 CHECK RCS AND SG PRESSURES:

  • Check pressure in all SGs - STABLE OR INCREASING
  • Check RCS pressure - STABLE OR DECREASING NOTE: SG pressures may be decreasing due to coodown. RO may report SG pressure as lowering. The SRO will obtain Team concurrence that SG pressure decrease is related to RCS cooldown not a SG fault. The brief is closed 1-E-1 SRO 16 CHECK IF EDGs CAN BE STOPPED:

a) Check AC emergency buses - ENERGIZED BY OFFSITE POWER RO Reports that H Emergency bus energized by off-site power, and J emergency powered from #3 EDG.

b) Reset both trains of SI if necessary RO RO presses SI reset pushbuttons.

c) Check CTMT pressure - LESS THAN 14 PSIA RO Reports actual containment pressure (pressure will be greater than 14 psia).

RNO c) GO TO Step 17. WHEN pressure less than 14 psia, THEN do Steps 16d and 16e.

1-E-1 SRO 17 CHECK INSTRUMENT AIR AVAILABLE:

a) Check annunciator B-E NOT LIT RO Reports B-E-6 NOT LIT.

b) Check at least one CTMT IA compressor - RUNNING

  • 1-IA-C-4A or 1-IA-C-4B RO Reports 1-IA-C-4A running.

c) Check 1-IA-TV-100 - OPEN RO Reports 1-IA-TV-100 position.

NOTE: When BOP performs Attachment 4 of E-0, 1-IA-TV-100 may be closed; SRO/BOP may confer over closure of the valve since Hi-Hi CLS actions are being

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 63 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

manually performed.

1-E-1 SRO 18 INITIATE EVALUATION OF PLANT STATUS:

END OF EVENT 8 END OF SCENARIO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 64 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior Attachment 1 of E-0 1 CHECK FW ISOLATION:

  • Feed pump discharge MOVs - CLOSED
  • 1-FW-MOV-150A
  • 1-FW-MOV-150B
  • MFW pumps - TRIPPED
  • Feed REG valves - CLOSED
  • SG FW bypass flow valves - DEMAND AT ZERO
  • SG blowdown TVs - CLOSED Attachment 1 of E-0 2 CHECK CTMT ISOLATION PHASE I:
  • Phase I TVs - CLOSED
  • 1-CH-MOV-1381 - CLOSED
  • 1-SV-TV-102A - CLOSED
  • PAM isolation valves - CLOSED
  • 1-DA-TV-103A
  • 1-DA-TV-103B Attachment 1 of E-0 3 CHECK AFW PUMPS RUNNING:

a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY Attachment 1 of E-0 BOP 4. CHECK SI PUMPS RUNNING:

  • CHG pumps - RUNNING
  • LHSI pumps - RUNNING

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 65 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Attachment 1 of E-0 BOP

5. CHECK CHG PUMP AUXILIARIES:
  • CHG pump CC pump - RUNNING
  • CHG pump SW pump - RUNNING Attachment 1 of E-0 BOP 6. CHECK INTAKE CANAL:
  • Level - GREATER THAN 24 FT
  • Level - BEING MAINTAINED BY CIRC WATER PUMPS Attachment 1 of E-0
7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:

a) Check if ANY of the following annunciators - HAVE BEEN LIT

  • E-F-10 (High Steam Flow SI)

BOP

  • B-C-4 (Hi Hi CLS Train A)
  • B-C-5 (Hi Hi CLS Train B)

Identifies annunciators not lit and goes to step 8.

Attachment 1 of E-0 BOP

  • 8. CHECK IF CS REQUIRED:

a) CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 66 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Attachment 1 of E-0 BOP *10. BLOCK LOW PRZR PRESS SI SIGNAL:

a) Check PRZR pressure - LESS THAN 2000 psig b) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c) Check Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.

Attachment 1 of E-0 BOP *11. BLOCK LOW TAVE SI SIGNAL:

Step may not be performed at this time (if Tave is greater than 543°F).

a) Check RCS Tave - LESS THAN 543°F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c) Check Permissive Status light F LIT Attachment 1 of E-0 NOTE:

  • CHG pumps should be run in the following order of priority: C, B, A.
  • Subsequent SI signals may be reset by re-performing Step 12.

BOP

12. CHECK SI FLOW:

a) HHSI to cold legs - FLOW INDICATED

  • 1-SI-FI-1961 (NQ)
  • 1-SI-FI-1962 (NQ)
  • 1-SI-FI-1963 (NQ)
  • 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c) Reset SI.

d) Stop one CHG pump and out in AUTO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 67 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Step 12, Attachment 1 of E-0, Continued e) RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:

1) Verify reset or reset SI.
2) Stop one LHSI pump and put in AUTO.
3) GO TO Step 13.

Attachment 1 of E-0 BOP

13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]

Attachment 1 of E-0 BOP

14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.

Attachment 1 of E-0 BOP

15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next Page of this guide)

Depending on timing, this attachment may have already been completed.

Attachment 1 of E-0 BOP

16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Unit 2 Operator will state that Unit 2 is at 100% power (if asked)

Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 68 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 SRO NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.

ATTACHMENT 2 of 1-E-0 RO/BOP 1. Check opened or open CHG pump suction from RWST MOVs.

  • 1-CH-MOV-1115B
  • 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 RO/BOP 2. Check closed or close CHG pump suction from VCT MOVs.
  • 1-CH-MOV-1115C
  • 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 RO/BOP 3. Check running or start at least two CHG pumps. (listed in preferred order)
  • 1-CH-P-1C
  • 1-CH-P-1B
  • 1-CH-P-1A ATTACHMENT 2 of 1-E-0 RO/BOP 4. Check opened or open HHSI to cold legs MOVs.
  • 1-SI-MOV-1867C
  • 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 RO/BOP 5. Check closed or close CHG line isolation MOVs.
  • 1-CH-MOV-1289A
  • 1-CH-MOV-1289B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 69 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

ATTACHMENT 2 of 1-E-0 RO/BOP 6. Check closed or close Letdown orifice isolation valves.

  • 1-CH-HCV-1200A
  • 1-CH-HCV-1200B
  • 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 RO/BOP 7. Check opened or open LHSI suction from RWST MOVs.
  • 1-SI-MOV-1862A
  • 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 RO/BOP 8. Check opened or open LHSI to cold legs MOVs.
  • 1-SI-MOV-1864A
  • 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 RO/BOP 9. Check running or start at least one LHSI pump.
  • 1-SI-P-1A
  • 1-SI-P-1B ATTACHMENT 2 of 1-E-0 RO/BOP 10. Check High Head SI flow to cold legs indicated.
  • 1-SI-FI-1961
  • 1-SI-FI-1962
  • 1-SI-FI-1963
  • 1-SI-FI-1943 or 1-SI-FI-1943A

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 70 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

ATTACHMENT 2 of 1-E-0 RO/BOP 11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.

  • Alternate SI to Cold legs
  • Hot leg injection

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 71 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 72 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 73 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 74 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Unit 2 will prompt BOP: Chilled Water has been aligned IAW CAUTION prior to Step 1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 75 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Unit 2 will prompt BOP: MCR Boundary DP is the same as DP indicated on Unit 2 Ventilation Panel.

Unit 2 will prompt BOP: Unit 2 remains operating at 100%

power.

Unit 2 will assume responsibility for the Attachment action from this point.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 76 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 77 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

Time Position Applicants Action or Behavior 1-FR-Z.1 Actions CAUTION: If 1-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, is in effect, containment spray systems should be operated as directed by 1-ECA-1.1, instead of Step 1 below.

SRO 1 CHECK IF CS REQUIRED:

a) Check CTMT pressure - HAS INCREASED TO GREATER THAN 23 PSIA b) Check CS pumps - RUNNING b) IF RWST level greater than 3%,

THEN start CS pumps. IF any CS pump can NOT be started, THEN monitor OSRS pumps for cavitation.

RO Starts 1-CS-P-1A / 1B IF cavitation is indicated, THEN put affected OSRS pump in PTL c) Check CS system valves - OPEN c) Manually align CS valves.

  • 1-CS-MOV-100A
  • 1-CS-MOV-100B
  • 1-CS-MOV-101A and B
  • 1-CS-MOV-101C and D
  • 1-CS-MOV-102A and B RO Opens Valves Listed Above (BOLDED).

d) Stop all RCPs RO Stops RCPS and acknowledges Loop Low Flow Alarms.

Critical Task:

CT-2: WOG E-0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (red-path) challenge develops to the CSF. Establish CS flow from at least one CS pump before containment pressure exceeds 60 psia AND at least one RS train before RMT.

Evaluator Note: To meet the CT, One Train of CTMT Depressurization must be aligned. One CS pump with either of its associated discharge MOVs open.

1-CS-P-1A Running, with 1-CS-MOV-101A or 1-CS-MOV-101B OPEN. OR 1-CS-P-1B Running, with 1-CS-MOV-101C or 1-CS-MOV-101D OPEN.

CRITICAL TASK:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 78 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

1-FR-Z.1 Actions SRO 2 CHECK SW FLOW TO RS HXs - Align valves as necessary.

GREATER THAN 4750 GPM RO Checks flow > 4750 GPM following the Opening of the SW Valves Listed below.

a) Check the following valves - OPEN

  • 1-SW-MOV-103A, B, C, and D
  • 1-SW-MOV-104A, B, C, and D
  • 1-SW-MOV-105A, B, C, and D RO Open the SW MOVs listed above.

1-FR-Z.1 Actions SRO 3 CHECK RS SYSTEMS:

a) Check RWST level -LESS THAN 60% a) Do the following:

1) Monitor RWST level.
2) WHEN RWST level is less than 60%, THEN perform Steps 3b and 3c.

1-FR-Z.1 Actions SRO 4 CHECK INTAKE CANAL LEVEL - GREATER THAN 24 FT RO Reports Intake Canal Level 29 feet and Stable.

1-FR-Z.1 Actions SRO 5 CHECK CTMT ISOLATION VALVES -

CLOSED IAW ATTACHMENT 1 IF flow path NOT necessary, THEN close valves BOP Aligns Valves as necessary.

NOTE: BOP and SRO may confer on leaving 1-IA-TV-100 open.

NOTE: FR-Z.1 Actions located at the end of this section.

1-FR-Z.1 Actions SRO 6. ___ CHECK MSTVs - CLOSED Manually close MSTVs.

RO/BOP Closes MSTVs if not already performed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 79 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

1-FR-Z.1 Actions CAUTION:

  • At least one SG must be maintained available for RCS cooldown.
  • If all SGs are faulted, at least 60 gpm [100 gpm] feed flow should be maintained to each SG.

SRO 7. ___ CHECK IF FEED FLOW SHOULD BE ISOLATED TO ANY SG(s):

a) Check pressures in all SGs: a) GO TO Step 8

  • ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR
  • ANY SG COMPLETELY DEPRESSURIZED RO/BOP Reports SGs NOT Faulted.

1-FR-Z.1 Actions SRO 8 CHECK SERVICE WATER AVAILABLE:

a) Check Intake Canal level - BEING MAINTAINED BY CIRC WATER PUMPS RO/BOP Reports Intake Canal Level 29 feet and Stable. Being maintained by CW pumps.

b) RETURN TO procedure and step in effect SRO Returns to 1-E-1, Step In Effect.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 80 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

Valves Operated for Hi CLS Failure.

Valves Operated for Hi Hi CLS Failure.

Valve BOP/SRO may confer and leave open.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 81 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

Valves Operated for Hi CLS Failure.

Valves Operated for Hi Hi CLS Failure.

Valve BOP/SRO may confer and leave open.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 82 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

Section Not Performed for this Scenario.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 83 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 84 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 85 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 86 of 103 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:

Recall IC -263 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.

Open the monitor window and add the following points to it:

  • asp_ao_off
  • set sphhcntprs_k1 = 60
  • iadryer_reset
  • ??

Enter the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Type (Auto or Manual)

RC0801 TAVE TAYLOR MATH 10 0 1 0 -1 MAN UNIT FAILURE HI/LOW MS0801 SG A STM FLOW 10 30 3 0 -1 MAN TRNSMTR MS-FT-475 FAILURE EL4902 BKR 15J8 SPURIOUS TRIP 10 0 5 FALSE TRUE MAN RC04 RCS LEAK NONISOLABLE 10 0 9 0 3.5 MAN (0 - 1200 GPM)

RM0202 PROCESS RAD 10 0 9 0 0.1 MAN MONITOR RI-RMS-159 FAILURE RM0201 PROCESS RAD 10 0 9 0 0.1 MAN MONITOR RI-RMS-160 FAILURE CA03 Disable IA-TV-101A Auto 0 0 9 FALSE TRUE MAN Closure CA06 Disable IA-TV-101B Auto 0 0 9 FALSE TRUE MAN Closure RC0101 RCS COLD LEG A PIPE 10 600 11 0 .6 MAN RUPTURE RS0901 TRN A HI CLS FAILS TO 0 0 30 FALSE TRUE ACTIVE ACTIVATE RS0902 TRN B HI CLS FAILS TO 0 0 30 FALSE TRUE ACTIVE ACTIVATE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 87 of 103 SIMULATOR OPERATORS GUIDE Enter the following Remote Functions:

Override Set Condition Trigger AC_SMS_MODE OFF 30 Enter the following Override:

Override Set Condition Trigger TEST_IRL_IIL EHC ON, 10 Sec TD 7 TEST 1RL 1IL CLS_ACT_TRA OFF 30 CLS_ACT_TRB OFF 30 TRIGGER TYPE DESCRIPTION 1 MAN TAVE TAYLOR MATH UNIT FAILURE LOW 3 MAN SG A STM FLOW TRNSMTR MS-FT-475 FAILURE 5 MAN BKR 15J8 SPURIOUS TRIP 7 MAN IRL/ILL TEST PUSHBUTTON FAILURE RCS LEAK NONISOLABLE (35 GPM) with AUTO ACTIONS RM-MAN 9 159/160 FAILURE 11 MAN LBLOCA WITH HI and HI HI CLS FAILED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 88 of 103 SIMULATOR OPERATORS GUIDE Verify the following control room setup:

Place the simulator in RUN and verify normal 100% power operation indications.

Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:

Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).

Verify Ovation System operating.

Reset ICCMs.

Verify Component Switch Flags.

Verify Brass Caps properly placed.

Verify SG PORVs set for 1035 psig.

Verify Rod Control Group Step Counters indicate properly.

Verify Ovation CRT display.

Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)

Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:

AP-53.00 AP-16.00 AP-23.00 1-OPT-RX-007 (3)

E-0 E-1 (2)

OP-CH-007 MOL OP-RX-010 OP-ZZ-002 Verify Reactivity Placard is current.

Verify ALL PINK MAGNETS are accounted for.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 89 of 103 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

Ask for and answer questions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 90 of 103 SIMULATOR OPERATORS GUIDE Conduct shift turnover:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1.

The last shift performed two 35 gallon alt dilutions followed by a manual makeup for training.

A BAST at 8.0 W/%.

When the team has accepted the shift, proceed to the Session Conduct Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 91 of 103 SIMULATOR OPERATORS GUIDE Session Conduct:

  • Ensure conditions in Simulator Set-up are established.
  • Ensure Trigger 30 is active prior to team entering the simulator.
  • Verify Exam Security has been established and ASP_AO_OFF = True.

EVENT 1 Deleted.

EVENT 2 Failure Median Tave Low, 0-AP-53.00.

When cued by examiner, implement Trigger #1.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of Median Tave. The individual(s) contacted will also acknowledge entry into AP-53.00.
  • If contacted, will take responsibility for writing the CR.
  • If asked, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.

STA:

  • If contacted, will acknowledge the failure of Median Tave.
  • If asked, the STA will report that upon review of CEP 99-0029, Median Tave is NOT listed in CEP 99-0029.
  • If asked, the STA will review VPAP-2802 and TRM Section 3.3 and report that the results of the review have been discussed with Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 92 of 103 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge instrumentation failure and commence investigation of the failure.

Unit 2 Operator:

  • If contacted, will acknowledge the failure.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 93 of 103 SIMULATOR OPERATORS GUIDE EVENT 3 Failure of Steam Flow Channel Low, A SG. 0-AP-53.00.

When cued by examiner, implement Trigger #3.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of 1-MS-FT-1474. The individual(s) contacted will also acknowledge any TS LCOs.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to place the channel in trip.
  • If contacted, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.

STA:

  • If contacted, will acknowledge the failure of 1-MS-FT-1474. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
  • If contacted, will take responsibility for writing the CR.
  • If asked, 1-MS-FT-1474 is a RG 1.97 variable
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
  • When directed, STA review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

Field Operators:

  • Will perform actions as directed.

I&C:

  • If notified by MCR to place the channel in trip, state that you will review the procedure and notify the Shift Manager when ready to brief.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 94 of 103 SIMULATOR OPERATORS GUIDE Maintenance/ Work Week Coordinator:

  • If contacted, will notify I&C of the failure.

Unit 2:

  • If contacted, will acknowledge the channel failure.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 95 of 103 SIMULATOR OPERATORS GUIDE EVENT 4 1J 4160V emergency bus off-site power supply breaker trips. 1-AP-10.07.

When the Evaluator is ready, Implement Trigger #5 for the failure. Evaluator may go to next event (event #5) when 1-CC-P-1B is placed in Auto.

Operations Supervisor/Management:

  • If contacted, will acknowledge the loss of 1J 4160 V bus, and the start and load of #3 EDG.
  • If contacted, will inform OM on Call and Electrical Foreman.

STA:

  • If contacted, will acknowledge the loss of 1J 4160V bus and the start and load of #3 EDG.
  • After directed, the STA will report that VPAP-2802 has been reviewed and discussed with the Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Maintenance/ Work Week Coordinator:

  • If contacted, will acknowledge the failure and commence investigations.

Field Operators:

  • If contacted, will check status of 15J8 breaker and find an individual in the area that reports he bumped the cabinet while cleaning and heard a loud noise. 1-CC-P-1B must have been returned to Auto before this report is made.
  • If asked, the condensate polishing building operator will report current polishing building DP (read from simulator screen).
  • When Directed, to check status of IA compressors (1B-E6 ARP), CA6 1-IA-C-1 IA Local Panel, the local panel will have an Alarm light lit. Depress U1_IAC1_SET button to clear alarm.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 96 of 103 SIMULATOR OPERATORS GUIDE

  • When Directed, to check status of IA Dryer (1B-E5 ARP), the dryer will be bypassed, use IADRYER_RESET on monitor to reset the dryer.
  • When contacted, to close 15J9 breaker, EL11, Unit 1 - 4160 Breakers, 15J9, scroll to bottom of pop-up box, double click on SW_15J9_RF, select close, INSERT.
  • When contacted, RM-159/160 Particulate and Gas RM skid is normal.
  • When contacted, concerning monitoring of #3 EDG parameters, follow instructions.

Unit 2:

  • If contacted, acknowledge start and load of #3 EDG on Unit 1.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 97 of 103 SIMULATOR OPERATORS GUIDE EVENT 5 Test Button failure, 1RL/1IL close, 0-AP-23.00 ramp to 71%.

When 1-CC-P-1B in Auto and examiner ready, implement Trigger #7.

Operations Supervisor/Management:

  • If contacted, will acknowledge closure of 1RL/1IL. Also acknowledge the entry into AP-53.00/AP-38.00 for the failure.
  • If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC (Lead Evaluator), the Shift Manager will direct a 1%/minute ramp rate.
  • If contacted, will take responsibility for writing the CR.

Unit 2 Operator:

  • If notified, acknowledge the failure and impending ramp of Unit 1.

STA:

  • If contacted, will acknowledge the closure of 1RL/1IL, and entry into AP-53.00/AP-38.00.
  • If contacted, will take responsibility for writing the WR and CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
  • The STA will acknowledge the Reactivity Plan reported by the RO.
  • If contacted, STA review of VPAP-2802 complete and reviewed with Shift Manager.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 98 of 103 SIMULATOR OPERATORS GUIDE Field Operators:

  • If contacted, as the Turbine Building Operator to walkdown the Turbine during the ramp, acknowledge the direction.
  • If contacted, as the polishing building operator, acknowledge the direction to monitor polisher DP.
  • If contacted, as Turbine Building operator, the 1RL/1IL valves are closed, no external abnormalities noted.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 99 of 103 SIMULATOR OPERATORS GUIDE EVENTS 6 RCS Leak 35 gpm. 1-AP-16.00.

Note: It would be preferable to wait until power is <80% to implement this failure to allow for ramp stabilization prior to creating RCS leak; this will allow the team to assess leakrate with more precision.

When the Evaluator is ready, implement Trigger # 9. If the Team manually trips the reactor, the Evaluator may prompt initiation of Event #8.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will acknowledge entry into AP-16.00.
  • If contacted, will acknowledge Unit shutdown imminent due to excessive RCS leakage.
  • If contacted, will acknowledge EPIPs require evaluation.

STA:

  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
  • When Notified, acknowledge that EPIPs require evaluation.
  • If contacted, will enter the control room and and prepare for the transient brief (items are reported as you see them or previously reported).

Unit Two:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 100 of 103 SIMULATOR OPERATORS GUIDE

  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO/BOP.
  • If asked, blowdown and air ejector RM readings are [as indicated at the time].
  • When required, assist Unit by acknowledging Fire Panel Alarms.
  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.

Field Operators:

  • If contacted, field operators will perform valve manipulations as required:

Health Physics:

  • If contacted, will acknowledge the leak of RCS coolant into containment.

Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge the failure.

Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge the failure.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 101 of 103 SIMULATOR OPERATORS GUIDE EVENT 7 Particulate and gas RM fail, No Auto Actions.

Implemented with Trigger #9.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of the automatic actions on RM-160 High alarm.
  • If contacted, will take responsibility for writing the WR and CR.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
  • If directed, perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.

Field Operators:

  • If directed, field operators will perform local manipulations as required.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 102 of 103 SIMULATOR OPERATORS GUIDE EVENT 8 SBLOCA, 1-AP-16.00, 1-E-0.

When the Evaluator is ready, actuate Trigger #11. Prompt the Evaluator when RCS Subcooling reaches 35 °F and decreasing so that start time for CT-1 is monitored.

Operations Supervisor/Management:

  • If contacted, will acknowledge the reactor trip and Entry into E-0.
  • If contacted, will take responsibility for writing the WR and CR.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.

STA

  • Enter MCR when called and standby to monitor CSFSTs.
  • When entry conditions for Containment Orange Path identified, circle the appropriate Path and show to the SRO.

Field Operators:

  • If directed, field operators will perform local manipulations as required.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 103 of 103 SIMULATOR OPERATORS GUIDE EVENT 9 Hi and HI-CLS Failure, FR-Z.1.

Implemented by ACTIVE Triggers.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of Hi and Hi-Hi CLS.

STA:

  • When the Team identifies containment pressure has exceeded 23 psia, use CSFSTs to mark flowpath to FR-Z.1, ORANGE path and present to SRO.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
  • When BOP performs Attachment 3 of E-0, MCR Boundary DP readings are the same as the indication on Unit 2 Ventilation Panel. Unit 2 has initiated 0-AP-50.00. Unit 2 remains at 100% power. Assume responsibility for E-0, Attachment 3, monitoring of SFP.
  • If asked, Unit 2 RWST cross-ties are open.

Field Operators:

  • If directed, field operators will perform local manipulations as required.

Role play as other individuals as needed.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Facility: Surry Power Station Scenario No.: 4 Op-Test No.: 2014-001 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Time in Core Life - Middle of Life; Core Cycle - Cycle 26 Unit 1 and 2 operating at 100%. All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
  • 1-CC-P-1D tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4)

RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.

  • Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
  • A BAST at 8.0 W/%.

Event Malf. Event Event No. No. Type* Description 1 N/A Deleted 2 RC4802, I - RO 1-RC-PT-1445 fails high, PRZR Pressure channel fail high. AP-31.00,

+1 Deg TS - SRO Increasing or Decreasing RCS Pressure.

3 MS1305, I - BOP Steam Pressure Channel III, B SG fails High. 0-AP-53.00, Loss of Vital

+1 Deg TS-SRO Instrumentation/Controls.

CH2101, 4 +1 Deg I - RO Failure of VCT Level Channel LT-115 High.

CC0302 5 CC0802 C - BOP Overcurrent on B CC pump with breaker mechanically stuck closed SW_15J9_ TS - SRO causing the trip of Stub Bus Supply breaker.

RF, TRIP C - RO 6 TS - SRO RD1236 R - RO / Dropped Rod Control Bank C, Group 1; AP-1.00, Rod Control SRO Malfunction, AP-23.00, Rapid Load Reduction.

N - BOP 7 RC MOV RC Loop C Tc MOV disc falls into flow stream, Valid First-Out 595, 30% M - All received, No Auto or Manual Reactor Trip. 1-FR-S.1, Response to Nuclear Generation/ATWS.

RD17 SI1502, 8 40% Deg LOCA outside of Containment in Unit 1 Valve Pit Area.

SI1603 M - All SI1606 SI2402 9 SI2405 SI Relay SI2A fails to Actuate, SI Relay SI5A Fails to Actuate; 1-SI-P-1A CC1801 not auto start; MOV-1115D, CH-MOV-115C, CH-MOV1289A, CV-TV-C - BOP 150A, and CH-TV-1204A fail to re-position on SI. 1-CC-P-1A Auto Start Disabled.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Event #1: Deleted.

Event #2: 1-RC-PT-1445 Fails High. (I - RO, TS-SRO)

The RO will respond to the alarms and indications received by performing the Immediate Actions of AP-53.00, Loss of Vital Instrumentations/controls; or 1-AP-31.00, Increasing or Decreasing RCS pressure. RCS pressure is expected to lower to less than 2205 psig for a short time period resulting in a Tech Spec consultation.

Verifiable Actions:

1) RO will place control switch for 1-RC-PCV-1456 in close.
2) BOP may place Rod Control in manual to stop rod motion caused by the reactivity inserted by the pressure coefficient.
3) RO will close 1-RC-MOV-1535 due to Technical Specification requirements.

Technical Specifications:

1) The SRO will consult Tech Specs, TS Section 3.1.A.6, and determine that 1-RC-PCV-1456 is Inoperable but capable of being manually cycled, and enter a one hour clock to close the block valve for the PORV. The block valve will remain energized.
2) Further consultation will find Tech Spec 3.12.F.1 to restore RCS pressure >2205 psig in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce Thermal Power to less than 5% in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The Core Operating Limits Report (COLR, DRP-21) provides the reference for 2205 psig RCS pressure.

Technical Requirements Manual/R.G. 1.97

1) No TRM or R.G. 1.97 requirements apply.

Event #3: Steam Pressure Channel III Fails High on B steam line causing B steam flow increase and B FRV to open. (I - BOP, TS - SRO)

The BOP will respond to the alarms and indication received by placing the B FRV in manual and restoring B SG NR level to program IAW 1-AP-53.00, Loss of Vital Instrumentation/Controls. The Abnormal Procedure will require the Controlling Steam Flow channel to be swapped to Channel IV so that the B FRV can be restored to Auto.

Verifiable Actions:

1) BOP will place the B FRV in manual and restore B SG NR level to program.
2) RO will shift controlling channel.

Technical Specifications The SRO should consult Tech Specs and determine the following:

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4

1) Tech Specs Section 3.7, Table 3.7-1, Item 17, Low steam generator water level with steam/feedwater flow mismatch, Operator Action 6. With the number of Operable channels on less than the total number of channels, Power Operation may proceed provided the channel is placed in the trip condition in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the channel may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance; if these requirements are not met, the Unit must be placed in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2) Tech Spec 3.7, Table 3.7-2, Item 1.c., High differential pressure between any steam line and the steam header, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the channels may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to less than 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3) Tech Spec 3.7, Table 3.7-2, Item 1.e.1 and 1.e.3, High Steam line flow in 2/3 steam lines coincident with low Tavg or low line pressure, Operator Action
20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the channels may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to less than 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4) Tech Spec Table 3.7-3, item 2a, Steam Line Isolation. Refers to Tech Spec Table 3.7-2, Item 1.e. See Above.
5) Tech Spec Table 3.7-6, Item 16, SG Pressure, 2 per SG are required. This condition is met.

Technical Requirements Manual/R.G. 1.97:

1) The TRM Section 3.3 2, Appendix R Instrumentation, Table 3.3.2-1, Steam Generator Pressure 1-MS-PI-1485 is a Primary indicator. One of the three listed transmitters must be Functional to meet the requirement. Two of the three are Functional. No TRM requirements for this failure. (The TRM review is normally performed by the STA in consultation with the Shift Manager; if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).

RG-1.97

1) RG-1.97 variables, Steam Generator pressure is an A-02 variable, 2 channels per SG are required, table refers to Tech Spec Table 3.7-6. (The RG 1.97 review is normally performed by the STA in consultation with the Shift Manager; if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).

Event #4: VCT Level Transmitter LT-115 Fails High. (I - RO)

The RO is expected to diagnose this failure based upon alarms and indications received.

The RO will perform the Immediate Action Steps of 0-AP-53.00, Loss of Vital Instrumentation/Controls and place the VCT divert valve, 1-CH-LCV-1115A, in the NORM position to stop divert of Letdown flow to the PDTT. The Team will continue through the abnormal procedure.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Verifiable Actions:

1) RO will place the control switch for 1-CH-LT-1115A in the NORM position to stop letdown diversion to the PDTT.

Technical Specifications:

1) There are no Tech Spec or TRM actions required for this failure.

Technical Requirements Manual:

1) None for this failure.

Reg. Guide 1.97:

1) RG 1.97 requirements: 1-CH-LI-1115 is a D-29 variable, Category 2. 1 channel is required. Required Action C from Attachment 2; restore the required channel to functional status and use alternate indication to accomplish this function, if possible (VCT level channel 1-CH-LI-1112 functional and meets this requirement). Completion Time 60 days if no alternate indication available OR on or before the next planned outage if an alternate indication is available. (The RG 1.97 review is normally performed by the STA in consultation with the Shift Manager, if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).

Event #5: Overcurrent of the B CC pump with the Breaker Stuck closed, resulting in the trip of the stub bus breaker 15J9 on overcurrent. (C - BOP, TS-SRO)

The BOP is expected to diagnose this failure based on alarms and indications received.

The BOP will place the B CC pump in PTL.

Verifiable Actions:

1) BOP will place the control switch for 1-CC-P-1B in PTL.
2) BOP will start 1-CC-P-1A.

Technical Specifications:

1) The SRO will consult Tech Specs 3.13.A.2 and 3.13.B, and determine that the minimum Operable CC pumps requirement is not met. For 2 Unit operation 3 CC pumps must be operable, and TS 3.13.B cannot be met, the SRO should identify a TS 3.01 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> clock to HSD, and a 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> clock to CSD.
2) Consult Tech Spec 3.5.A.1 and determine the Minimum Operable RHR pumps requirement is not met. This requires, IAW TS 3.5.B, that a 14 day clock be entered to restore A RHR pump to an Operable condition.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Technical Requirements Manual

1) IAW IAW TRM 3.7.9.A additional 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clocks are in effect to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status. Normally an STA function in consult with Shift Manager, recommend use of follow up question.

Event #6: Dropped Control Rod, M-4, Control Bank C, Group 1. (C - RO, R - RO, TS - SRO, R

- SRO, N - BOP)

The RO is expected to diagnose this failure based on alarms and indications received and place Rod Control in manual to stop outward rod motion IAW 0-AP-1.00, Rod Control Malfunction.

The Team will continue in AP-1.00 to the point where 0-AP-23.00, Rapid Load Reduction will be used to reduce reactor power to 70-74% to meet the TS requirement to be <75%

of Rated Power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Verifiable Actions:

1) RO will place rod control in manual.
2) BOP will perform actions of Annunciator Response Procedure 1G-F8, Bank D WITHDRAWAL to realign group step counters.

Technical Specifications:

1) The SRO will determine that the dropped control rod is Inoperable since it is misaligned from its Bank > +/- 12 steps. IAW Tech Spec 3.12.C.3, power must be reduced to < 75% Rated Power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and the High Neutron Flux trip setpoint shall be reduced to 85% of Rated Power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2) Shutdown margin must be determined to be satisfactory within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
3) Hot channel factors are shown to be within limits of TS 3.12.B.1 in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and it shall be demonstrated that the value of Fxy(Z) used in the Constant Axial Offset Analysis is still valid.
4) Reevaluation of each accident analysis of Table 3.12-1 is performed within 5 days, to confirm the previous analysis of these accidents remain valid.
5) If, except for operation at THERMAL POWER < 50% or for physics and control rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2%, then:
a. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either the hot channel factors shall be determined and the power level adjusted to meet the requirement of Specification 3.12.B.1, or

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4

b. The power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
6) If the QUADRANT POWER TILT exceeds 10%, the power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Event #7: Tcold Loop stop disc detaches and drops into the flowstream, Valid First-Out indication, No automatic or manual reactor trip, FR-S.1. (M - ALL)

This Event begins the Major Accident sequence. The RO will identify a First-Out alarm is received, the alarm is valid (Low Flow Condition in C RCS Loop), the reactor has not automatically tripped, attempt a manual reactor trip, and then perform the Immediate Action of 1-FR-S.1, Response to Nuclear Power Generation/ATWS.

The reactor trip breakers will be opened locally two (2) minutes after the Team directs an Operator to perform this action (based upon time critical operator action time requirement for locally tripping the reactor trip breakers).

The Team will complete 1-FR-S.1, transition to 1-E-0, Reactor Trip or Safety Injection to perform the Immediate Operator Actions, Transition to 1-ES-0.1, Reactor Trip Response, and perform a brief.

Verifiable Actions:

1) RO will attempt to trip the reactor using both reactor trip pushbuttons.
2) RO will check or place rods control in automatic.
3) RO will manually trip the turbine.
4) RO verifies control rods inserting at >48 steps per minute.
5) When rod speed lowers to < 48 steps per minute; RO places rod control in manual and inserts rods.

Critical Task:

CT-1: DRP-049 E-12, Insert negative reactivity into the core by at least one of the following methods before completing the Immediate Action Steps of FR-S.1.

Insert Control Rods in auto or manual within 30 seconds of the onset of the ATWS event.

Event #8: LOCA Outside of Containment. (M - ALL)

The Team will be alerted to this condition based upon alarms and indications received, return to 1-E-0, and manually Safety Inject.

The RO and SRO continue with E-0 while the BOP performs Attachments 1, 2, and 3 of E-0. The Team will transition from 1-E-0 to 1-ECA-1.2, LOCA Outside Containment. In 1-ECA-1.2, the LOCA will be isolated by closing 1-SI-MOV-1890C, common LHSI pump discharge to RCS Cold Legs. The Team will transition to 1-E-1, Loss of Reactor or Secondary Coolant.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Verifiable Actions:

1) RO will manually initiate SI.
2) During performance of 1-E-0 Attachments the BOP will identify and correct the following items: 1-SI-P-1A not auto start, 1-CH-MOV-1115D not auto open, 1-CH-MOV-1115C not auto close, 1-CH-MOV-1289A not auto close, 10CV-TV-150A and 1-CH-TV-1204A not auto close.

Critical Task:

CT-2: Critical Task: E 1.2. Trip all RCPs within 5 minutes of reaching RCP Trip Criteria. (WOG E-1-C).

CT-3: WOG ECA-1.2A, Isolate the LOCA outside containment before transition out of ECA-1.2, or cavitation of any LHSI pump. SPS- Isolate LOCA outside containment before transition out of ECA-1.2 (PSA).

Post Scenario Classification:

Follow-up Classification: Site Area Emergency, FS-1.1.

The Scenario can be terminated upon 1-E-1 entry or Lead Evaluator Cue.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Initial Conditions: IC #1 100%, MOL - Cycle 26. The unit has been at 100% power for > 30 days Pre-load malfunctions: (Trigger 30s) o SI2402, SI RELAY SI2A FAILS TO ACTUATE o SI2405, SI RELAY SI5A FAILS TO ACTUATE o AAC_SMS_MODE, OFF, AAC DG LOCAL MODE SWITCH POSITION o CC1801, DISABLE CCP1A AUTO START o SW_25J10_RF, 1-CC-P-1D CONTROL SWITCH, PTL Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:

AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

1-CC-P-1D id tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.

Turnover:

Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. . IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
  • 1-CC-P-1D, D CC pump tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
  • Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
  • A BAST at 8.0 W/%.

Event Malf. #s Severity Instructor Notes and Required Feedback 1 N/A N/A Deleted.

2 RC4802, +1 Deg 1-RC-PT-1445 fails high, PRZR Pressure channel fail high. AP-31.00, Increasing or Decreasing RCS Pressure.

3 MS1305, +1 Deg Steam Pressure Channel III, B SG fails High. 0-AP-53.00, Loss of Vital Instrumentation/Controls.

4 CH2101, +1 Deg Failure of VCT Level Channel LT-115 High.

CC0302 TRUE 5 CC0802 Overcurrent on B CC pump with breaker mechanically stuck closed causing the TRUE trip of Stub Bus Supply breaker.

SW_15J9_

RF TRIP 6 RD1236 Dropped Rod Control Bank C, Group 1; AP-1.00, Rod Control Malfunction, AP-TRUE 23.00, Rapid Load Reduction.

7. RC MOV 30%

RC Loop C Tc MOV disc falls into flow stream, Valid First-Out received, No Auto 595 or Manual Reactor Trip. 1-FR-S.1, Response to Nuclear Generation/ATWS.

TRUE RD17 SI1502, 40% Deg 8 SI1603 TRUE LOCA outside of Containment in Unit 1 Valve Pit Area.

SI1606 TRUE

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 9 SI2402 SI Relay SI2A fails to Actuate, SI Relay SI5A Fails to Actuate;1-SI-P-1A not auto SI2405 C - BOP start, CH-MOV-1115D, CH-MOV-115C, CH-MOV1289A, CV-TV-150A, and CH-TV-1204A fail to re-position of SI.

Scenario Objectives:

A. Deleted.

B. Given a failure of 1-RC-PT-1445 in the high direction respond IAW AP-53.00/AP-31.00 to regain control of RCS pressure.

C. Given the failure of Steam Pressure Channel III, B SG fails High repons IAW 0-AP-53.00, Loss of Vital Instrumentation/Controls.

D. Given the failure of VCT level 1-CH-LI-1115 high, respond IAW AP-53.00 to secure the divert of letdown flow to the PDTT.

E. Given the loss of the 1J stub bus, respond IAW 1K-H4 to restore CC flow to normal on Unit 1.

F. Given a dropped rod, respond IAW AP-1.00 and AP-23.00 to ramp the Unit to 70-74%.

G. Given a valid reactor trip signal with no automatic reactor trip respond IAW FR-S.1 to shutdown the reactor.

H. Given a LOCA outside of Containment respond IAW E-0 and ECA-1.2 to isolate the RCS leak path.

I. Given various component failing to reposition utilize E-0 Attachments to identify and place the components in the correct position.

SHIFT TURNOVER INFORMATION OPERATING PLAN:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

  • 1-CC-P-1D is tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training.

A BAST at 8.0 W/%.

PSA is Green.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 1 Page 11 of 98 Event

Description:

Perform 1-OP-RP-001. Section 5.2, Preparation for Channel II Testing.

Cue: When team ready.

Time Position Applicants Action or Behavior EVENT 1 - Deleted

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 12 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

Note: An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.

The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.

A facility representative will be present for consultation with the Evaluation Team, as needed.

Time Position Applicants Action or Behavior RO Diagnoses the event using the following:

Alarms:

1C-F8, PRZR HI PRESS 1D-H4, PRZR SFTY VV PWR RELIEF VV OPEN Indications:

1-RC-PCV-1456, PRZR PORV, RED Open Lights LIT.

RCS Pressure Decreasing.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS Note: SRO may directly enter 1-AP-31.00, Increasing or Decreasing RCS Pressure, Page 14.

RO [1] Check REDUNDANT INSTRUMENT CHANNEL(S) INDICATION - NORMAL Identifies RCS Pressure decreasing using 1-RC-PI-1444 or RCS Wide Range Pressure Indicated on A / B ICCM Display.

RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-RC-PV-1456 control switch in Close. Verifies 1-RC-PCV-1456 closes by GREEN Light LIT, RED Light off.

RO/BOP During pressure transient, the Rod Control Switch may be placed in MANUAL due to Rods stepping OUT due to pressure coefficient.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 13 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00 SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

  • PRZR Pressure Control, Step 5 RO The RO will identify that 1-RC-PI-1445 failed high.

NOTE: RCS pressure decrease will cause a slight decrease in RCS Tave due to negative reactivity from the moderator pressure coefficient.

SRO 5 CHECK PRZR SPRAY VALVE CONTROLLERS - NORMAL RO RO identifies PRZR Spray Valves controllers normal.

SRO 6 GO TO ( )-AP-31.00, INCREASING OR DECREASING RCS PRESSURE SRO announces transition to AP-31.00.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 14 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-AP-31.00 SRO [ 1 ] ___ CHECK PRZR PORVS - CLOSED RO Identifies 1-RC-PCV-1456 closed.

1-AP-31.00 Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-31.00 1-AP-31.00 CAUTION: A Safety Injection may occur if the unit is not tripped prior to RCS pressure decreasing below 2100 psig.

SRO 2 CHECK RCS PRESSURE - DECREASING RO Identifies RCS Pressure rising following PORV Closure.

2 RNO IF RCS pressure is stable or increasing following PORV closure, THEN GO TO Step 10.

Note: If the RO responds to Step as conditions were prior to PORV closure, this flow path is incorrect and a follow-up may be required.

1-AP-31.00 SRO 10 CHECK RCS PRESSURE - STABILIZING AT OR TRENDING TO 2235 PSIG RO Identifies RCS pressure trending to 2235 psig.

1-AP-31.00 SRO 11. GO TO STEP 17

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 15 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

1-AP-31.00 SRO 17 CHECK MASTER CONTROLLER GO TO Step 19

- IN MANUAL RO Identifies Master Pressure Controller in Auto 1-AP-31.00 SRO 19 CHECK PRZR PORVS - EITHER INOPERABLE

  • 1-RC-PCV-1455C

1-AP-31.00 20 CLOSE BLOCK VALVE FOR INOPERABLE PORV SRO

  • 1-RC-MOV-1535 if 1-RC-PCV-1456 inoperable RO Places 1-RC-MOV 1535 control switch in close. Monitors MOV until GREEN indicating light LIT and RED Light out.

1-AP-31.00 SRO 21 CHECK PRZR PORVS - EITHER GO TO Step 23 INCAPABLE OF BEING MANUALLY CYCLED

  • 1-RC-PCV-1455C
  • 1-RC-PCV-1456 RO States Both PORVs are capable of being manually cycled.

1-AP-31.00 SRO 23 NOTIFY THE FOLLOWING:

  • OM on call
  • I&C Notifies Shift Manager of the Event and requests notifications be made.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 16 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

1-AP-31.00 SRO 24 REFER TO TECH SPECS:

  • 3.1.A.5
  • 3.1.A.6
  • 3.1.C
  • 3.12.F
1) The SRO will consult Tech Specs, TS Section 3.1.A.6, and determine that 1-RC-PCV-1456 is Inoperable but capable of being manually cycled, and enter a one hour clock to close the block valve for the PORV. The block valve will remain energized.
2) Further consultation will find Tech Spec 3.12.F.1 to restore RCS pressure >2205 psig in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce Thermal Power to less than 5% in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The Core Operating Limits Report (COLR, DRP-21) provides the reference for 2205 psig RCS pressure.

NOTE: Following closure of block valve the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tech Spec clock clears. RCS pressure decreases to < 2205 psig during the transient; once the PORV has been closed, pressure recovers quickly and goes above 2205 psig.

SRO updates the Team concerning the identified items in Tech Specs and updates the Shift manager.

1-AP-31.00 SRO 25 REVIEW APPLICABILITY:

  • VPAP-2802
  • EAL Matrix SU6.1 SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.

1-AP-31.00 SRO 26 RESTORE PRESSURE CONTROL SYSTEM(S) TO NORMAL END EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 17 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-53.00 BOP Diagnoses failure 1-MS-PT-1485 with the following indications/alarms:

Alarms:

Indications:

  • Step increase in 1B SG Steam Flow indication CH-III
  • Increasing level on B SG.

0-AP-53.00 SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS 0-AP-53.00 BOP [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies Channel IV indication for steam flow/Steam Pressure is NORMAL 0-AP-53.00 BOP [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and lowers demand (FF < SF) to restore level to program

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 18 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00.

0-AP-53.00 SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

Note: Based on the feed flow > steam flow mismatch during initial stage of the Event, Calorimetric power may exceed 100% during restoration of B SG NR level to program.

0-AP-53.00 SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

0-AP-53.00 SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

SG Pressure, Step 7 BOP States B SG Pressure affected.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 19 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.

SRO 7. CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS -

NORMAL

  • Steam Pressure
  • Steam Flow
  • Feed Flow

Step 7. RNO IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level Control system has failed, THEN do the following:

a) Place the associated Feed Reg Valve in MANUAL.

BOP Verifies B SG MFRV controller, 1-FW-FCV-1488, in manual b) Control SG level at program level (44%, a band will be given).

BOP Verifies B SG NR level is returning to program level.

c) Select the redundant channel for affected SG(s)

RO Selects Channel IV Steam Flow for B SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV).

d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.

BOP Places B SG FRV controller, 1-FW-FCV-1488, in automatic control

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 20 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO Step 7. RNO (Continued)

Perform follow-up actions:

a) Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.

b) Refer to the following Tech Spec 3.7 items:

  • Table 3.7-1, 12 and 17
  • Table 3.7-2, 1.c, 1.e, and 3.a
  • Table 3.7-3, 2.a, and 3.a
1) Tech Specs Section 3.7, Table 3.7-1, Item 17, Low steam generator water level with steam/feedwater flow mismatch, Operator Action 6. With the number of Operable channels one less than the total number of channels, Power Operation may proceed provided the channel is placed in the trip condition in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the channel may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance; if these requirements are not met, the Unit must be placed in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2) Tech Spec 3.7, Table 3.7-2, Item 1.c., High differential pressure between any steam line and the steam header, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the channels may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to less than 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3) Tech Spec 3.7, Table 3.7-2, Item 1.e.1 and 1.e.3, High Steam line flow in 2/3 steam lines coincident with low Tavg or low line pressure, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the channels may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to less than 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4) Tech Spec Table 3.7-3, item 2a, Steam Line Isolation. Refers to Tech Spec Table 3.7-2, Item 1.e. See Above
5) Tech Spec Table 3.7-6, Item 16, SG Pressure, 2 per SG are required. This condition is met (2 of 3 channels still Operable).

c) Refer to Attachment 1.

d) IF no other instrumentation failure exists, THEN GO TO Step 13.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 21 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO 13. CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001.

SRO/RO reviews OPT-RX-001, Attachment 4, and determines Calorimetric is NOT impacted and OPT-RX-007 will NOT need to be performed.

0-AP-53.00 SRO 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 16 if not Reg. Guide 1.97)

SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-MS-PT-1485 is a Reg. Guide 1.97 component.

0-AP-53.00 SRO 15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.

[CEP 99-0029 requires two channels of Steam Pressure indication per steam generator, refers to Tech Spec 3.7, Table 6, Item 16, 2 required per SG.]

0-AP-53.00 SRO 16. Review the following:

  • TS 3.7 Determines Table 3.7-1 item 17, 3.7-2 item 1.c. and 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). Also TS-3.7, Table 6, item 16, two SG Pressure Indicators per SG.
  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

[VPAP-2802 and TRM Section 3.3 are not impacted by this failure.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 22 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO 17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS BOP Reports no additional failure exists SRO GOES TO Step 19 0-AP-53.00 SRO 19. PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC
  • I&C END EVENT #3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 4 Page 23 of 98 Event

Description:

Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.

Cue: When initiated by Team Time Position Applicants Action or Behavior Diagnoses failure 1-CH-LT-1115 with the following indications/alarms:

BOP Alarms:

  • 1-CH-LCV-1115A Amber Divert light LIT.
  • Decreasing VCT level on channel 1-CH-LI-1112.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS RO [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL RO identifies Channel LI-1112 VCT Level indication is NORMAL.

RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION RO places the control switch for 1-CH-LCV-1115A in NORM position to close the VCT Divert Valve. Monitors to ensure amber light extinguishes and VCT level stabilizes.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00.

SRO Note: Discusses with RO control of VCT level and monitoring of channel 1-CH-LT-1112 to ensure that VCT level will not drop to the point where the CH pumps could air bind. The SRO will set a band for manual makeup to the VCT and a minimum VCT level where the manual swap to the RWST will be required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 4 Page 24 of 98 Event

Description:

Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.

Cue: When initiated by Team SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

VCT Level, Step 12e RO SRO 12 e) VCT level Instrumentation - NORMAL RO States 1-CH-LT-1115, VCT Level Channel affected.

SRO Refer to Attachment 6 Attachment 6, 0-AP-53.00 SRO If ( )-CH-LT-( )115 fails high, ( )-CH-LCV-( )115A will open. Manual control of the blender will be required. Automatic swap-over of the CHG pump suction from the VCT to the RWST will not function.

a. VCT High level divert of ( )-CH-LCV-( )115A to PDT at 85%
b. VCT High level alarm at 82%
c. Auto makeup to VCT stop at 34%
d. Auto makeup to VCT start at 27%
e. VCT Low level alarm at 24%
f. CHG pump suction swap over to the RWST at 13% (2/2)

SRO Note: Discusses with RO control of VCT level and monitoring of channel 1-CH-LT-1112 to ensure that VCT level will not drop to the point where the CH pumps could air bind. The SRO will set a band for manual makeup to the VCT and a minimum VCT level where the manual swap to the RWST will be required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 4 Page 25 of 98 Event

Description:

Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.

Cue: When initiated by Team SRO 13 CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001 SRO/RO SRO/RO determines that OPT-RX-001, Attachment 4, is NOT impacted and OPT-RX-007 will NOT need to be performed.

14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 SRO VARIABLE (Go to Step 16 if not Reg. Guide 1.97)

The STA will report that 1-CH-LI 1115 is a Reg. Guide 1.97 component.

SRO 15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.

[CEP 99-0029 requires 1 channel of VCT level indication. 1-CH-LT-1112 may be used as an alternate indication. Restore 1-CH-LT-1115 before the next outage.]

SRO 16. Review the following:

  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO SRO will consult Tech Specs and find no items affected.

SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

[VPAP-2802 and TRM Section 3.3 are not impacted by this failure.]

0-AP-53.00 SRO 17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS BOP Reports no additional failure exists SRO GOES TO Step 19

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 4 Page 26 of 98 Event

Description:

Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.

Cue: When initiated by Team

19. PROVIDE NOTIFICATIONS AS NECESSARY:

SRO

  • Shift Supervision
  • OMOC
  • I&C END EVENT #4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 27 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

Time Position Applicants Action or Behavior TEAM Diagnose the failure using the following:

Alarms:

1K-D5, CC PP 1B IN LOCAL CONTROL OR OL TRIP 1K-E7, CC PPS DISCH HDR LO PRESS 1K-H4, 4KV EMERG BUS STUB BUS TIE BKR TRIP Indications:

Breaker 15J9, 1J Stub Bus Breaker, indicates Open on PCS Breaker 15J10, 1-CC-P-1B breaker indication RED and GREEN Light OFF.

1-CC-P-1B amps indication at 0. 1-CC-P-1A not running.

Note: ARP Steps start on Page 30.

Note: If the Team opts to trip the reactor, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-AP-10.07 SRO SRO will hold a Transient Brief and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Directs the BOP to review ARPs for Lit annunciators, SRO/RO will continue with 1-AP-10.07.

Directs RO/BOP to contact Auxiliary Building Operator to check status of 1-CC-P-1A and 1-CC-P-1B. Direct Service Building Operator to check status of 1-CC-P-1B breaker, BKR 15J10, and the 1J stub bus breaker, 15J9.

Completes Brief and continues with AP-10.07.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 28 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

Step 1, 1-AP-10.07 SRO NOTE:

  • If both units are affected, local actions should be coordinated.
  • The AAC Diesel Generator will automatically start if an undervoltage occurs on Transfer Buses D and F.
  • With Degraded Voltage or Undervoltage on 2J Bus, or a loss of Unit 2B DC Bus, Breaker 15J3 will not close automatically, except with a valid Unit 1 SI signal.
1. CHECK UNIT - BLACKOUT HAS OCCURRED
  • Transfer Buses D and F - DEENERGIZED AND
  • All Station Service Buses - DEENERGIZED RO Reports Blackout has not occurred.

SRO GOES TO Step 39.

Step 39, 1-AP-10.07 SRO 39 CHECK THE FOLLOWING BREAKERS - ANY OPEN:

  • 15J8 RO Reports Breakers Closed.

39 RNO IF all 480V Emergency Buses energized, THEN GO TO Step 75.

SRO Goes to Step 75.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 29 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

Step 75, 1-AP-10.07 SRO 75 CHECK ANY STATION SERVICE BUS - DEENERGIZED:

  • 15A1 and 15A2 - OPEN OR
  • 15B1 and 15B2 - OPEN OR
  • 15C1 and 15C2 - OPEN RO Reports breakers 15A2 / 15B2 / 15C2 closed.

SRO 75 RNO IF ALL 480V Station Service Buses are energized, THEN GO TO Step 97.

SRO Goes to Step 97.

Step 97, 1-AP-10.07 SRO 97 NOTIFY THE FOLLOWING:

  • OMOC
  • Electrical Foreman ARP 1K-D5 BOP 1 CHECK 1-CC-P-1B IN LOCAL CONTROL DUE TO PLANT EVOLUTION 1-CC-P-1B not in Local due to Plant Evolution.

No Plant evolution in progress.

IF 1-CC-P-1B tripped due to leak or rupture, THEN do the following:

No leak or rupture indicated.

IF leak or rupture NOT present, THEN GO TO Step 3.

Go to Step 3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 30 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

ARP 1K-D5 BOP 3. VERIFY STANDBY CC PP - STARTED

  • 1-CC-P-1A No, 1-CC-P-1A not running Consults SRO concerning Manual start of 1-CC-P-1A.

Announces and Starts 1-CC-P-1A.

ARP 1K-D5 BOP 4 CHECK 1-CC-P-1B - TRIPPED DUE TO UNDERVOLTAGE ON THE 1J EMERGENCY BUS Do the following:

a) IF CC pump NOT tripped, THEN do the following:

b) Locally check breaker 15J10.

c) Locally check 1-CC-P-1B.

BOP When local status of 1-CC-P-1B received, Focus Brief to inform Team that 1-CC-P-1B normal; 1-CC-P-1B breaker is closed, breaker 15J10 closed with an overcurrent trip flag, breaker 15 J9, stub bus breaker, is open with an overcurrent trip flag.

d) IF unable to restore 1-CC-P-1B, THEN do the following:

1) Initiate a Condition Report.
2) Review Tech Spec 3.13.
3) GO TO Step 7.

ARP 1K-D5 BOP 7 VERIFY CC SYSTEM PARAMETERS - NORMAL

  • CC Surge Tank Level - STABLE
  • CC Pump amps - STABLE
  • AUX BLDG and CTMT Sump levels - NORMAL Review parameters, identify no trends exist, report parameters as normal.

ARP 1K-D5 BOP 8 PROVIDE NOTIFICATIONS:

  • OMOC

Move to next ARP.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 31 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

ARP 1K-E7 BOP 1 VERIFY CC HEADER PRESSURE - LESS THAN 90 PSIG

  • PI-CC-100, CC PP DISCH PRESS Reports PI-CC-100 indicates approximately 100 psig.

Step 1 RNO Do the following:

a) Increase surveillance of CC parameters.

b) Initiate a Work Request.

c) GO TO Step 18.

ARP 1K-E7 BOP 18 NOTIFY SHIFT SUPERVISION Notifies SRO, ARP 1K-E7 complete, a CR is required.

Moves to 1K-H4 ARP ARP 1K-H4 BOP 1 VERIFY ALARM - LOSS OF EMERGENCY BUS

  • Bus 1H Undervolt - 15H8 TRIPPED OR
  • Bus 1J Undervolt - 15J8 TRIPPED Identifies 1H and 1J not tripped Step 1 RNO Do the following:

a) Check for loss of Stub Bus loads:

  • RHR Pump Identifies Stub bus loads have been lost.

Step 1 RNO b) IF Stub Bus loads lost, THEN do the following:

1) Start standby pumps IAW Shift Supervision direction.
2) Locally check stub bus tie breaker cubicles in ESGR.
3) IF Stub Bus Breaker Cubicle Relays (Type IAC) orange drop - IN, THEN GO TO Step 4.

Based on Focus Brief - Goes to Step 4.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 32 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

ARP 1K-H4 BOP 4 CHECK RHR AND CC - RESTORED AS NECESSARY Identifies 1-CC-P-1A running.

ARP 1K-H4 BOP 5 PROVIDE NOTIFICATIONS AS NECESSARY:

  • OMOC
  • Electrical Foreman
  • Control Operations
  • Shift Supervision Notifies SRO that in addition to previous individuals notified, the Electrical Forman needs to be notified ARP 1K-H4 BOP 6 SUBMIT A CONDITION REPORT Notifies SRO that a CR is required.

ARP 1K-H4 BOP 7 REVIEW TECH SPECS Notifies SRO to Review Tech Specs SRO The SRO will consult Tech Specs 3.13.A.2 and 3.13.B, and determine that the minimum Operable CC pumps requirement is not met. For 2 Unit operation, 3 CC pumps must be operable, and TS 3.13.B cannot be met, the SRO should identify a TS 3.01, 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> clock to HSD, and a 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> clock to CSD.

Consult Tech Spec 3.5.A.1 and determine the Minimum Operable RHR pumps requirement is not met. This requires, IAW TS 3.5.B, that a 14 day clock be entered to restore A RHR pump to an Operable condition.

[TRM Table 3.7.9-1; IAW TRM 3.7.9.A, additional 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clocks are in effect to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 33 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

SRO Directs STA to review Tech Specs and TRM.

STA Acknowledge direction to review Tech Specs and TRM. STA will report TRM has been reviewed and discussed with the Shift Manager.

SRO Contacts the Shift Manager to provide an update on Plant Status, Tech Spec Clocks entered, and request notification of the OMOC and Electrical Foreman.

END EVENT #5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 34 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior Team Diagnoses the dropped rod with the following indications/alarms:

Alarms:

  • 1G-B5, COMPUTER PRINTOUT ROD CONT SYS.
  • 1G-C4, UPPER ION CHAMBER DEVIATION OR AUTO DEFEAT <50%.
  • 1G-D4, LOWER ION CHAMBER DEVIATION OR AUTO DEFEAT <50%.
  • 1G-H1 - NIS DROPPED ROD FLUX DECREASE > 5% PER 2 SEC
  • 1G-F8, ROD BANK D WITHDRAWAL.

Indications:

RO

  • Outward Rod Motion.
  • RCS Temperature and Pressure decrease.
  • Flux Variations (radial).

In accordance with the immediate actions of 1-AP-1.00 (Rod Control System Malfunction) the RO will place Control Rods in MANUAL to stop the outward rod motion.

RCS pressure <2205 psig places the unit in a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> clock iaw TS. 3.12.F.1 (and COLR) - it is expected that the SRO will track this clock (entry/exit times).

0-AP-1.00 SRO Enters 0-AP-1.00 (Rod Control System Malfunction).

SRO CAUTION prior to Step 1:

  • If Tave decreases below 530 °F, 1-E-0, Reactor Trip or Safety Injection, must be implemented.

RO [1] CHECK FOR EITHER OF THE FOLLOWING:

  • Continuous rod withdrawal
  • Continuous rod insertion RO will note that there was a continuous rod withdrawal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 35 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

RO/BOP [2] STOP ROD MOTION

a. Put ROD CONT MODE SEL switch in MANUAL
b. Verify rod motion - STOPPED RO will place control rods in MANUAL and note that Rods stopped moving.

0-AP-1.00 SRO The team will hold a transient brief. During the brief the dropped rod will be discussed.

The RO and BOP will report out critical parameters, as per placard on Main Control Room Bench Board.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

0-AP-1.00 RO

3. CHECK ROD MOTION - DUE TO INSTRUMENTATION FAILURE
  • First Stage Impulse Pressure
  • Tave/Tref
  • Nuclear Instrumentation RO will note that an instrumentation failure did not exist. The team will transition to the RNO for Step 3.

0-AP-1.00 RO

3. RNO If rod motion due to a dropped rod, THEN GO TO Step 6.

RO will note that dropped rod caused the rod motion.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 36 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

0-AP-1.00 RO

6. CHECK IF ANY ROD DROPPED:

PER 2 SEC - LIT OR

  • Rod Bottom Lights - ANY LIT OR
  • Any Rod On Bottom light - LIT OR
  • Indication of a partially dropped rod in the core The RO will note that they have multiple indications of a dropped rod in the core.

0-AP-1.00 RO

7. CHECK REACTOR STATUS PRIOR TO FAILURE - CRITICAL 0-AP-1.00 RO 8. CHECK ONLY ONE ROD AFFECTED 0-AP-1.00 RO
9. CHECK REACTOR POWER - GREATER THAN 25%

0-AP-1.00 BOP/RO

10. CHECK UNIT CONDITIONS - STABLE 0-AP-1.00 RO
11. PLACE ROD CONTROL IN MANUAL 0-AP-1.00 RO/BOP
12. CHECK POWER RANGE NIs - ANY DROPPED ROD SIGNAL PRESENT 0-AP-1.00 BOP
13. RESET NIS DROPPED ROD SIGNAL IAW ATTACHMENT 4 Note: Attachment 4 of AP-1.00 is located on Page 40.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 37 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

0-AP-1.00 RO

14. CHECK ANNUNCIATOR 1G-F8, ROD BANK D WITHDRAWAL - NOT LIT If alarm is LIT, then the RNO will direct the team to initiate Attachment 5 - This attachment follows attachment 4 at the end of this event.

Note: This may not be lit if the ROBOP quickly placed rods in MANUAL when withdrawing or ARP 1G-F8, Bank D Withdrawal, has been completed.

0-AP-1.00 SRO Note prior to Step 15:

  • Quadrant power tilt may cause unit ramp requirements to be more restrictive.

0-AP-1.00 SRO

15. VERIFY QUADRANT POWER TILT RATIO
  • Initiate Attachment 6, QUADRANT POWER TILT CALCULATION

Summary of applicable Tech Specs are found following Step 18.

0-AP-1.00 SRO Notes prior to Step 16:

  • Checking that the unit is operating between Hot Zero Power and Hot Full Power, that there is only one fully dropped (less than 10 steps) control rod, and that all other rods are above the rod insertion limit, checks that adequate SDM exists.
  • SDM must be re-verified using 1-OP-RX-001 every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the control rod was dropped until the Reactor is shutdown or the rod is declared operable.

0-AP-1.00 SRO

16. VERIFY SHUTDOWN MARGIN (WITHIN ONE HOUR)
  • The fully dropped rod (less than 10 steps) is the only inoperable rod AND
  • All other rods are greater than the Rod Insertion Limit 0-AP-1.00 SRO
17. MAKE NARRATIVE LOG ENTRY THAT SDM IS MET

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 38 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

SRO Caution prior to Step 18:

  • Loop T is the most accurate measure of Reactor power with a mis-aligned rod, and must be monitored during the ramp and used as a basis for stabilizing power.

RO 18. CHECK REACTOR POWER - LESS THAN OR EQUAL TO 75%

Step 18 RNO actions:

Do the following:

a. Reduce Reactor Power to between 70% - 74% within one hour.
b. Reduce NIS High Flux trip setpoints to less than or equal to 85% within the following four hours.
c. WHEN Reactor Power has been reduced, THEN GO TO Step 19.

The team will enter AP-23.00 to reduce reactor power.

Note: 0-AP-23.00, Rapid Load Reduction, actions start on page 42.

Evaluators Note: Go to EVENT 7 when the Examiner has seen a sufficient change in power level during the ramp in AP-23.00.

SRO Applicable Tech Specs for Dropped Rod:

3.12.B.6:

If, except for operation at THERMAL POWER < 50% or for physics and control rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2%, then:

c. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either the hot channel factors shall be determined and the power level adjusted to meet the requirement of Specification 3.12.B.1, or
d. The power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
e. If the QUADRANT POWER TILT exceeds 10%, the power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 39 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

Applicable Tech Specs for Dropped Rod: (Continued) 3.12.C.3:

Startup and POWER OPERATION may continue with one control rod assembly inoperable provided that within one hour either:

a. The control rod assembly is restored to OPERABLE status, as defined in Specification 3.12.C.1 and 2, or
b. the shutdown margin requirement of Specification 3.12.A.3.c is satisfied.
c. POWER OPERATION may then continue provided that:
1) either:

a) power shall be reduced to less than 75% of RATED POWER within one (1) hour, and the High Neutron Flux trip setpoint shall be reduced to less than or equal to 85% of RATED POWER within the next four (4) hours, or b) the remainder of the control rod assemblies in the group with the inoperable control rod assembly are aligned to within 12 steps of the inoperable rod within one (1) hour while maintaining the control rod assembly sequence and insertion limits specified in the CORE OPERATING LIMITS REPORT; the THERMAL POWER level shall be restricted pursuant to Specification 3.12.A during subsequent operation.

2) the shutdown margin requirement of Specification 3.12.A.3.c is determined to be met within one hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 40 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

BOP ATTACHMENT 4 of AP-1.00 - RESETTING NIS DROPPED ROD SIGNALS Perform the following for each NI with a dropped rod status light lit.

1. N41 RESET a) Place the Power Range Test Switch in RESET.

b) Check the Dropped Rod Status Light on N41 - NOT LIT.

c) Return the Power Range Test Switch to NORMAL.

2. N42 RESET a) Place the Power Range Test Switch in RESET.

b) Check the Dropped Rod Status Light on N42 - NOT LIT.

c) Return the Power Range Test Switch to NORMAL.

3 N43 RESET a) Place the Power Range Test Switch in RESET.

b) Check the Dropped Rod Status Light on N43 - NOT LIT.

c) Return the Power Range Test Switch to NORMAL.

4. N44 RESET a) Place the Power Range Test Switch in RESET.

b) Check the Dropped Rod Status Light on N44- NOT LIT.

c) Return the Power Range Test Switch to NORMAL.

5. Check annunciator ( )G-H1, NIS DROPPED ROD FLUX DECREASE >5% PER SEC - NOT LIT
6. Check annunciator ( )G-F8, ROD BANK D WITHDRAWAL - NOT LIT
7. IF ( )G-F8, ROD BANK D WITHDRAWAL is LIT, THEN initiate Attachment 5.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 41 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

BOP ATTACHMENT 5 of AP-1.00 - RESPONSE TO ROD BANK D WITHDRAWAL

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 42 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 0-AP-23.00 TEAM 0-AP-23.00 (RAPID LOAD REDUCTION) Actions SRO The team will hold a transient brief. During the brief, the upcoming ramp will be discussed.

The RO and BOP will report out critical parameters, as per placard on Main Control Room Bench Board. It is expected that the RO will discuss reactivity parameters associated with the ramp from the pre-planned ramp plans taking in account the conditions presented by the dropped rod.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

The following reactivity plan will be discussed for a ramp to 75%:

  • Gallons of boric acid required as per plan - 146 gallons, Rate of 5.8 gpm.
  • D control bank end at 197 steps, 1957 gallons PG to stabilize.
  • Subtracted from the boration will be the equivalent boron added from the dropped rod - 9.5 gallons for each degree of Tave decrease - this should be about 42 gallons based on a 4.4° temp decrease. This will be subtracted from the initial 146 gallons - therefore, approximately 104 gallons of boric acid are required to be added.

EVALUATOR NOTE: RO Emergency borates for 25 seconds which corresponds to

~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.

SRO Caution Prior to Step 1:

  • Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.

Notes Prior to Step 1:

  • Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
  • When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
  • Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
  • The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
  • For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 43 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

0-AP-23.00 RO 1. TURN ON ALL PRZR HEATERS

2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:

BOP a) Check turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.

RO b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5°F.

SRO/BOP c) Check or place turbine in IMP IN as determined by Shift Supervision The SRO can choose IMP IN or IMP OUT.

d) Adjust SETTER to desired power level BOP e) Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute) f) Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) g) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.

SRO 3. CHECK EMERGENCY BORATION - REQUIRED The team may decide to emergency borate after the ramp has progressed to the point that Tave and Tref are matched (or close).

SRO Note Prior to Step 4:

  • Step 4 or Step 5 may be performed repeatedly to maintain Tave and Tref matched, Flux in band, and control rod position above the LO-LO insertion limit.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 44 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

0-AP-23.00 RO 4. PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:

a) Check or raise CHG flow to greater than 75 gpm b) Transfer the in-service BATP to FAST c) Open ( )-CH-MOV-( )350 d) Monitor EMRG BORATE FLOW

  • ( )-CH-FI-( )110 e) After required emergency boration, perform the following:
1) Close ( )-CH-MOV-( )350
2) Transfer the in-service BATP to AUTO
3) Restore Charging flow control to normal NOTE: RO Emergency borates for 25 seconds which corresponds to ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.

RO 5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.

SRO Notes Prior to Step 6:

  • If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
  • RCS Tave must be maintained less than or equal to 577°F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
  • I & C should be contacted to provide assistance with adjusting IRPIs.

RO 6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 45 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

RO *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.

BOP 8. MONITOR STEAM DUMPS FOR PROPER OPERATION 0-AP-23.00 SRO 9. NOTIFY THE FOLLOWING:

  • Energy Supply (MOC)
  • Polishing Building
  • Chemistry
  • OMOC SRO 10. EVALUATE THE FOLLOWING:
  • VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.

[VPAP-2802 and EPIP are not applicable for this event.]

SRO 11. CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR When reactor power has decreased >15%, then chemistry will be notified.

END EVENT #6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 46 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Adjust 1-CH-YIC-1113 to desired total gallons RO 3. Adjust 1-CH-FC-1113A to desired flow rate.

RO 4. Place the MAKE-UP MOD SEL switch in the BORATE position.

RO 5. Place the MAKE MODE CNTRL switch in the START position.

RO 6. Check proper valve positions.

RO 7. Adjust boration rate using 1-CH-FC-1113A, as necessary.

RO 8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.

a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.

b) Enter N/A for the remaining steps in this Attachment.

Attachment 5 is on the next page RO 9. Check controllers for Primary Grade water and Boric Acid are set correctly.

RO 10. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 11. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 12. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 47 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions

1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
5. Place the MAKE-UP MODE CNTRL switch in the START position.
6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
7. Check proper valve positions.
8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position
9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
10. Check or place the control switches in the AUTO position.
11. Check controllers for Primary Grade water and Boric Acid are set correctly.
12. Place the MAKE-UP MODE SEL switch in the AUTO position.
13. Place the MAKE-UP MODE CNTRL switch in the START position.
14. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 48 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

Time Position Applicants Action or Behavior Team Diagnose the failure based on the following:

Alarms:

1E-B10, LOSS OF COOL FLOW PWR > P8, RED 1E-A3, RC LOOP 1C LO FLOW CH 1 1E-B3, RC LOOP 1C LO FLOW CH 2 1E-C3, RC LOOP 1C LO FLOW CH 3 Indications:

Low flow indication on C loop, CH-1, CH-2, CH-3 Reactor - Critical RO Attempt to Trip the Reactor by pressing BB-1 and BB-2 Reactor Trip Pushbuttons.

GO TO FR-S.1 Critical Task: CT-1: DRP-049 E-12, Insert negative reactivity into the core by at least one of the following methods before completing the Immediate Action Steps of FR-S.1. Insert Control Rods in auto or manual within 30 seconds of the onset of the ATWS event.

Critical Step Start Time: ________________

1-FR-S.1 CAUTION: RCPs should not be tripped with Reactor power greater than 5%.

RO [ 1] VERIFY REACTOR TRIP: Verify or place control rods in Auto.

a) Manually trip Reactor b) Check the following:

  • All Rods On Bottom light - LIT

OPEN

  • Neutron Flux - DECREASING RO Identifies Reactor NOT Tripped, Performs RNO Action 1-FR-S.1 RO [2] MANUALLY TRIP THE TURBINE:

RO presses Both Turbine Trip Pushbuttons, Simultaneously.

  • Verify all turbine stop valves - CLOSED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 49 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-FR-S.1 RO [3] VERIFY CONTROL RODS - INSERTING IN AUTO AT GREATER THAN 48 STEPS /

MINUTE Critical Task Stop Time: ____________________

RO/BOP Manually insert control rods.

When Rod Speed lowers, places Rods in MANUAL, and inserts Rods.

4 VERIFY AFW PUMPS RUNNING:

SRO a) MD AFW pumps - RUNNING BOP b) TD AFW pump - RUNNING IF NECESSARY BOP BOP check MD / TD AFW Pumps Running.

SRO 1-FR-S.1 SRO 5 INITIATE EMERGENCY BORATION OF RCS:

a) Verify CHG flow - GREATER THAN 75 GPM RO Check CHG FLOW > 75 gpm.

b) Align boration path:

SRO 1) Put BATP in FAST RO Places 1-CH-P-2A, A BAST Recirc Pump, in FAST.

SRO 2) Open 1-CH-MOV-1350 RO Places control switch 1-CH-MOV-1350 in OPEN.

SRO 3) Verify emergency borate flow RO Checks Flow on 1-CH-FI-1110 rises to 110 gpm.

SRO c) Check PRZR pressure - LESS THAN 2335 PSIG RO Checks RCS Pressure < 2335 psig using RCS NR or WR Pressure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 50 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-FR-S.1 SRO *6 CHECK IF SI INITIATED: GO TO Step 8 RO

  • LHSI pumps - RUNNING
  • A-F-3
  • A-F-4 Identifies SI NOT initiated, SRO GOES TO STEP 8.

1-FR-S.1 SRO 8 CHECK IF THE FOLLOWING TRIPS HAVE OCCURRED:

RO a) Reactor trip b) Turbine trip SRO Directs BOP to contact Service Building Operator to locally open Unit 1 Reactor Trip Breakers.

NOTE: Two (2) Minutes will elapse from the time an Operator is dispatched to open the Reactor Trip breakers until the Simulator Operator Opens the breakers.

Based on Time Critical Operator Action.

1-FR-S.1 NOTE: If adverse CTMT conditions have been exceeded, the Gamma-Metrics Excore Neutron Monitor system (Source and Wide Ranges) should be used to monitor neutron flux for the duration of the event.

  • 9 CHECK REACTOR - SUBCRITICAL SRO a) Check power range channels - LESS THAN 5% [Gamma-Metrics Wide Range Power - LESS THAN 5%]

RO Identifies Reactor Power < 5%.

b) Check Intermediate range channels - NEGATIVE STARTUP RATE [Gamma-Metrics Wide Range Power - DECREASING]

RO Identifies negative SUR on IR Channels.

SRO c) GO TO Step 18

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 51 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-FR-S.1 CAUTION: Boration should be continued to obtain adequate shutdown margin during subsequent actions.

SRO 18 RETURN TO PROCEDURE AND STEP IN EFFECT SRO Announces Transition to E-0.

SRO Directs Reactor Operator to perform E-0 Immediate Actions Steps.

1-E Reactor Trip or Safety Injection RO [1] CHECK REACTOR TRIP:

a) Manually trip reactor Pushes the reactor trip push buttons.

b) Check the following:

  • All Rods On Bottom light - LIT
  • Neutron flux - DECREASING RO [2] CHECK TURBINE TRIP:

RO a) Manually trip the turbine Pushes the turbine trip push buttons.

b) Verify all turbine stop valves - CLOSED c) Isolate reheaters by closing MSR steam supply SOV

  • 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)

Identifies that Output Breakers did open RO [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 52 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

[4] CHECK IF SI INITIATED:

RO a) Check if SI is actuated:

  • LHSI pumps - RUNNING
  • A-F-3 SI INITIATED - TRAIN A
  • A-F-4 SI INITIATED - TRAIN B RO RO will determine that SI has NOT occurred and perform step 4a RNO actions:

4a RNO Check if SI is required or imminent as indicated by any of the following:

  • Low PRZR pressure
  • High steamline differential pressure
  • High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.

RO reports Immediate Actions of E-0 are complete, SI not in service or required, and recommends transition to ES-0.1.

After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.

SRO SRO will lead a brief using the brief checklist.

The RO will provide critical parameters using the Brief placard.

The BOP will provide critical parameters using the brief placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

The SRO will direct the BOP to perform ES-0.1, Transient AFW Control, Attachment 5 of ES-0.1, while the RO and SRO continue with ES-0.1.

Note: Attachment 5 of ES-0.1 is located at the End of this Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 53 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-ES-0.1 NOTE: Team may elect to secure the C RCP.

NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM SRO GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.

  • 1 CHECK RCS TEMPERATURE CONTROL RO a) Check RCPS - ANY RUNNING Reports all three RCPs running, C with abnormally low flow.

b) Monitor RCS Average Temperature

1) STABLE AT 547°F OR RO 2) TRENDING TO 547°F Reports RCS temperature stable at 547 °F.

1-ES-0.1 SRO 2 CHECK FW STATUS:

a) Check RCS Average temperatures - LESS THAN 554°F RO Identifies RCS Temperature < 554 °F b) Check Feed REG valves - CLOSED RO Identifies all FRVs closed.

c) Close SG FW isolation MOVs

  • 1-FW-MOV-154A
  • 1-FW-MOV-154B
  • 1-FW-MOV-154C RO/BOP Close 1-FW-MOV-154 A / B / C d) Check AFW pumps - RUNNING
  • Motor Driven AFW pumps

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 54 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

BOP Identifies MD / TD AFW pump running.

e) Check total AFW flow - GREATER THAN 540 GPM (350 GPM W/O RCPs)

BOP Identifies AFW flow > 540 GPM (IAW band given by SRO) f) Check emergency buses - BOTH ENERGIZED RO Identifies emergency buses energized.

g) Control feed flow to maintain narrow range level between 22% and 50%

BOP Acknowledges direction to control AFW flow to obtain band.

1-ES-0.1 SRO 3 CHECK CHARGING IN SERVICE RO Provides CH flow value and trend to SRO.

Note: If not already implemented, go to Event #8.

1-ES-0.1 SRO 4 CHECK CC SYSTEM STATUS:

a) Check SW to CC HXs - IN SERVICE RO Identifies two (2) CC headers flowing to CC HXs.

b) Check CC pumps - AT LEAST ONE RUNNING RO Identifies 1-CC-P-1A running.

1-ES-0.1 SRO 5 CHECK PRZR LEVEL CONTROL:

a) Check PRZR level - GREATER THAN 15%

RO Reports PRZR level and trend to SRO.

b) Check letdown - IN SERVICE RO Reports Letdown flow and trend to SRO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 55 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

Time Position Applicants Action or Behavior ES-0.1, Attachment 5 BOP 1 Maintain minimum AFW flow of 540 gpm with RCP(s) in service until one SG Narrow Range level is greater than 12%.

ES-0.1, Attachment 5 BOP 2 Maintain minimum AFW flow of 350 gpm with NO RCPs running, until one SG Narrow Range level is greater than 12%.

Throttles AFW to band provided by SRO.

ES-0.1, Attachment 5 NOTE: AFW to idle loop(s) (RCP secured), should be throttled to prevent depressurization of the SG and subsequent Header / Line SI. AFW flow between approximately 60 gpm and 100 gpm should be adequate to prevent a Header / Line SI.

BOP 3 When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50% by throttling AFW Isolation MOVs:

  • SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
  • SG B, 1-FW-MOV-151C and 1-FW-MOV-151D
  • SG C, 1-FW-MOV-151A and 1-FW-MOV-151B ES-0.1, Attachment 5 BOP 4. Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves:

Emergency Bus H deenergized: 1-FW-141 1-FW-156 1-FW-171 Emergency Bus J deenergized: 1-FW-140 1-FW-155 1-FW-170 Identifies Bus H and J not deenergized.

End EVENT #7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 56 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

Time Position Applicants Action or Behavior Team Identify Failure based on the following:

Alarms:

1B-F3, SFGDS AREA SUMP HI LEVEL 1C-B-8, PRZR LO PRESS 1C-D8, PRZR LO LEVEL 1D-E5, CHG PP TO REGEN HX HI-LO FLOW RMA-D6, VENT STACK #2PART ALERT/HI RMA-D7, VENT STACK #2 NORM RNG GAS ALERT/HI Indications:

Lowering PRZR Level Rising CH flow NOTE: SRO may direct manual safety injection and return to E-0 due to degrading plant conditions.

1-AP-16.00 SRO Direct RO to perform the Immediate Actions of 1-AP-16.00.

1-AP-16.00 RO NOTE:

  • RCS average temperature has a direct impact on pressurizer level.

[1] MAINTAIN PRZR LEVEL:

  • Isolate Letdown Closes 1-CH-LCV-1460 A / B
  • Control Charging flow Takes Manual control of 1-CH-FCV-1122 and raises CH Flow.

RO Reports that CH flow at maximum value and PZR level decreasing.

SRO Direct RO to Re-perform the Immediate Action Steps of E-0, and Safety Inject on Step 4.

1-E-0 RO [1] CHECK REACTOR TRIP:

1-E-0

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 57 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

RO [2] CHECK TURBINE TRIP:

1-E-0

[3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED 1-E-0 RO [4] CHECK IF SI INITIATED:

a) Check if SI is actuated:

  • LHSI pumps - RUNNING
  • A-F-3
  • A-F-4 b) Manually initiate SI Report SI has been initiated, SI flow to the core, 1-E-0 Immediate Actions with SI complete.

1-E-0 SRO Will Check off the Immediate Action Steps of 1-E-0.

SRO will conduct a commensurate Brief. Ensure the Team agrees that a LOCA outside of containment is in progress. Poll the Team as to any higher priority than continuing actions for a LOCA outside of containment.

SRO closes the brief.

Directs BOP to perform Attachments 1, 2, and 3 of 1-E-0. Attachment 1, 2, and 3 located in Event 9.

Continues with 1-E-0 with RO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 58 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 1-E-0 RO Identify RCS Subcooling < 30 °F and SI flow indicated to all three loops.

SRO Using 1-E-0 Continuous Actions Page:

1. RCP TRIP CRITERIA Trip all RCPs if BOTH conditions listed below occur:
a. Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS
b. RCS Subcooling - LESS THAN 30°F [85°F]

RO Checks RCP Trip Criteria exist.

SRO Directs RO to Trip all RCPs.

2. MINIFLOW RECIRC CRITERIA
a. CLOSED - When RCS pressure is less than 1275 psig [1475 psig] AND RCP Trip Criteria are met (RCPs OFF).

RO Identifies Criteria are met.

SRO Direct RO to close mini-flow recirc valves.

CT-2: Critical Task: E 1.2. Trip all RCPs within 5 minutes of reaching RCP Trip Criteria. (WOG E-1-C).

CT-2: Start Time: _________. CT-2: Stop Time: _________.

Note: Examiner will be notified by Simulator Operator when RCS Subcooling reaches 35°F and Lowering for CT-2 Monitoring.

SRO *6. CHECK RCS AVERAGE TEMPERATURE

  • STABLE AT 547°F OR
  • TRENDING TO 547°F

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 59 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

SRO 7. CHECK PRZR PORVs AND SPRAY VALVES:

a) PRZR PORVs - CLOSED b) PRZR spray controls

  • Demand at Zero (or)
  • Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN NOTE: Seal injection flow should be maintained to all RCPs.

SRO *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO Two or three Charging pumps will be running and flowing to the RCS.

b) RCS subcooling - LESS THAN 30°F [85°F]

RCS subcooling will be less than 30 °F c) Stop all RCPs d) RCS pressure - LESS THAN 1275 psig [1475 PSIG]

e) Close CHG pump miniflow recirc valves:

  • 1-CH-MOV-1275A
  • 1-CH-MOV-1275B
  • 1-CH-MOV-1275C Mini-flow recirc valves closed.

SRO 9. CHECK IF SGs ARE NOT FAULTED:

  • Check pressures in all SGs a) STABLE OR INCREASING AND b) GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 60 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

SRO 10. CHECK IF SG TUBES ARE NOT RUPTURED:

  • Condenser air ejector radiation - NORMAL
  • SG blowdown radiation - NORMAL
  • SG MS radiation - NORMAL
  • TD AFW pump exhaust radiation - NORMAL
  • SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER 11 CHECK RCS - INTACT INSIDE CTMT SRO
  • CTMT radiation - NORMAL
  • CTMT pressure - NORMAL

RO SRO 12 CHECK RCS - HAS BEEN MAINTAINED INTACT OUTSIDE CTMT a) Radiation Monitors - NORMAL

  • MGPI vent-vent
  • Auxiliary Building Control Area RO Reports MGPI Vent-Vent in Alarm b) Sump annunciators - NOT LIT
  • VSP-F-4
  • B-D-1
  • B-D-2
  • B-F-3 Step 12 RNO Determine cause of abnormal conditions.

IF the cause is a loss of RCS inventory outside CTMT, THEN GO TO 1-ECA-1.2, LOCA OUTSIDE CONTAINMENT.

RO Reports conditions caused by LOCA outside CTMT SRO Transitions to ECA-1.2.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 61 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 1-ECA-1.2 SRO Performs a commensurate brief. Ensures Team assessment confirms event in progress is a LOCA outside CTMT. Polls Team concerning any abnormal condition that needs to be addresses of a higher priority than isolating the LOCA outside CTMT. When any issues are addressed, SRO closes brief and continues with ECA-1.2.

1-ECA-1.2 CAUTION: Depending on break location, higher than normal dose levels should be expected in the Auxiliary Building and the Safeguards after a LOCA outside CTMT.

SRO 1 VERIFY PROPER VALVE ALIGNMENT:

a) Locally unlock and close the following breakers:

  • 1H1-2N 9A for 1-SI-MOV-1890C Directs the BOP to contact the Shift Manager/Desk SRO and have an operator briefed and dispatched to remove tags and close the breakers for 1-SI-MOV-1890 A / B / C.

NOTE: Booth will time compress this action when SM/Desk SRO contacted.

b) LHSI to hot legs - CLOSED

  • 1-SI-MOV-1890A
  • 1-SI-MOV-1890B When Valves Energized, the valves indicate closed.

c) SI accumulator test valves - CLOSED

  • HCV-SI-1850A
  • HCV-SI-1850B
  • HCV-SI-1850C
  • HCV-SI-1850D
  • HCV-SI-1850E
  • HCV-SI-1850F When Checked, Valves Indicate closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 62 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

1-ECA-1.2 NOTE: The SRO is expected to have a Focus Brief prior to this step. The SRO will bring the BOP into the discussion concerning the expected response of the RCS SRO when 1-SI-MOV-1890C is closed. If closure of this valves isolates the RCS break, RCS pressure and LHSI flow is expected to increase. If the break remains isolated, RCS pressure and LHSI flow will remain the same or decrease. The SRO will complete the brief and continue ECA-1.2.

2 TRY TO IDENTIFY AND ISOLATE BREAK:

a) Close LHSI to cold legs RO

  • 1-SI-MOV-1890C Team Shortly after closure of 1-SI-MOV-1890C, the Team should identify that RCS pressure and LHSI flow is increasing.

Critical Task:

CT-3: WOG ECA-1.2A, Isolate the LOCA outside containment before transition out of ECA-1.2, or cavitation of any LHSI pump. SPS- Isolate LOCA outside SRO containment before transition out of ECA-1.2 (PSA).

RO b) Check RCS pressure - INCREASING RO will identify RCS increasing.

c) Place LHSI pumps in PTL RO Places LHSI pumps in PTL.

SRO d) Close LHSI pump suctions from RWST

  • 1-SI-MOV-1862A
  • 1-SI-MOV-1862B Closes 1-SI-MOV-1862A / B.

e) GO TO 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT SRO Transitions to 1-E-1.

CRITICAL TASK STOP TIME ____________________

END EVENT 8 END of Scenario 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 63 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Time Position Applicants Action or Behavior ATTACHMENT 1 OF E-0 BOP 1. CHECK FW ISOLATION:

  • Feed pump discharge MOVs - CLOSED
  • 1-FW-MOV-150A
  • 1-FW-MOV-150B
  • MFW pumps - TRIPPED
  • Feed REG valves - CLOSED
  • SG FW bypass flow valves - DEMAND AT ZERO
  • SG blowdown TVs - CLOSED BOP 2. CHECK CTMT ISOLATION PHASE I:
  • Phase I TVs - CLOSED Identifies 1-CV-TV-150A, 1-CH-TV-1204A OPEN, Closes valves
  • 1-CH-MOV-1381 - CLOSED
  • 1-SV-TV-102A - CLOSED
  • PAM isolation valves - CLOSED
  • 1-DA-TV-103A
  • 1-DA-TV-103B BOP 3. CHECK AFW PUMPS RUNNING:

a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 64 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Attachment 1 of E-0 BOP 4. CHECK SI PUMPS RUNNING:

  • CHG pumps - RUNNING
  • LHSI pumps - RUNNING Manually Starts 1-SI-P-1A.

BOP 5. CHECK CHG PUMP AUXILIARIES:

  • CHG pump CC pump - RUNNING
  • CHG pump SW pump - RUNNING
6. CHECK INTAKE CANAL:

BOP

  • Level - GREATER THAN 24 FT
  • Level - BEING MAINTAINED BY CIRC WATER PUMPS
7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:

a) Check if ANY of the following annunciators - HAVE BEEN LIT

  • E-F-10 (High Steam Flow SI)
  • B-C-4 (Hi Hi CLS Train A)

BOP

  • B-C-5 (Hi Hi CLS Train B)

Identifies annunciators not lit and goes to step 8.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 65 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

BOP *8 CHECK IF CS REQUIRED:

a) CTMT pressure - HAS EXCEEDED 23 PSIA 8, a) RNO Do the following:

1) IF CTMT pressure has exceeded 17.7 psia, THEN check or align the following valves:

Identifies CTMT pressure remains at normal pressure

2) GO TO Step 10.

Attachment 1 of E-0 BOP *10. BLOCK LOW PRZR PRESS SI SIGNAL:

a) Check PRZR pressure - LESS THAN 2000 psig b) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c) Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.

BOP *11. BLOCK LOW TAVE SI SIGNAL:

Step may not be performed at this time (if Tave is greater than 543°F).

a) Check RCS Tave - LESS THAN 543°F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c) Verify Permissive Status light F LIT

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 66 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

NOTE:

  • CHG pumps should be run in the following order of priority: C, B, A.
  • Subsequent SI signals may be reset by re-performing Step 12.

BOP 12. CHECK SI FLOW:

a) HHSI to cold legs - FLOW INDICATED

  • 1-SI-FI-1961 (NQ)
  • 1-SI-FI-1962 (NQ)
  • 1-SI-FI-1963 (NQ)
  • 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c) Reset SI.

d) Stop one CHG pump and out in AUTO Attachment 1 of E-0 e) RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:

1) Verify reset or reset SI.
2) Stop one LHSI pump and put in AUTO.

BOP 13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]

BOP 14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.

BOP 15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next Page of this guide)

Depending on timing, this attachment may have already been completed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 67 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

BOP 16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2.

Unit 2 Operator will state that Unit 2 is at 100% power (if asked)

Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 68 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Time Position Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 BOP NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.

ATTACHMENT 2 of 1-E-0 BOP 1. Check opened or open CHG pump suction from RWST MOVs.

  • 1-CH-MOV-1115B
  • 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 BOP 2. Check closed or close CHG pump suction from VCT MOVs.
  • 1-CH-MOV-1115C
  • 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 BOP 3. Check running or start at least two CHG pumps. (listed in preferred order)
  • 1-CH-P-1C
  • 1-CH-P-1B
  • 1-CH-P-1A ATTACHMENT 2 of 1-E-0 BOP 4. Check opened or open HHSI to cold legs MOVs.
  • 1-SI-MOV-1867C
  • 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 BOP 5 Check closed or close CHG line isolation MOVs.
  • 1-CH-MOV-1289A
  • 1-CH-MOV-1289B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 69 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

ATTACHMENT 2 of 1-E-0 BOP 6. Check closed or close Letdown orifice isolation valves.

  • 1-CH-HCV-1200A
  • 1-CH-HCV-1200B
  • 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 BOP 7. Check opened or open LHSI suction from RWST MOVs.
  • 1-SI-MOV-1862A
  • 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 BOP 8. Check opened or open LHSI to cold legs MOVs.
  • 1-SI-MOV-1864A
  • 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 BOP 9. Check running or start at least one LHSI pump.
  • 1-SI-P-1A
  • 1-SI-P-1B ATTACHMENT 2 of 1-E-0 BOP 10. Check High Head SI flow to cold legs indicated.
  • 1-SI-FI-1961
  • 1-SI-FI-1962
  • 1-SI-FI-1963
  • 1-SI-FI-1943 or 1-SI-FI-1943A ATTACHMENT 2 of 1-E-0 BOP 11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.
  • Alternate SI to Cold legs
  • Hot leg injection End of Event 9 -. End of Scenario 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 70 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 71 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 72 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 73 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 74 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Unit 2 will prompt BOP: MCR Boundary DP is the same as DP indicated on Unit 2 Ventilation Panel.

Unit 2 will prompt BOP: Unit 2 remains operating at 100%

power.

Unit 2 will assume responsibility for the Attachment action from this point.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 75 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 76 of 98 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 77 of 98 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 78 of 98 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:

Recall IC -264 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.

Ensure the Delta T Selector Switch is in the Channel II Position.

Ensure PRZR Level Recorder on Channel II.

Open the monitor window and add the following points to it:

  • asp_ao_off
  • CC_579 set at 0.38 Enter the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Type (Auto or Manual)

RC4802 PRZR PRESS CONT 10 10 1 0 1 MAN XMTR FAILURE (445)

MS1305 SG B STM PRESSURE 10 0 3 0 1 MAN TRNSMTR MS-PT-485 FAILURE CH2101 VCT LEVEL 10 0 5 0 1 MAN TRANMITTER LT-1115 FAILS CC0302 CC PUMP 1-CC-P-1B 10 0 7 FALSE TRUE MAN OVERCURRENT TRIP CC0802 CC-P-1B BKR 15J10 0 0 7 FALSE TRUE MAN MECHANICALLY STUCK CLOSED RD1236 DROPPED RCCA, M-4, 10 0 9 FALSE TRUE MAN CONTROL BANK C RD17 ATWS, WITH MANUAL RX 0 0 11 FALSE TRUE MAN TRIP PB DEFEATED SI1502 SI COLD LEG HDR LEAK 10 0 13 0 40 MAN UPSTRM MOV-SI-890C SI1603 FAIL CHECK VALVES SI- 10 0 13 FALSE TRUE MAN 85 SI1606 FAIL CHECK VALVE SI- 10 0 13 FALSE TRUE MAN 243 LOOP C (LHSI)

SI2402 SI RELAY SI2A FAILS TO 0 0 30 FALSE TRUE MAN ACTUATE SI2405 SI RELAY SI5A FAILS TO 0 0 30 FALSE TRUE MAN ACTUATE CC1801 DISABLE CCP1A AUTO 0 0 30 FALSE TRUE MAN START Enter the following Remote Functions:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 79 of 98 SIMULATOR OPERATORS GUIDE Remotes Set Condition Trigger SW_15J9_RF 4KV Stub TRIP, 20 Sec TD 7 Bus BKR 15J9 Control Switch RCMOV595 RC-MOV- 100 to 30, 0 Ramp, 10 Sec TD 11 595 C Loop Cold Leg Isol SIMOV890A_BKR SI- CLOSED 21 MOV-1890A LHSI To HOT Legs SIMOV890B_BKR SI- CLOSED 22 MOV-1890B LHSI To HOT Legs SIMOV890C_BKR SI- CLOSED 23 MOV-1890C LHSI To Cold Legs RX_RTA_OPEN TRUE 16 RX_RTB_OPEN TRUE 17 AAC_SMS_MODE OFF OFF 30 AAC DG LOCAL MODE SWITCH POSITION EL12, SW_25J10_RF, Bkr PTL 30 25J10 Control Switch, 1-CC-P-1D TRIGGER TYPE DESCRIPTION 1 MAN Przr Press Cont Xmtr Failure (445) Fails High 3 MAN SG B Stm Pressure Trnsmtr MS-FT-485 FAILS High 5 MAN VCT Level Transmitter LT-1115 Fails High OVERCURRENT Trip 1-CC-P-1B, BREAKER Stuck Closed, 15J9 7 MAN Breaker Trips Open

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 80 of 98 SIMULATOR OPERATORS GUIDE TRIGGER TYPE DESCRIPTION 9 MAN Dropped RCCA, M-4, Control Bank C 11 MAN RC-MOV-595 C Loop Cold Leg Isol Disc Falls Into Flow Stream 11 MAN ATWS, WITH MANUAL RX TRIP PB DEFEATED SI Cold Leg HDR Leak Upstrm MOV-SI-890C, With Check Valves 13 MAN Stuck Open

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 81 of 98 SIMULATOR OPERATORS GUIDE Verify the following control room setup:

Place the simulator in RUN and verify normal 100% power operation indications.

Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:

Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).

Verify Ovation System operating.

Reset ICCMs.

Verify Component Switch Flags.

Verify Brass Caps properly placed.

Verify SG PORVs set for 1035 psig.

Verify Rod Control Group Step Counters indicate properly.

Verify Ovation CRT display.

Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)

Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:

AP-53.00 AP-1.00 AP-23.00 AP-16.00 E-0 ECA-1.2 1-OPT-RX-001 AP-1.00, Att 6 (3)

OP-CH-007 Reactivity Sheet OP-ZZ-002 Verify Reactivity Placard is current.

Verify ALL PINK MAGNETS are accounted for.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 82 of 98 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

Ask for and answer questions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 83 of 98 SIMULATOR OPERATORS GUIDE Conduct shift turnover:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

  • 1-CC-P-1D is tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training.

A BAST at 8.0 W/%.

PSA is Green.

When the team has accepted the shift, proceed to the Session Conduct Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 84 of 98 SIMULATOR OPERATORS GUIDE Session Conduct:

  • Ensure conditions in Simulator Set-up are established.
  • Ensure Trigger 30 is active prior to team entering the simulator.
  • Verify Exam Security has been established and ASP_AO_OFF = True.

EVENT 1 Deleted EVENT 2 1-RC-PT-1145 Fails High, 1-AP-31.00/0-AP-53.00 When cued by examiner, implement Trigger #1.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of 1-RC-PT-1445. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00/AP-31.00.
  • If contacted, acknowledge review of VPAP-2802 and EPIP SU6.1 review required.
  • If contacted, will take responsibility for writing the CR.

STA:

  • If contacted, will acknowledge the failure of 1-RC-PT-1445. The individual(s) contacted will also acknowledge (but not confirm/deny) any TS LCOs.
  • If asked, the STA will review VPAP-2802, TRM Section 3.3, and SU6.1 review complete and discussed with Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Field Operators:

No feedback required for this failure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 85 of 98 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge instrumentation failure and commence investigations.

Unit 2 Operator:

If Contacted, acknowledge the failure of 1-RC-PT-1445.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 86 of 98 SIMULATOR OPERATORS GUIDE EVENT 3 Steam Pressure Fails High, B SG. 0-AP-53.00.

When cued by examiner, implement Trigger #3.

Operations Supervisor/Management:

  • If contacted, will acknowledge that Failure of 1MS-PT-1485, Channel III, B SG, Steam Pressure. The individual(s) contacted will also acknowledge any TS LCOs.
  • If asked, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into AP-53.00.

STA:

  • If contacted, will acknowledge the Failure of 1MS-PT-1485, Channel III, B SG, Steam Pressure. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
  • When asked, STA reports the failed channel is a RG 1.97 variable.
  • When asked, SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
  • When contacted, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Field Operators:

No feedback required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 87 of 98 SIMULATOR OPERATORS GUIDE Maintenance/ Work Week Coordinator:

  • If contacted, will have I&C brief on placing the failed channel in trip.

Unit 2:

  • If contacted, will acknowledge Failure of 1-MS-PT-1485, Channel III, B SG, Steam Pressure.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 88 of 98 SIMULATOR OPERATORS GUIDE EVENT 4 Failure of VCT Level Channel LT-1115 High. 0-AP-53.00.

When Evaluator ready: Implement Trigger #5.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of 1-CH-LT-1115 high.

STA:

  • If contacted, will acknowledge the failure of 1-CH-LT-1115 high.
  • If asked, SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
  • After directed, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Maintenance/ Work Week Coordinator:

  • If contacted, will acknowledge the failure and commence investigations.

Field Operators: (Wait 4 minutes from time of direction to report).

  • If contacted, to check the status of 1-CH-LT-1115 locally, report no obvious abnormal condition with the transmitter.

Unit 2:

  • If contacted, will acknowledge the failure of 1-CVH-LT-1115 high.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 89 of 98 SIMULATOR OPERATORS GUIDE EVENT 5 Overcurrent trip 1-CC-P-1B with breaker stuck Shut, 15J9 trip open.

When cued by examiner, implement Trigger #7. If the Team decides to trip the reactor on this event, consult the examiner and actuate Trigger #11 when first Reactor Trip button pressed.

Operations Supervisor/Management:

  • If contacted, will acknowledge the fault on of 1-CC-P-1B, the failure of the breaker to open, and the trip of breaker 15J9. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into ARP.

Unit 2 Operator:

  • If asked: 1-CC-P-1C is running, and CC cross-ties are open.

STA:

  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will acknowledge any TS information.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
  • If asked, The STA will report that TRM review is complete and TRM requirements have been discussed with the Shift Manager.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 90 of 98 SIMULATOR OPERATORS GUIDE Field Operator:

  • When contacted, report that 15J10 breaker for 1-CC-P-1B has a timed overcurrent drop on A phase. 1-CC-P-1A breaker, 15H10, has no abnormalities.
  • When contacted, report that 15J9 breaker has a timed overcurrent drop on all three phases.
  • If contacted, report as Aux Bldg Operator that there are no abnormalities locally with 1-CC-P-1A and 1-CC-P-1B.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 91 of 98 SIMULATOR OPERATORS GUIDE EVENT 6 Dropped Rod C Bank Group 1. 1-AP-1.00, 0-AP-23.00.

When Examiner ready, Actuate Trigger #9.

Operations Supervisor/Management:

  • If contacted, will acknowledge the dropped rod and the need to ramp at 1%/minute to 70 - 74%

power.

  • If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC, the Shift Manager will direct a 1%/minute ramp rate.
  • If contacted, will take responsibility for writing the WR and CR.

STA:

  • If asked, the STA will perform a QPTR. See AP-1.00, Attachment 6, attached.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
  • If asked, the STA will acknowledge the need to borate and use rods (will acknowledge the team review of pre-planned reactivity plans and OP-RX-010, if performed). If asked to perform the OP-RX-010 review, the STA will state that he is not able to at this time.
  • When contacted, SRO directs STA to review VPAP-2802. The STA reports that review is complete and has been discussed with the Shift Manager.

Unit Two:

  • If contacted, all conditions on U2 are normal.

Field Operators:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 92 of 98 SIMULATOR OPERATORS GUIDE

  • If contacted, Will perform actions as directed (i.e., may be asked to read bank overlap counter-RD 2).

I&C:

  • If requested by MCR to reset the bank overlap - use RD2 drawing to set as requested.

Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge the failure and commence investigations.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 93 of 98 SIMULATOR OPERATORS GUIDE EVENT 7 RC Loop C disc falls, Valid First-Out, FR-S.1 When Evaluator has seen a sufficient change in power, Actuate Trigger #11.

Operations Supervisor/Management:

  • If contacted, will acknowledge the reactor trip failure and entry into FR-S.1, E-0, and ES-0.1.
  • If contacted, will acknowledge direction for local opening of reactor trip breakers. After two (2) minutes, use Trigger 16 (A RT breaker) and Trigger 17 (B RT breaker).
  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, SRO requests that tags be cleared and breakers closed for 1-SI-MOV-1890A / B /

C, use Triggers 21, 22, and 23 to perform close the breakers for the MOVs.

Field Operators:

  • If directed, field operators will acknowledge direction for local opening of reactor trip breakers.

After two (2) minutes, use Trigger 16 (A RT breaker) and Trigger 17 (B RT breaker).

  • If contacted, SRO requests that tags be cleared and breakers closed for 1-SI-MOV-1890A / B /

C, use Triggers 21, 22, and 23 to perform close the breakers for the MOVs.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 94 of 98 SIMULATOR OPERATORS GUIDE EVENT 8 LOCA Outside Containment Upstream 1-SI-MOV-1890C.

When Evaluator is ready, implement Trigger # 13.

When RCS Subcooling reaches 35°F and lowering, notify the Lead Examiner, for monitoring CT-2.

1-SI-MOV-1890A / B/ C can be energized when directed using Triggers 21, 22, and 23. 2 minutes to transit to valve, when directed; wait 1 minute between Triggers to energize MOV.

Operations Supervisor/Management:

  • If contacted, will acknowledge the reactor trip failure, completion of FR-S.1, completion of E-0 Immediate Actions, and transition to ES-0.1.
  • If contacted, will take responsibility for writing the WR and CR.

Unit 2 Operator:

  • If directed to respond to radiation alarms on the radiation alarm panel, silence the alarms when and report the alarm to the Unit 1 SRO.
  • When FP alarms occur, acknowledge alarms.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
  • When contacted by BOP, Chilled Water has been throttled IAW the Caution prior to Step 10 of Attachment 3. MCR boundary D/P indicates the same value as Unit 2 ventilation panel D/P gauges. Unit 2 will assume responsibility for Attachment 3 when last page is reached (SFP monitoring).
  • When directed, to read Unit 1 A/E, Blowdown, Main Steam and TDAFW radiation, report as pre-event, no trend.

Field Operators: Perform with a two minute delay to transit to the valve breaker; 1 minute between Triggers to energize MOVs.

  • If directed, field operators will remove tags and close breakers for 1-SI-MOV-1890A / B / C.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 95 of 98 SIMULATOR OPERATORS GUIDE Role play as other individuals as needed.

EVENT 9 BOP Failures.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
  • When directed, to read Unit 1 A/E, Blowdown, Main Steam and TDAFW radiation, report as pre-event, no trend.

Field Operators: Role play as necessary to support the Teams actions.

The scenario will end upon entering 1-E-1 or at the lead examiners discretion

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Facility: Surry Power Station Scenario No.: 1 Op-Test No.: 2014-001 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Unit 1 and 2 at 100% power; MOL.

  • A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Turnover: The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Event Malf. Event Event No. No. Type* Description 1 RCMOV_5 N BOP Test Cycle Pressurizer PORV, Block Valve breaker will trip when re-35_BKR, N SRO opened Open TS SRO 2 RC4903, I RO PRZR Level Transmitter Fails Low, requiring IAs of AP-53.00 to control

-.2 DEG CH flow.

TS SRO 3 FW1803, I BOP Feed Flow Channel fails high requiring manual FRV control, IAs of AP-

+1 DEG 53.00 TS SRO 4 SD0201 C BOP Loss of High Pressure Drain, AP-18.00 5 R RO R SRO Ramp to 75% power IAW AP-23.00 N - BOP C RO 6 RC2402 C SRO Steam Generator Tube Leak B SG at approximately 74 gpm. AP-16.00, E0.

Auto Actions of Air Ejector Hi Rad do not function, BOP manually aligns.

AS02, C - BOP A/E RM Annunciator Response Procedure.

AS05 RC5601 Reactor Coolant Pumps trip on electrical power swap to Reserve Station RC5602 Service Transformers (30 seconds after reactor trip).

RC5603 7 RC2402, M - All SGTL B SG escalates to Design Basis rate (800 gpm) in ES-0.1. AP-79%, 710 16.00, Manual SI, E-0, E-3.

gpm, 60 sec ramp 8 PCV455C M - All PZR PORV 1-RC-1455C will not open when switch placed in open - Go

_OPEN, to ECA-3.3 OFF

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 9 SI2409 C BOP BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-SI2505 100A/B not close.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Event 1: PT-18.6 I, PZR Block Valve Stroke Test. (N- BOP/SRO)

The Team will pre-brief this evolution prior to entering the Simulator. Upon entry of the Team to the Simulator, the Scenario brief will be given, Questions answered, and the Team allowed ~ 5 minutes to become acclimated to the Simulator Environment.

When the BOP closes 1-RC-MOV-1535, 1-RC-PCV-1456 block valve, and attempts to re-open 1-RC-MOV-1535, a series of triggers actuate to trip the power supply breaker to 1-RC-MOV 1535.

Verifiable Action(s):

1) BOP will close 1-RC-MOV-1535 and time the stroke.
2) RO/BOP will place the 1-RC-MOV-1456 PORV control switch in the close position following Tech Spec review.

Technical Specifications:

The SRO will review Tech Specs (3.1.A.6.d) and determine a one (1) hour clock exists to place 1-RC-PCV-1456 in manual (switch to close); and a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to return the block valve to an OPERABLE status, or be in HSD in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and RCS temperature <350°F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

This Event sets up entry into ECA-3.3, SGTR without Pressure Control; Major Event later in the Scenario.

Event 2: PRZR level Upper Channel Fails Low (-.2 DEG) PRZR level on selected Upper Channel fails to ~34%. (I - RO, TS - SRO). ARP 1C-D8, PRZR LO Level.

The RO will diagnose the failure based on CH to Regen HX Hi/Low flow alarm (Annunciator 1D-E5) or identification of CH flow increasing and PZR level Channel III decreasing.

Verifiable Actions(s):

1) The RO will place CH flow in Manual and control PRZR level at setpoint IAW AP-53.00, Loss of Vital Instrumentation/Controls.
2) BOP will select an operable channel on the pressurizer level recorder.
3) The RO will defeat the failed channel IAW AP-53.00, and return CH flow to automatic when normal PRZR level restored.

Technical Specifications:

1) The SRO will Review Tech Specs and determine a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to place the Failed Channel in trip (TS 3.7, Table 3.7-1, item 9 (Pressurizer High Water Level), Operator Action 7. With the number of OPERABLE Channels less than the Total number of channels; place the failed channel in trip in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, allowable to bypass the channel for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance, if requirements not met reduce power to less than P-7 (10%) within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1

2) TS-Table 3.7-6, item 14, Pressurizer Level, 2 Channels required, condition met.

(Referred by check of CEP 99-0029, RG 1.97).

TRM Actions:

1) TRM section 3.3.2, Table 3.3.2-1, Pressurizer Level Channel 1-RC-LI-1461.

Condition A applies, Implement a Fire Watch in cable vault and tunnel and the emergency switchgear room of the affected Unit (Unit 1) IAW TRM Section 5.2 (Hourly) within 14 days and restore the failed channel in 60 days. (Usually an STA Function to identify, may be performed as a follow-up).

Reg. Guide 1.97:

1) CEP-99-0029, Reg. Guide 1.97 Operability/Functionality, Reportability and Alternate Indications, Attachment 1, Post Accident Monitoring Equipment, A-13 variable, 2 channels required, Condition is met. Refers to TS Table 3.7-6. (Usually an STA Function to identify - could be covered as a follow-up).

Event 3: Feed Flow Channel III, B SG fails high. (I - BOP, TS - SRO)

BOP will diagnose the failure based upon alarms and indications received and take the Immediate Actions of AP-53.00. The Team will implement AP-53.00, Loss of Vital Instrumentation/Controls and shift SGWLC input to Channel IV for B SG. The BOP will restore B SG NR level to program.

Verifiable Action(s):

1) BOP will place the B FRV in manual and regain control of B SG NR level.
2) RO will defeat the failed channel.
3) BOP will return the B FRV to automatic.

Technical Specifications:

Tech Spec Table 3.7-1

1) Item 17, Low steam generator water level with steam flow/feedwater flow mismatch, Operator Action 6.
2) With the number of OPERABLE Channels less than the TOTAL number of channels, operation may continue if the failed channel is placed in trip in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the channel may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance, if conditions not satisfied in the time permitted, be in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Technical Requirements Manual. Reg. Guide 1.97:

1) The TRM Section 3.3, Appendix R Instrumentation unaffected; and RG 1.97 requires one channel of Feed Flow indication per steam generator and no further actions are required are by this failure.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Event #4: Loss of the HP Heater Drain Pump (1-SD-P-1A) (C - BOP)

The BOP will diagnose the failure based upon alarms and indication received. The Team will initiate AP-18.00, Loss of HP Heater Drain Pump/ Network 90 failure Verifiable Actions:

1) The BOP will place the tripped High Pressure Drain pump control switch in PTL.
2) Reduce Turbine Load as necessary to maintain reactor power less than 100% using the valve position limiter or using Turbine Manual (approximately 50 MW reduction required).

Event 5: Power Reduction to less than 75% power using AP-23.00, Rapid Load Reduction. (R - RO, R - SRO, N - BOP)

The SRO will lead a Team Brief where the reactivity plan will be discussed to reduce reactor power to less than 75% power in order to restore the Polishing Building to service. The RO and SRO will be credited with a Reactivity Manipulation and the BOP with a Normal Evolution.

Verifiable Action(s):

1) RO will manipulate control rods to control delta flux and/or Tave.
2) RO will manipulate CVCS controls to Emergency Borate.
3) RO will manipulate CVCS control to establish a normal boration to assist in Tave control.
4) BOP will manipulate Turbine Controls to establish power reduction.

Event #6: Steam Generator Tube Leak B Steam Generator. Failure of Auto actions of A/E RM. Trip of all RCPs on electrical transfer to RSSTs. (C - RO, C - BOP)

When the Evaluation Team is satisfied with the Reactivity manipulation, the event will be triggered. A SGTL of approximately 74 gpm will initiate requiring the RO to perform the actions of 1-AP-16.00 to quantify the leakrate. The A/E RM will go into High alarm due to the primary to secondary leakage; the BOP will manually align A/E discharge to containment IAW A/E RM ARP. When the RCS leakrate is identified as greater than 50 gpm, the RO will trip the reactor and perform the Immediate Actions of 1-E-0.

Verifiable Actions:

1) RO will isolate LD flow and place charging flow in manual to quantify leakrate.
2) BOP will respond to failure of auto actions on A.E RM High alarm by swapping A/E discharge to containment.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Event #7: SGTR in B SG, approximately 710 gpm. (M - ALL)

When the evaluation Team is ready, a SGTR in the B SG will be implemented. The RO will re-assess RCS leakage in response to alarms and indications received. The RO will determine that RCS leakage exceeds the capacity of a single CH pump, and the Team will return to E-0 and manually initiate SI.

The SRO will perform a commensurate brief and continue with E-0. While the RO and SRO continue with E-0, the BOP will be directed to perform E-0 Attachments 1 through 3.

Verifiable Actions:

1) RO will increase CH flow in manual per Immediate Action Steps of 1-AP-16.00, Excessive RCS Leakage to determine if RCS leakage is greater than the capacity of a single CH pump.
2) RO re-perform High Level Steps of E-0, and manually Safety Inject on Step 4 of 1-E-0.
3) BOP will perform actions of Attachments 1 through 3 of E-0. BOP Failures in E-0 Attachments: 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not auto close, 1-VS-MOD-103A not auto close, 1-MS-TV-109 and 1-DA-TV-100A/B will not auto close (Listed as Event 9).

Critical Task:

1) SPS E G: LHSI pumps will not undergo significant degradation while operating under very low flow conditions during the onset of a SBLOCA (implicit in SBLOCA analysis). Operators will secure one LHSI pump as directed by Emergency Operating Procedures to prevent pump damage while on recirculation. Secure one LHSI pump within 30 minutes of initiation of SI (KOA). NOTE: If the BOP Fails to Start 1-SI-P-1B, Critical Task becomes Not Applicable.
2) WOG E-3 -- A: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs. Example: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs (KOA).

KOA: For the design basis tube rupture, isolate the ruptured SG from the atmosphere/Turbine building within 30 minutes. Note: The 30 minute criteria in the CT is ONLY for the design basis tube rupture.

Event #8: SGTR with Loss of Pressure control. (M - All)

The Team continues through the EOP progression E-0 to E-3.

After the Team has completed the rapid cooldown of E-3 and moves to the Depressurization steps, the Team will be presented with the inability to depressurize the RCS (No RCPs - No Spray available), 1 PZR PORV inoperable, and the last Pzr PORV not responding to placing the control switch in Open. This will require the Team to Transition to ECA-3.3, SGTR without Pressure Control.

When ECA-3.3 is entered, it is expected that the ruptured SG level will be > 73% NR leading to Team moving to Step 6, Check If SI Can Be Terminated.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Verifiable Actions:

1) RO will isolate AFW flow to the Ruptured SG.
2) BOP will reset SI and secure A CH pump and one of the running LHSI pumps.

(Discretionary CT - within 30 minutes).

3) RO will manipulate steam dump controls for rapid cooldown.
4) RO/BOP will block SI signals when conditions established.
5) RO will manipulate SI/CVCS control to terminate SI, establish CH flow, and restore letdown flow.

Classification:

Follow-up Classification question for SGTR: Alert FA-1.1.

The Scenario is terminated at Lead Evaluator discretion or at Step 11 of ECA-3.3, Check If CS Should Be Stopped (CH and LD flow have been re-established).

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 Initial Conditions: Unit 1 and 2 Operating at 100%.

Turnover: The Team will pre-brief conduct of PT-18.6I, PZR Block Valve Stroke Test Pre-load malfunctions: (Trigger 30s) o SI2409 SI RELAY CI1A FAILS TO ACTUATE o SI2505 SI RELAY SI5B FAILS TO ACTUATE o AS02 DISABLE SV-TV-102 OPEN o AS05 DISABLE SV-TV-103 CLOSE o AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

o AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

Turnover:

Unit 1 and 2 at 100% power; MOL.

A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon dilutions followed by a manual makeup for training.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Turnover: Team will perform PT-18.6I, PZR Block Valve Stroke Test. The performance of this procedure has been analyzed based on the current plant configurations and the PRA indicates green.

Event Malf. #s Severity Instructor Notes and Required Feedback 1 RCMOV_53 Open Test Cycle Pressurizer PORV, Block Valve breaker will trip when re-opened.

5_BKR, 2 RC4903, -.2 DEG PRZR Level Transmitter Fails Low, requiring IAs of AP-53.00 to control CH flow. 0-AP-53.00.

3 FW1803, +1 DEG Feed Flow Channel fails high requiring manual FRV control, IAs of AP-53.00 4 SD0201 True Loss of High Pressure Drain, AP-18.00 5 N/A N/A Ramp to 75% power IAW AP-23.00

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #1 6 RC2402 8% Steam Generator Tube Leak B SG at approximately 74 gpm. AP-16.00, E0.

AS02, Auto Actions of Air Ejector Rad Mon on High alarm do not function, BOP manually AS05 aligns. A/E RM Annunciator Response Procedure.

RC5601 RC5602 Reactor Coolant Pumps trip on electrical power swap to Reserve Station Service RC5603 TRUE Transformers (30 seconds after reactor trip).

7. RC2402 88%, 60 SGTL B SG escalates to Design Basis rate (710 gpm) in AP-24.01. AP-16.00, sec ramp Manual SI, E-0, E-3.

Failure of Auto Air Ejector to re-align on A/E RM High Alarm.

AS02/03 8 PCV455C OFF PZR PORV 1-RC-1455C will not open when switch placed in open - Go to ECA-

_OPEN, 3.3 PCV455C ON

_CLOSE 9 SI409 TRUE BOP Failures in E-0 Attachments; 1-SI-P-1B not start, 1-CH-HCV-1200 A/B not close, VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.

SI2505 Scenario Objectives:

A. Given a failure of 1-RC-MOV-1535 to re-open during performance of 1-PT-18.6I, PZR Block Valve Stroke Test, Implement the Applicable Tech Spec LCO.

B. Given a pressurizer level channel deviation, respond IAW 0-AP-53.00 to the failure.

C. Given a High Failure of SG Feed Flow Channel II on B SG, take action IAW 0-AP-53.00 to control SG level, and apply the applicable Tech Spec LCOs for the failure.

D. Given a trip of the running High Pressure Drain pump, ramp the Unit 1 <75% IAW 1-AP-18.00 and 0-AP-23.00.

E. Given a SG Tube Leak, respond IAW 1-AP-16.00 to quantify the leak rate, trip Unit 1, and perform the Immediate Action Steps of 1-E-0, Reactor Trip or Safety Injection.

F. Given a Design Basis SG Tube Rupture, respond IAW 1-E-0, and 1-E-3, Steam Generator Tube Rupture.

G. Given the Failure of 1-RC-PCV-1445C to open to depressurize the RCS, transition to 1-ECA-3.3, Steam Generator Tube Rupture without Pressurizer Pressure Control.

H. Given SI relay failures, manually align components IAW E-0, Attachment 1, 2, and 3.

SHIFT TURNOVER INFORMATION OPERATING PLAN:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance. Expected to be returned to services in 3 days. Per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training. A BAST concentration is 8.0 w/%.

Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, PZR Block Valve Stroke Test. Performance of this procedure has been authorized and has been PSA analyzed for current plant conditions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 1 Page 10 of 92 Event

Description:

Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.

Cue: By Examiner.

Note: An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.

The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.

A facility representative will be present for consultation with the Evaluation Team, as needed.

Time Position Applicants Action or Behavior 1-PT-18.6I SRO/BOP NOTE - Team will pre-brief this evolution prior to entering the simulator. Initial Conditions and Precautions and Limitations will be completed before entering the simulator.

BOP Verify closed or close PRZR PORV 1-RC-PCV-1456.

Verify key switch for PRZR PORV 1-RC-PCV-1456 OVPRESS BOP Mitigating System is in DISABLE.

Verify PRZR PORV Block Valve 1-RC-MOV-1535 is open.

BOP Stroke PRZR PORV Block Valve 1-RC-MOV-1535 through one complete cycle, timing valve movement in each direction. Time from signal initiation to complete valve travel.

BOP Valve closes and fails to reopen.

SRO Refer to Technical Specification 3.1.A.6 for required action

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 1 Page 11 of 92 Event

Description:

Test Cycle Pressurizer Block Valves, Block Valve Trips on re-open, PT-18.6I.

Cue: By Examiner.

SRO Refer to Technical Specification 3.1.A.6 for required actions.

With one block valve inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve to operable status or place the associated PORV in manual. In addition, restore the block valve to operable status in the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or, be in at least HSD within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature to < 350°F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

BOP Places 1-RC-PCV-1456 in CLOSE.

SRO Start 72 Hour Clock to repair Block Valve.

SRO Direct RO/BOP to notify Service Building Operator to check status of 1H1-2S 6A breaker for 1-RC-MOV-1535.

RO/BOP Contact Service Building Operator to check status of 1-RC-MOV-1535 Breaker.

RO/BOP When notified by field operator that 1H1-2S 6A. Breaker is tripped, report information to the Team using a Focus Brief.

SRO Notify Shift Manager of Block Valve failure and suspension of PT performance.

Request Electrical Maintenance support to investigate breaker trip.

SRO Exit 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> clock to place 1-RC-PCV-1456 in manual.

SRO Perform brief to update Team on Technical Specification requirements. Brief driven by brief card and placards.

END of Event #1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 2 Page 12 of 92 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior RO Diagnoses failure of 1-RC-LI-1461 with the following indications/alarms:

Alarms:

  • CH Flow rises on 1-CH-FI-1122A to ~109 gpm
  • PRZR Level on 1-RC-LI-1461 lowers to 34%

In accordance with the immediate actions of AP-53.00 the RO will take manual control of pressurizer level control by placing 1-CH-FV-1122 in manual and lowering charging flow to maintain program level (per AP-53.00).

SRO Enters 0-AP-53.00, Loss of Vital Instrumentation / Controls.

RO [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL Checks 1-RC-LI-1459, Pressurizer Level Channel 1, and 1-RC-LI-1460, Pressurizer Level Channel 2 are NORMAL.

RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-CH-FV-1122 in manual and raises charging flow.

SRO Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.

SRO will provide a band for control of PRZR level with CH flow in MANUAL.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Step 3, AP-53.00 RO VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO will identify that reactor power is less than 100% using PCS Display of Core Thermal Power.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 2 Page 13 of 92 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

  • PRZR Level Control, Step 11.

RO The RO will identify that 1-RC-LI-1461 has failed.

Step 11, AP-53.00 SRO 11. CHECK PRZR LEVEL CONTROL CHANNELS - NORMAL RO Responds NO, 1-RC-LI-1461 Abnormal.

SRO 11 a) RNO 1) Place either of the following in MANUAL:

  • 1-CH-FC-1122C, CHG FLOW CNTRL, OR
  • 1-CH-LC-1459G, PRZR LEVEL CNTRL RO Responds 1-CH-FC-1122 in MANUAL SRO 11 a) RNO 2) Control PRZR Level at Program Level.

RO Responds Maintain PRZR Level at program +/- band set by SRO SRO 11 a) RNO 3) Move PRZR Level - CH SEL switch to Defeat the failed channel.

RO/BOP Transfers CH SEL switch to 1 / 2 Position.

SRO 11 a) RNO 4) Check or place recorder 1-RC-LR-1459 on an operable channel.

BOP Checks or adjusts PRZR Level Recorder to 1-RC-LI-1459 or 1-RC-LI-1460.

SRO 11a) RNO 5) Refer to Tech Spec 3.7-1, Item 9 and Table 3.7-6, Item 13.

TS 3.7, Table 3.7-1, item 9; Operator Action 7. Number of Operable channels one less than Total number of channels: Place Inoperable channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, allowed to bypass channel for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance, If conditions not met within allowed time, reduce power to less than P-7 in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

TS Table 3.7-6m Item 13: Required Number of channels to meet function = 2.

11 a) RNO 6) Refer to Attachment 3.

SRO hands Attachment 3, Pressurizer Level Control diagram to RO/BOP for SRO review.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 2 Page 14 of 92 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

Step 11, AP-53.00, Continued:

SRO Step 11 b) Check Pressurizer Heaters - Energized.

RO Checks Required Pressurizer Heaters energized, and reports that Pressurizer heaters are energized.

SRO Step 11 c) Check Letdown - IN SERVICE.

RO Reports Letdown in service.

SRO Step 11 d) Check PRZR level control - IN AUTOMATIC.

RO Reports pressurizer level control in MANUAL.

SRO Step 11 d) RNO When pressurizer level restored to program level, un-saturate 1-CH-LC-1459G, PRZR LEVEL CNTRL. Place 1-CH-FCV-1122 in automatic.

RO Acknowledges direction and notifies SRO when pressurizer level returned to AUTOMATIC.

Step 13, AP-53.00 SRO SRO recalls NOTE 2 Prior to Step 4 and goes to Step 13 of AP-53.00.

SRO Step 13 Check Calorimetric - Functional IAW 1-OPT-RX-001, Attachment 4.

RO/BOP Checks Calorimetric unaffected by this failure, and reports to the SRO.

Step 14, AP-53.00 SRO CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-RC-LI-1461 is a Reg. Guide 1.97 component.

STEP 15, AP-53.00 SRO REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that the Reg. Guide 1.97 Review is complete and has been reviewed with the Shift Manager.

[CEP 99-0029 requires two channels of pressurizer level indication and refers to TS Table 3.7-6.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 2 Page 15 of 92 Event

Description:

PRZR Level Transmitter Fails Low, 0-AP-53.00.

Cue: By Examiner.

STEP 16, AP-53.00 SRO Review the following:

  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO determines that TS Table 3.7.1, Item 9 is applicable (72-hours to place the channel in trip). SRO determines that 3.1.A.5 is not applicable since pressurizer heaters did not de-energize and that Table 3.7-6 item 1 is Not Applicable.

SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

[TRM Section 3.3, Condition A, requires a Fire Watch be established in the Cable Vault and Tunnel and Emergency Switchgear Room of the affected Unit within 14 days, and restore the instrument to Functional status in 60 days. Hourly Fire Watch Requirement established in TRM Section 5.2. NO VPAP-2802 requirement for this failure.]

Step 17, AP-53.00 SRO CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS The team will identify that no new additional failures exist (i.e., all failures have already been addressed), proceed to the RNO section, and this will direct the team to Step 19.

Step 19, AP-53.00 SRO PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC
  • I&C END EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 16 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior BOP Diagnoses failure FT-1487 with the following indications/alarms:

Alarms:

Indications:

  • Step increase in 1B SG Feed Flow indication CH-3
  • decrease in 1B SG Feed Flow indication CH-4
  • decreasing level on B SG.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS Step 1, AP-53.00 BOP [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies Channel IV indication for feed flow is NORMAL.

Step 2, AP-53.00 BOP [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and increases demand (FF >

SF) to restore level to program using Channel IV indication.

SRO Conduct a Brief using the Briefing Placard and obtains Critical Parameter information from the RO and BOP. The SRO will update the Shift Manager during AP-progression.

SRO will provide a band for control of B SG level with B FRV in MANUAL.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 17 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

Step 3, AP-53.00 SRO

  • VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Checks Reactor Power < 100% using PCS Calorimetric. Due to restoration of FF on 1B SG, power increase may be noted. As required, the SRO may direct the BOP to reduce turbine load to prevent exceeding 100% Calorimetric power.

Note: 0-AP-53.00, Attachment 7 Actions are contained at the end of this section starting on page 20.

Step 4, AP-53.00, Notes SRO NOTE: When the affected instrument/controller malfunction has been addressed by this procedure, recovery actions may continue at Step 13.

Step 4, AP-53.00 SRO DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

RO/BOP Identifies 1B SG Feed Flow affected.

SRO Goes to Step 7.

Step 7, AP-53.00 SRO CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.

SRO CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS - NORMAL

  • Steam Pressure
  • Steam Flow
  • Feed Flow

Step 7. RNO, AP-53.00 IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level Control system has failed, THEN do the following:

BOP a) Place the associated Feed Reg Valve in MANUAL.

BOP Verifies B SG MFRV controller, 1-FW-FCV-1488, in manual BOP b) Control SG level at program level (44%, a band will be given).

BOP Verifies B SG NR level is returning to program level.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 18 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

RO c) Select the redundant channel for affected SG(s)

RO Selects Channel IV Feed Flow for B SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV)

BOP d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.

BOP Places B SG FRV controller, 1-FW-FCV-1488, in automatic control.

Step 6, RNO, AP-53.00 (Continued)

SRO Perform follow-up actions:

a) Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.

If asked the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.

b) Refer to the following Tech Spec 3.7 items:

SRO

  • Table 3.7-1, 12 and 17
  • Table 3.7-2, 1.c, 1.e, and 3.a
  • Table 3.7-3, 2.a, and 3.a
  • Table 3.7-6, 15 and 16 Determines Table 3.7-1 item 17, is applicable (place channel in trip w/in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).

SRO c) Refer to Attachment 1.

d) IF no other instrumentation failure exists, THEN GO TO Step 13.

Step 13, AP-53.00 SRO 13. Review OPT-RX-001, Rx Power Calorimetric using PCS computer program, Attachment 4, to determine operability of calorimetric and need to perform OPT-RX-007, Shift Average Power Calculation.

RO Determines that OPT-RX-001 is NOT impacted and OPT-RX-007 will NOT need to be performed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 19 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

Step 13, RNO, AP-53.00 SRO a) Initiate ( )-OPT-RX-007, SHIFT AVERAGE POWER CALCULATION, as necessary.

Note: The Team will determine that the Calorimetric Program is functional based on a recent change to 1-OPT-RX-001, Calorimetric, Attachment 4.

Step 14, AP-53.00 SRO 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 14 if not Reg. Guide 1.97)

SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-FW-FT-1487 is a Reg. Guide 1.97 component.

Step 15, AP-53.00 SRO 15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 requirements have been reviewed with the Shift Manager.

[Reg. Guide 1.97 requires one channel of Feed Flow indication per steam generator and no further actions are required.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 20 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

SRO 16 REVIEW THE FOLLOWING:

  • VPAP-2802, NOTIFICATIONS AND REPORTS

STA The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

[VPAP-2802 - no requirement associated with the failure, No TRM requirements for this failure].

SRO 17. CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS Goes to Step 19 SRO 19. PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC
  • I&C END OF EVENT 3 0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 1 IF a rise in Reactor Power is caused by secondary transient, THEN GO TO Step 2.

IF a rise in Reactor Power is caused by primary transient, THEN GO TO Step 6.

NOTE: During secondary transient conditions, the most reliable indications of Reactor Power are Core T and Power Range NI. These indications should be used as the basis for Reactor Power until stable conditions have been reestablished.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 21 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 2 Mitigate a rise in Reactor Power caused by secondary transients by lowering steam demand or Turbine load as follows:

a) Reduce the Turbine Setter by an appropriate amount.

b) Place the Load Rate Selector thumbwheel to 1% / min.

c) Depress the GO pushbutton.

3 IF Turbine load can NOT be reduced using Operator Auto, THEN lower Turbine load using the Valve Position Limiter.

4 IF Turbine load still can NOT be reduced, THEN do the following.

a) Push the Turbine Manual pushbutton.

b) Check Turbine controls in Manual.

c) Depress the GV down pushbutton to reduce GV position.

NOTE: The CALCALC 10 minute Average Power will lag actual Reactor Power following a transient, and may continue to rise even after core thermal power has been reduced to less than 100%.

5 Check Reactor Power reduced to less than 100%.

  • Power Range NI power.
  • Core T power
  • CALCALC Instantaneous power (if reliable)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 3 Page 22 of 92 Event description: Feed Flow Channel Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00, Attachment 7 Actions, Prompt Actions to Reduce Reactor Power 6 Mitigate a rise in Reactor Power caused by primary transients as follows. Enter N/A for Steps 6 through 9 if NOT applicable.

a) Place the Rod Control Selector switch in Manual.

b) Insert control rods.

NOTE: The CALCALC 10 minute Average Power will lag actual Reactor Power following a transient, and may continue to raise even after core thermal power has been reduced to less than 100%.

7 Check Reactor Power reduces to less than 100%.

  • Power Range NI power.
  • Core T power
  • CALCALC Instantaneous power (if reliable) 8 IF necessary, THEN initiate a normal boration to control Flux.
9. WHEN Tave and Tref are within 1°F, THEN place control rods in Auto.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 4 Page 23 of 92 Event

Description:

Loss of High Pressure Drain Pump, 1-AP-18.00.

Cue: By Evaluator BOP Diagnose the trip of the High Pressure Drain Pump, 1-SD-P-1A based on the following indications:

  • 1H-G5/6/7 SG 1A/1B/1C LVL ERROR Step 1, AP-18.00 SRO Enter 1-AP-18.00 CHECK HP HEATER DRAIN PUMP STATUS:

SRO a) Check HP Heater Drain Pump - TRIPPED OR NOT PROVIDING SUFFICIENT FLOW BOP Reports that 1-SD-P-1, HP Heater Drain pumps tripped.

SRO b) Place pump control Switch in PTL BOP Places 1-SD-P-1A control switch in PTL Step 2, 1-AP-18.00 SRO CHECK REACTOR POWER - GREATER THAN OR EQUAL TO 75%

RO/BOP Reports reactor power at 100%

Step 3, AP-18.00 SRO START THIRD CONDENSATE PUMP AS REQUIRED BY PLANT CONDITIONS BOP Starts 1-CN-P-1A and verifies Proper Operation.

Step 4, AP-18.00 SRO NOTE: With unit at 100% power, Turbine load should be decreased approximately 50 MW.

REDUCE TURBINE LOAD AS NECESSARY TO MAINTAIN LOOP Ts -

LESS THAN 100%

  • Use Valve Position Limiter OR
  • Reduce Turbine load using Turbine Manual BOP Using Guidance of NOTE preceding the Step, Turbine load will be reduced.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 4 Page 24 of 92 Event

Description:

Loss of High Pressure Drain Pump, 1-AP-18.00.

Cue: By Evaluator Step 5, 1-AP-18.00 SRO NOTE: Ramping to 75% allows the Condensate Polishing Building to be placed fully in service.

COMMENCE RAMP TO 75% POWER IAW 0-AP-23.00, RAPID LOAD REDUCTION Step 6, 1-AP-18.00 SRO

  • USE CONTROL RODS AND CHEMICAL SHIM TO MAINTAIN FLUX IN BAND Step 7, 1-AP-18.00 SRO MONITOR MAIN FEED REG VALVE RESPONSE - MAINTAINING SG LEVEL IN BAND BOP Acknowledges Step direction.

SRO Initiate AP-23.00, Rapid Load Reduction END EVENT #4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 25 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior AP-23.00, Rapid Load Reduction SRO The team will hold a transient brief. During the brief the upcoming ramp will be discussed.

The RO and BOP will report critical parameters, as per placard on Main Control Room Bench Board. It is expected that the RO will discuss reactivity parameters associated with the ramp from the pre-planned ramp plan.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

The following reactivity plan will be discussed for a ramp to 75%:

  • Gallons of boric acid required as per plan - 146 gallons
  • D control bank end at 197 steps
  • 5.8 gpm Boric Acid Flow, average rate during ramp.
  • 1957 gallon PG required to stabilize at 75% power.
  • The Team will discuss duration of Emergency Borate at start of Ramp, and remaining boron to be added via normal boration flowpath.

NOTE: RO Emergency borates for 25 seconds which corresponds to ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.

Step 1, 0-AP-23.00 SRO Caution Prior to Step 1:

  • Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.

Notes Prior to Step 1:

  • Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
  • When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
  • Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
  • The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
  • For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 26 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Step 1, 0-AP-23.00 RO TURN ON ALL PRZR HEATERS.

Step 2 0-AP-23.00 INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:

BOP a) Check turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter. If turbine is on limiter; reduce setter an appropriate amount, set load rate thumbwheel to 2% (or higher), press GO.

When Turbine limiter light OFF, press HOLD button.

RO b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5°F.

BOP c) Check or place turbine in IMP IN or IMP OUT as determined by Shift Supervision The SRO chooses IMP IN.

BOP d) Adjust SETTER to desired power level BOP e) Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute)

BOP f) Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button)

BOP g) Reduce Turbine Valve Position Limiter as load decreases Periodically reduce the limiter setpoint during the ramp.

Step 3, 0-AP-23.00 SRO CHECK EMERGENCY BORATION - REQUIRED RO Reports Emergency Boration required.

Step 4, 0-AP-23.00 SRO NOTE: Step 4 or Step 5 may be performed repeatedly to maintain Tref and Tave matched, Flux in band, and control rod position above the LO-LO insertion limit.

RO Acknowledges NOTE.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 27 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Step 4, 0-AP-23.00 SRO PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:

RO a) Check or raise CHG flow to greater than 75 gpm RO b) Transfer the in-service BATP to FAST RO c) Open 1-CH-MOV-1350 for required time (~25 seconds)

RO d) Monitor EMRG BORATE FLOW

  • ( )-CH-FI-( )110 e) After required emergency boration, perform the following:

RO 1) Close 1-CH-MOV-1350 RO 2) Transfer the in-service BATP to AUTO

3) Restore Charging flow control to normal.

Step 5, 0-AP-23.00 RO ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.

Step 6, 0-AP-23.00, NOTES SRO NOTES:

  • If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
  • RCS Tave must be maintained less than or equal to 577°F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
  • I & C should be contacted to provide assistance with adjusting IRPIs.

Step 6, 0-AP-23.00 RO/BOP CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG Step 7, 0-AP-23.00 RO

  • CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 28 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Step 8, 0-AP-23.00 BOP MONITOR STEAM DUMPS FOR PROPER OPERATION Step 9, 0-AP-23.00 SRO NOTIFY THE FOLLOWING:

  • Energy Supply (MOC)
  • Polishing Building
  • Chemistry
  • OMOC Step 10, 0-AP-23.00 SRO EVALUATE THE FOLLOWING:
  • VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.

[VPAP-2802 and EPIP are not applicable for this event.]

Step 11, 0-AP-23.00 SRO CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR.

When reactor power has decreased >15%, then chemistry will be notified.

END EVENT #5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 29 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Adjust 1-CH-YIC-1113 to desired total gallons RO 3. Adjust 1-CH-FC-1113A to desired flow rate.

RO 4. Place the MAKE-UP MOD SEL switch in the BORATE position.

RO 5. Place the MAKE MODE CNTRL switch in the START position.

RO 6. Check proper valve positions.

RO 7. Adjust boration rate using 1-CH-FC-1113A, as necessary.

RO 8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.

a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.

b) Enter N/A for the remaining steps in this Attachment.

Attachment 5 is on the next page RO 9. Check controllers for Primary Grade water and Boric Acid are set correctly.

RO 10. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 11. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 12. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 1 Event No.: 5 Page 30 of 92 Event

Description:

Ramp to 75% Power, 0-AP-23.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.

RO 3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.

RO 4. Place the MAKE-UP MODE SEL switch in the MANUAL position.

RO 5. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.

RO 7. Check proper valve positions.

RO 8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1113B in the AUTO position RO 9. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 10. Check or place the control switches in the AUTO position.

RO 11. Check controllers for Primary Grade water and Boric Acid are set correctly.

RO 12. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 13. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 14. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 31 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Time Position Applicants Action or Behavior Team Diagnose SGTL B SG based on the following:

Alarms:

  • RM-G8 CNDSR AIR EJECTOR ALERT/FAILURE
  • RM-H8 1-SV-RI-111 HIGH Indications:
  • Increasing trend on 1-MS-RR-193, Control Room N16 Trend Recorder, from Normal to 200 GPD.

SRO Direct Unit to Perform Annunciator Response Procedure for A/E Alert and High Alarms.

Note: Unit 2 Operator will perform ARP for A/E RM Alarms. Unit 2 will hand Page 3 and 4 of RM-H8 ARP to BOP to check Auto Actions complete; following E-0 Team Brief.

Verification of ARP RM-H8, A/E RM High Alarm RM-H8, Step 6 BOP NOTE: On a high alarm, air ejector gaseous effluent is diverted from vent stack to containment.

CHECK AUTOMATIC ACTIONS - VALVES POSITIONED AS FOLLOWS:

  • 1-SV-TV-103 - CLOSED Identifies 1-SV-TV-103 Open, places control switch in close.
  • 1-SV-TV-102 - OPEN Identifies 1-SV-TV-102 Closed, places control switch in open.

RM-H8, Step 7 BOP CHECK AIR EJECTOR VENT TO CTMT VV - OPEN

  • 1-SV-TV-102A Identifies 1-EV-RV-102A open Report to SRO that A/E manually aligned to containment.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 32 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

1-AP-16.00 SRO Direct the RO to perform the Immediate Action Steps of 1-AP-16.00.

Step 1, 1-AP-16.00 RO NOTE:

  • RCS average temperature has a direct impact on pressurizer level.

[ 1 ] ___ MAINTAIN PRZR LEVEL:

RO

  • Isolate Letdown Close 1-CH-LCV-1460A and 1-CH-LCV-1460B
  • Control Charging flow Place 1-CH-FCV-1122, CH Flow Control Valve, in Manual Monitor CH Flow on 1-CH-FI-1122 Identify RCS leak rate less than the capacity of a single CH pump Continue adjustment of CH flow to quantify leak rate to determine if reactor trip required Step 1, 1-AP-1600 SRO Upon report of completion of Immediate Action Step of 1-AP-16.00, Perform a commensurate brief; continue to Step 2 of 1-AP-16.00.

Step 2, 1-AP-16.00 SRO CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING

  • PRZR level
  • PRZR pressure
  • RCS subcooling RO Report that PRZR Level, Pressure, and Subcooling Stable RO continues actions to quantify leakrate Step 3, 1-AP-16.00 SRO PLACE THE FOLLOWING COMPONENTS IN OFF:

RO

  • CTMT sump pumps Places 1-DA-P-4B control switch on OFF
  • CTMT vacuum pumps Places 1-CV-P-1A control switch in OFF

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 33 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 4, 1-AP-16.00 SRO NOTE: Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.

SRO CHECK REACTOR TRIP - REQUIRED

  • Leak rate - GREATER THAN 50 GPM OR
  • Adequate makeup not being provided by blender RO Reports RCS leak rate greater than 50 gpm.

NOTE: Due to transient on RCS caused by Ramp for previous event, exact quantification of leak rate may be difficult.

Step 5, 1-AP-16.00 SRO ALIGN CHG PUMP SUCTION TO RWST a) Open 1-CH-MOV-1115B and 1-CH-MOV-1115D RO Opens CH pump Suction MOVs from RWST, 1-CH-MOV-1115B/D b) Close 1-CH-MOV-1115C and 1-CH-MOV-1115E Closes CH pump Suction from VCT MOVs, 1-CH-MOV-1115C/E Step 6, 1-AP-16.00 SRO GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 34 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

1-E Reactor Trip or Safety Injection RO [1] CHECK REACTOR TRIP:

a) Manually trip reactor Pushes the reactor trip push buttons.

b) Check the following:

  • All Rods On Bottom light - LIT
  • Neutron flux - DECREASING RO Reports Reactor Tripped at completion of Step 1. SRO Acknowledges.

RO [2] CHECK TURBINE TRIP:

RO a) Manually trip the turbine Pushes the turbine trip push buttons.

b) Check all turbine stop valves - CLOSED c) Isolate reheaters by closing MSR steam supply SOV

  • 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)

RO Reports Turbine Tripped at completion of Step 2. SRO Acknowledges.

RO [3] VERIFY BOTH AC EMERGENCY BUSES - ENERGIZED RO Reports Both AC Emergency Buses Energized at completion of Step 3. SRO acknowledges.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 35 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

RO [4] CHECK IF SI INITIATED:

a) Check if SI is actuated:

  • LHSI pumps - RUNNING
  • A-F-3 SI INITIATED - TRAIN A
  • A-F-4 SI INITIATED - TRAIN B RO will determine that SI has not occurred and perform step 4a RNO actions:

RO 4a RNO Check if SI is required or imminent as indicated by any of the following:

  • Low PRZR pressure
  • High steamline differential pressure
  • High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.

RO reports SI is not in service or required; Immediate Actions of E-0 are complete; recommend transition to ES-0.1 after completion of Step 4. SRO Acknowledges.

After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0 and announce a transition to ES-0.1. After the immediate actions are verified, the team will conduct a brief.

During the Brief RO/BOP reports that ALL RCPs are tripped.

Team Identify 1B SG experiencing a Large SG Tube Leak.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal, with the exception of the alarms already received. He will also state that containment conditions and the electrical conditions are as you see them (or as reported by the RO/BOP).

If not previously performed, Unit 2 Operator will Provide BOP/SRO with ARP pages Unit 2 for A/E RM High alarm for verification of Auto Actions.

Establish priorities at Brief End, RO:

SRO

  • Complete verification of A/E High Alarm auto actions.
  • Contact Service Building Operator to check status of RCP breakers.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 36 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

SRO When Brief is complete Announce Transition to ES-0.1, Reactor Trip Response, Read the First NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.

Transitions to 1-AP-24.01 Step 1, 1-AP-24.01 SRO CAUTION: If the leak rate increases to 150 gpm, 1-E-0, Reactor Trip or Safety Injection, must be implemented.

NOTE:

  • Procedure 1-ES-0.1, Reactor Trip Response, must not be performed when implementing this procedure.
  • Refer to Attachment 8 for guidance on transient AFW control.

CHECK SI - IN SERVICE RO Identifies NO not required. Team Goes To Step 3.

Note: Attachment 8 actions are start on Page 40.

Step 3, 1-AP-24.01 SRO CHECK CONDENSATE POLISHING BUILDING - BYPASSED RO Identifies Polishing Building bypassed Step 4, 1-AP-24.01 SRO CHECK ALL AC BUSSES - ENERGIZED BY OFFSITE POWER RO Identifies all AC Buses energized by off-site power by:

  • Checks breakers 15H8/15J8 closed
  • Station Service buses energized using Voltage/Current indications on Benchboard.
  • Checks for Abnormal Electrical System alarms on K Annunciator Panel.

Step 5, 1-AP-24.01 SRO

  • CHECK PRZR LEVEL - GREATER THAN 22%

RO Reports actual pressurizer level and trend.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 37 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 6, 1-AP-24.01 SRO CHECK FW STATUS:

a) Check RCS Average temperatures - LESS THAN 554°F RO Identifies RCS Tave less than 554°F b) Check Feed REG valves - CLOSED RO Identifies FRVs closed c) Close SG FW isolation MOVs

  • 1-FW-MOV-154A
  • 1-FW-MOV-154B
  • 1-FW-MOV-154C RO/BOP Closes SG FW Isolation MOVs d) Check AFW pumps - RUNNING
  • Motor Driven AFW pumps
  • TD AFW pump RO/BOP Identifies MD and TD AFW Running e) Check total AFW flow - GREATER THAN 540 GPM (350 W/O RCPs)

RO/BOP Identifies AFW flow indicated f) Check emergency buses - BOTH ENERGIZED RO Identifies Emergency buses energized g) Control feed flow to maintain narrow range level between 22% and 50%

BOP Acknowledges control of SG level when returned to NR scale.

Step 7, 1-AP-24.01 SRO CHECK PCS POINTS USING GROUP 80 REVIEW OR MAIN STEAM P & ID:

  • R1RM204C, RI-MS-124
  • R1RM205C, RI-MS-125
  • R1RM206C, RI-MS-126 RO/BOP Checks points for abnormal indication.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 38 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 8, 1-AP-24.01 SRO IDENTIFY AFFECTED SG(S):

  • Unexpected rise in any SG narrow range level OR
  • High radiation from any SG MS line monitor OR
  • High radiation from any SG blowdown line OR
  • High radiation from any SG sample OR
  • High radiation from any SG N-16 monitor RO/BOP Identifies rise in B SG NR level Step 9, 1-AP-24.01 SRO
  • CHECK AFFECTED SG LEVEL:

a) Narrow range level - GREATER THAN 12%

BOP Acknowledges when B SG NR Level > 12%, perform substep b).

b) Stop feed flow to affected SG(s)

BOP Isolates AFW flow to B SG, by closing 1-FW-MOV-151 C / D.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 39 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 10, 1-AP-24.01 SRO ISOLATE AFFECTED SG(S):

a) Adjust affected SG PORV controller setpoint to 1035 psig BOP Checks B SG PORV setpoint at 1035 psig b) Check affected SG PORV - CLOSED BOP Identifies B SG PORV closed c) Check blowdown TVs from affected SG - CLOSED RO Identifies B SG BD TVs closed.

d) Locally close steam supply valve to TD AFW pump:

  • 1-MS-87 for SG A
  • 1-MS-120 for SG B
  • 1-MS-158 for SG C BOP Directs Service Building operator to close 1-MS-120.

e) Close SG FW Isolation MOV, 1-FW-MOV-154A, B, or C BOP Identifies 1-FW-MOV-154B closed f) GO TO Step 13

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 6 Page 40 of 92 Event

Description:

SG Tube Leak 74 gpm, A/E Auto Functions Fail, RCPs trip on swap to RSST Cue: By Evaluator when blender has been returned to AUTO.

Step 1, AP-24.01, Attachment 8 BOP Maintain minimum AFW flow of 540 gpm with RCP(s) in service until one SG Narrow Range level is greater than 12%.

Checks AFW ~1050 gpm Step 2, AP-24.01, Attachment 8 Maintain minimum AFW flow of 350 gpm with NO RCPs running, until one SG BOP Narrow Range level is greater than 12%.

Throttles AFW to SGs per Step 2 to flow rate established by SRO or ~ 120 gpm per SG using 1-FW-MOV-151 A through F control switches.

Step 3, AP-24.01, Attachment 8 BOP NOTE: AFW to idle loop(s) (RCP secured), should be throttled to prevent depressurization of the SG and subsequent Header / Line SI. AFW flow between approximately 60 gpm and 100 gpm should be adequate to prevent a Header / Line SI.

Identifies NOTE as not applicable for this event.

When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50% by throttling AFW Isolation MOVs:

  • SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
  • SG B, 1-FW-MOV-151C and 1-FW-MOV-151D
  • SG C, 1-FW-MOV-151A and 1-FW-MOV-151B Identifies need to monitor flow rate as SG NR level recovers.

Step 4, AP-24.01, Attachment 8 BOP Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves:

Identifies Step as not applicable.

Contact Service Building operator to check status of RCP breakers.

BOP When contacted the Service Building operator will report no abnormalities with the RCP breakers, but the Speed Sensing Panel appears to be malfunctioning.

Performs a Focus Brief to apprise the other Team members of RCP status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 41 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

SG Tube Leak escalates to 710 gpm Tube Rupture RO Diagnose SG Tube Rupture by:

RCS Pressure decrease.

Pressurizer Level decrease.

Manually raise CH flow to maximum.

Identify pressurizer level decreasing.

Report to SRO that Safety Injection is required.

Re-Perform High Level Steps, 1 through 3 of E-0.

Manually Initiate Safety Injection.

Check Annunciator 1A-F3, SI Initiated Train A - LIT Check Annunciator 1A-F4, SI Initiates Train B - LIT Check LHSI Pumps Running.

Report to SRO Immediate Actions of E-0 with SI Complete.

Critical Task 2) Isolate steam release from ruptured SG within 30 Minutes START Time: _____________

SRO The team will hold a transition brief. During the brief it will be identified that SI was initiated and the SGTL has degraded into a SGTR.

The SRO will set priorities:

RO - Continue with SRO in performance of E-0 to E-3.

BOP - Perform Attachment 1 through 3 of E-0.

Step 5, E-0 SRO/BOP Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained under last section of Event 9).

SRO/RO SRO may direct the RO to perform Attachment 10 of 1-E-0 for Ruptured SG Isolation and AFW Control. This may or may not be initiated at any time during the performance of E-0. Attachment 10 actions are contained at the end of this section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 42 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 6, E-0 RO

  • CHECK RCS AVERAGE TEMPERATURE
  • STABLE AT 547°F OR
  • TRENDING TO 547°F The team will identify that RCS temperature is decreasing. The team should attribute this to the injection of SI into the RCS and AFW flow to the SGs. It is acceptable for the team to enter the RNO portion of this step and perform the applicable steps (summarized below):

Stop dumping steam Reduce AFW flow to the SG Close MSTVs if cooldown continues Step 7. E-0

7. CHECK PRZR PORVs AND SPRAY VALVES:

RO a) PRZR PORVs - CLOSED b) PRZR spray controls

  • Demand at Zero (or)
  • Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN Step 8, E-0 SRO NOTE: Seal injection flow should be maintained to all RCPs.
  • CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

RO a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.

b) RCS subcooling - LESS THAN 30°F [85°F]

RCS subcooling will NOT be less than 30 °F RNO for the step is to go to step 9.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 43 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 9, E-0 RO CHECK IF SGs ARE NOT FAULTED:

  • Check pressures in all SGs a) STABLE OR INCREASING AND b) GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.

Step 10, E-0 RO CHECK IF SG TUBES ARE NOT RUPTURED:

  • Condenser air ejector radiation - NOT NORMAL
  • SG blowdown radiation - NOT NORMAL
  • SG MS radiation - NORMAL
  • TD AFW pump exhaust radiation - NORMAL
  • SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO should observe B SG NR level going up uncontrollably.

SRO RNO: GO TO 1-E-3, STEAM GENERATOR TUBE RUPTURE.

SRO The team will hold a transition brief. During the brief it will be identified that B SG is ruptured, current isolation status of the ruptured SG and that the team is transitioning to 1-E-3.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified alarms. He will also state that containment conditions and the electrical conditions are as you see them.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 44 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

BEGIN Step 1, 1-E-3:

NOTE: Seal injection flow should be maintained to all RCPs.

  • CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

RO a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO will identify that two charging pumps are running.

b) RCS subcooling - LESS THAN 30°F [85°F]

RO will identify that RCS subcooling is greater than 30°F RNO is to go to step 2 Step 2, E-3 IDENTIFY RUPTURED SG(s):

  • Unexpected rise in any SG narrow range level SRO OR
  • High radiation from any SG MS line monitor OR
  • High radiation from any SG blowdown line OR
  • High radiation from any SG sample Team identifies B SG NR level rising unexpectedly.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 45 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 3, E-3 SRO CAUTION:

  • If the TD AFW pump is the only available source of feed flow, steam supply to the TD AFW pump must be maintained from at least one SG.
  • At least one SG must be maintained available for RCS cooldown.
3. ISOLATE RUPTURED SG(s):

RO a) Adjust ruptured SG PORV controller setpoint to 1035 psig b) Check ruptured SG(s) PORV - CLOSED c) Verify blowdown TVs from ruptured SG(s) - CLOSED d) Locally close steam supply valve(s) to TD AFW pump:

  • 1-MS-120 for B SG If 1-MS-120 not closed iaw attachment 10 of 1-E-0, then a field operator will be dispatched to close it at this time.

e) Close ruptured SG(s) MSTV (B)

Partial completion of the critical task (WOG E-3A) to isolate the SG is accomplished by performance of this step. KOA: For the design basis tube rupture, isolate the ruptured SG from the atmosphere/Turbine building within 30 minutes.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 46 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 4, E-3 SRO CAUTION: If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless needed for RCS cooldown.

  • CHECK RUPTURED SG LEVEL:

a) Narrow range level - GREATER THAN 12% [18%]

b) Stop feed flow to ruptured SG(s)

RO Identifies B SG level >12%, closes 1-FW-MOV-151C/D to isolate AFW Flow c) Check ruptured SG AFW MOVs auto-open signal - DEFEATED Identifies auto-open signal not defeated, SRO goes to Step 4 c) RNO NOTE: BOP may have performed the following IAW Attachment 10.

1) Select the ruptured SG AFW MOVs using the following switches:

RO

  • H TRAIN DISABLE SELECTOR SWITCH
  • J TRAIN DISABLE SELECTOR SWITCH
2) Defeat the auto-open signal for the selected MOVs by placing the following key switches in the DISABLE SELECTED position:
  • H TRAIN AUTO OPEN ENABLE SWITCH
  • J TRAIN AUTO OPEN ENABLE SWITCH Step 5, E-3 SRO CAUTION: Major steam flow paths from the ruptured SG(s) should be isolated before initiating RCS cooldown.

CHECK RUPTURED SG(S) PRESSURE - GREATER THAN 350 PSIG RO Identifies B SG pressure ~ 1000 psig.

Step 6, E-3 SRO

  • CHECK LOW PRZR PRESS SI SIGNAL - BLOCKED
  • Permissive Status light C LIT RO Identifies PSL C2 NOT LIT.

SRO WHEN PRZR pressure less than 2000 psig, THEN do the following:

a) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block.

b) Check Permissive Status light C LIT.

NOTE: BOP may have completed this action in E-0, Attachment 1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 47 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 7, E-3 SRO CHECK LOW TAVE SI SIGNAL - BLOCKED

  • Permissive Status light F LIT RO Identifies PSL F1 NOT LIT.

SRO WHEN Tave less than 543°F, THEN do the following:

a) Turn both HI STM FLOW & LO TAVG OR LP switches to block.

b) Check Permissive Status light F LIT.

NOTE: BOP may have completed this action in E-0, Attachment 1.

Step 8, E-3 SRO CAUTION:

  • Flow on each Main Steamline should be kept less than 1.0 x 106 PPH to prevent Main Steamline isolation during RCS cooldown with the Steam Dumps.
  • If no RCPs are running, RCS cooldown and depressurization may cause a false Integrity Status Tree indication on the ruptured loop. The Cold Leg indication on the ruptured loop should be disregarded until after the performance of Step 36.

NOTE: RCP trip criteria does NOT apply after initiation of an operator controlled cooldown.

INITIATE RCS COOLDOWN:

a) Determine required core exit temperature (ONE TIME):

SRO/BOP Concur Target CETC temperature 485 °F if SG pressure between 901 and 1000 psig, or 495° if SG pressure between 1001 and 1085 psig.

Step 8, E-3, Continued RO b) Place Steam Dump Mode Select switch in Steam Pressure mode c) Check RCS Tave - LESS THAN 543°F RO d) Place the STM DUMP CNTRL switch in BYP INTLK and then return to ON e) Check Bypass Status light D LIT RO f) Dump steam to condenser from intact SG(s) at maximum rate g) Check CETCs - LESS THAN REQUIRED TEMPERATURE SRO When RCS Temperature < 543°F, SRO will direct the block of HSF SI and check of PSL F1 LIT.

When RCS pressure < 2000 psig, SRO will direct the block of Low Pressure/Header-to-Line SI Signal, and check the PSL C2 LIT.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 48 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

RO Performs the Block of SI Signals and check of PSLs when directed.

h) Stop RCS cooldown RO When target CETC Temperature reached, RO throttles back on steam dumps.

i) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE SRO SRO will direct a band for control of CETC temperature.

Step 9, E-3 SRO CHECK INTACT SG LEVELS:

a) Any narrow range level - GREATER THAN 12% [18%]

b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%

RO/BOP Adjust AFW to restore A and C SG NR Level to 22-50%.

Step 10, E-3 SRO CAUTION: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure decreases to less than 2335 psig.

  • CHECK PRZR PORVs AND BLOCK VALVES:

a) Power to PRZR PORV block valves - AVAILABLE b) PRZR PORVs - CLOSED c) PRZR PORV block valves - AT LEAST ONE OPEN Step 11. E-3 SRO RESET BOTH TRAINS OF SI RO Push SI Reset Pushbuttons. SI previously reset.

Step 12, E-3 SRO RESET CLS:

a) Check CTMT pressure - HAS EXCEEDED 17.7 psia RO Report No, CTMT has not exceeded 17.7 psia.

RNO a) GO TO Step 13.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 49 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 13, E-3 SRO CHECK INSTRUMENT AIR AVAILABLE:

a) Check annunciator B-E NOT LIT RO Report Yes, B-E-6 Not Lit.

b) Check at least one CTMT IA compressor - RUNNING

  • 1-IA-C-4A or 1-IA-C-4B RO Report Yes, 1-IA-C-4A running c) Check 1-IA-TV-100 - OPEN RO Report Yes, 1-IA-TV-100 open.

Step 14, E-3 SRO ALIGN CONDENSER AIR EJECTOR TO CTMT:

a) Check the following:

  • 1-SV-TV-102 - OPEN
  • 1-SV-TV-103 - CLOSED RO Reports valves in required position. Valves Manually Aligned by BOP on A/E RM auto failure during Event 6.

b) Open the following valve:

  • 1-SV-TV-102A RO/BOP Opens 1-SV-TV-102A.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 50 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 15, E-3 SRO CAUTION: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.

  • CHECK IF LHSI PUMPS SHOULD BE STOPPED:

a) Check LHSI pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST RO Reports 1 LHSI pump running with suction aligned to RWST.

b) RCS pressure - GREATER THAN 250 PSIG [400 PSIG]

RO Reports RCS pressure greater than 250 psig.

c) Stop LHSI pumps and put in AUTO RO Stops running LHSI pump and places in AUTO.

Step 16, E-3 SRO CHECK IF RCS COOLDOWN SHOULD BE STOPPED:

a) Check CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP Reports CETCs < required temperature b) Stop RCS cooldown RO/BOP Reports RCS Coodown stopped.

c) Maintain CETCs - LESS THAN REQUIRED TEMPERATURE RO/BOP Reports that RCS temperature being maintained in required band.

Step 17, E-3 SRO CHECK RUPTURED SG(s) PRESSURE - STABLE OR INCREASING BOP Reports B SG pressure stable.

Step 18. E-3 SRO CHECK RCS SUBCOOLING BASED ON CETCs - GREATER THAN 50°F [105°F]

BOP Reports indicated subcooling value.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 51 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

Step 19, E-3 SRO DEPRESSURIZE RCS TO MINIMIZE BREAK FLOW AND REFILL PRZR:

a) Check normal spray - AVAILABLE

  • RCP C AND 1-RC-PCV-1455B - BOTH AVAILABLE OR
  • RCPs A and B, AND 1-RC-PCV-1455A - BOTH AVAILABLE RO Identifies No pressurizer spray available, SRO Goes To Step 20.

Step 20, E-3 SRO CAUTION:

  • The PRT may rupture if a PRZR PORV is used for RCS depressurization.

Rupturing the PRT may result in abnormal containment conditions.

  • Cycling of the PRZR PORV should be minimized.

NOTE: The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PRZR level.

DEPRESSURIZE RCS USING PRZR PORV TO MINIMIZE BREAK FLOW AND REFILL PRZR:

a) PRZR PORV - AT LEAST ONE AVAILABLE b) Open one PRZR PORV until ANY of the following conditions satisfied:

(Attachment 4 lists conditions)

  • PRZR level - GREATER THAN 69%

OR

  • RCS subcooling based on CETCs - LESS THAN 30°F [85°F]

OR

  • BOTH of the following exist:
1) RCS pressure - LESS THAN RUPTURE SG(s) PRESSURE
2) PRZR level - GREATER THAN 22% [50%]

RO When Attempt Made to open 1-RC-PCV-1455C, PCV will Not Open.

SRO Transition to ECA-3.3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 52 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

ATTACHMENT 10 of 1-E-0

1. Check SI is in progress. If SI is not in progress, then return to procedure step in effect.

RO/BOP RO/BOP identifies that SI is in progress.

ATTACHMENT 10 of 1-E-0 RO/BOP 2. Identify Ruptured SG by one of the following conditions:

  • Unexpected rise in any SG Narrow Range level
  • High radiation from any SG MS line monitor
  • High radiation from any SG Blowdown line With SRO concurrence identifies B SG as the ruptured SG ATTACHMENT 10 of 1-E-0 RO/BOP 3. Check running or start AFW Pumps, as necessary
  • 1-FW-P-3A
  • 1-FW-P3B
  • 1-FW-P-2 ATTACHMENT 10 of 1-E-0 RO/BOP 4. When ruptured SG Narrow Range level is greater than 12%, then isolate feed flow to ruptured SG by closing SG AFW Isolation MOVs:
  • SG B, 1-FW-MOV-151C and 1-FW-MOV-151D RO/BOP closes 1-FW-MOV-151C/D when SG level is greater than 12% Narrow Range.

Completion of Critical Task: WOG - A; Isolate feed flow into and steam flow from ruptured SG before a transition is made to ECA-3.1. STOP Time: _________.

ATTACHMENT 10 of 1-E-0 RO/BOP 5. Select the ruptured SG AFW MOVs using the following switches:

  • H TRAIN DISABLE SELECTOR SWITCH
  • J TRAIN DISABLE SELECTOR SWITCH

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 7 Page 53 of 92 Event

Description:

SGTL becomes SGTR (800) gpm, AP-16.00, E-0, E-3.

Cue: Notify Evaluator at 12% on B SG, then upgrade flowrate to SGTR.

RO/BOP ATTACHMENT 10 of 1-E-0

6. Disable the auto-open signal for the selected MOVs by placing the following keyswitches in the DISABLE SELETED position:
  • H TRAIN AUTO OPEN ENABLE SWITCH
  • J TRAIN AUTO OPEN ENABLE SWITCH ATTACHMENT 10 of 1-E-0 RO/BOP CAUTION: At least one SG must be maintained available for RCS heat sink.
7. Locally close steam supply valve to the TD AFW pump:
  • 1-MS-120 RO/BOP directs field operator to close 1-MS-120.

The field operator will acknowledge the requirement to close 1-MS-120. The field operator will later report that 1-MS-120 is closed.

ATTACHMENT 10 of 1-E-0 RO/BOP 8. Control Feed Flow to the SG IAW the following requirements:

  • Minimum AFW flow is 350 gpm with SI initiated, until one SG Narrow Range level is greater than 12%
  • When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50%.
  • SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
  • SG C, 1-FW-MOV-151A and 1-FW-MOV-151B End EVENT #7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 8 Page 54 of 92 Event

Description:

1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.

Time Position Applicants Action or Behavior 1-ECA-3.3 Actions SRO 1. CHECK RUPTURED SG(S) NARROW RANGE LEVEL - LESS THAN 75%

[73%]

RO Reports that B SG Level is greater than 75%.

1. RNO - GO TO Step 6 SRO 6. CHECK IF SI CAN BE TERMINATED:

a) Check RCS subcooling based on CETCs - GREATER THAN 30°F [85°F]

RO/BOP Identifies that RCS subcooling is greater than 30°F.

b) Check secondary heat sink:

  • Total feed flow to SGs - GREATER THAN 350 GPM [450 GPM]

AVAILABLE OR

  • Narrow range level in at least one intact SG - GREATER THAN 12%

[18%]

RO/BOP Identifies A and C SG NR level >12% OR identify >350 gpm flow Available.

c) Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs RVLIS INDICATION Running Full Range Dynamic Range 0 GREATER THAN 63%

1 GREATER THAN 36%

2 GREATER THAN 51%

3 GREATER THAN 82%

RO/BOP Identify that RVLIS Full Range is Greater than 63%.

d) Check any ruptured SG narrow range level - INCREASING IN AN UNCONTROLLED MANNER OR OFFSCALE HIGH BOP BOP will identify that B SG Level is Off-Scale High.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 8 Page 55 of 92 Event

Description:

1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.

SRO 7. STOP ALL BUT ONE CHG PUMP AND PUT IN AUTO RO Secure one of the running charging pumps SRO 8. ISOLATE HHSI TO COLD LEGS:

a) Verify the following:

RO 1) CHG pump suctions from RWST - OPEN

  • 1-CH-MOV-1115B
  • 1-CH-MOV-1115D
2) Check CHG pump miniflow recirc valves - OPEN
  • 1-CH-MOV-1275A
  • 1-CH-MOV-1275B
  • 1-CH-MOV-1275C
  • 1-CH-MOV-1373 b) Close HHSI to Cold Leg:
  • 1-SI-MOV-1867C RO
  • 1-SI-MOV-1867D
  • 1-SI-MOV-1842 SRO 9. ESTABLISH CHARGING FLOW:

a) Close CHG flow control:

RO

  • 1-CH-FCV-1122 a) b) Check CHG line isolation - OPEN
  • 1-CH-HCV-1310A c) Open CHG line isolation MOVs RO
  • 1-CH-MOV-1289A
  • 1-CH-MOV-1289B RO d) Establish at least 40 gpm charging flow using CHG flow control

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 8 Page 56 of 92 Event

Description:

1-RC-PCV-1455C not open, 1-ECA-3.3 Cue: Pre-Event Failures.

SRO 10. CHECK SI FLOW NOT REQUIRED:

  • RCS subcooling based on CETCs - GREATER THAN 30°F [85°F]
  • Check RVLIS indication - GREATER THAN VALUE FROM TABLE RCPs RVLIS INDICATION Running Full Range Dynamic Range 0 GREATER THAN 63%

1 GREATER THAN 36%

2 GREATER THAN 51%

3 GREATER THAN 82%

RO Reports Full Range RVLIS >63%.

END Event 8 End Scenario

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 57 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

ATTACHMENT 1 OF E-0 BOP 1. CHECK FW ISOLATION:

  • Feed pump discharge MOVs - CLOSED
  • 1-FW-MOV-150A
  • 1-FW-MOV-150B
  • MFW pumps - TRIPPED
  • Feed REG valves - CLOSED
  • SG FW bypass flow valves - DEMAND AT ZERO
  • SG blowdown TVs - CLOSED BOP 2. CHECK CTMT ISOLATION PHASE I:
  • Phase I TVs - CLOSED
  • 1-CH-MOV-1381 - CLOSED
  • 1-SV-TV-102A - CLOSED
  • PAM isolation valves - CLOSED
  • 1-DA-TV-103A
  • 1-DA-TV-103B BOP will identify 1-DA-TV-100A/B, and 1-MS-TV-109 OPEN and CLOSE them.

BOP 3. CHECK AFW PUMPS RUNNING:

a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 58 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of E-0 BOP 4. CHECK SI PUMPS RUNNING:

  • CHG pumps - RUNNING
  • LHSI pumps - RUNNING BOP starts 1-SI-P-1B 1-SI-P-1B START TIME: _____ (for critical task verification, CT-1)

BOP 5. CHECK CHG PUMP AUXILIARIES:

  • CHG pump CC pump - RUNNING
  • CHG pump SW pump - RUNNING
6. CHECK INTAKE CANAL:

BOP

  • Level - GREATER THAN 24 FT
  • Level - BEING MAINTAINED BY CIRC WATER PUMPS
7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:

a) Check if ANY of the following annunciators - HAVE BEEN LIT

  • E-F-10 (High Steam Flow SI)
  • B-C-4 (Hi Hi CLS Train A)

BOP

  • B-C-5 (Hi Hi CLS Train B)

Identifies annunciators not lit and goes to step 8.

BOP *8. CHECK IF CS REQUIRED:

a) CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 59 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of E-0 BOP *10. BLOCK LOW PRZR PRESS SI SIGNAL:

a) Check PRZR pressure - LESS THAN 2000 psig b) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c) Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.

BOP *11. BLOCK LOW TAVE SI SIGNAL:

Step may not be performed at this time (if Tave is greater than 543°F).

a) Check RCS Tave - LESS THAN 543°F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c) Verify Permissive Status light F LIT NOTE:

  • CHG pumps should be run in the following order of priority: C, B, A.
  • Subsequent SI signals may be reset by re-performing Step 12.

BOP 12. CHECK SI FLOW:

a) HHSI to cold legs - FLOW INDICATED

  • 1-SI-FI-1961 (NQ)
  • 1-SI-FI-1962 (NQ)
  • 1-SI-FI-1963 (NQ)
  • 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c) Reset SI.

d) Stop one CHG pump and out in AUTO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 60 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Attachment 1 of E-0 e) RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:

1) Verify reset or reset SI.
2) Stop one LHSI pump and put in AUTO.

1-SI-P-1A or 1B STOP TIME: ______

3) GO TO Step 13.

Critical Task: Secure one LHSI pump within 30 minutes of two LHSI pumps in service. [SPS E-1G, CT-1]

Note: If 1-SI-P-1B was not started on Step 4 of Attachment 1, CT becomes Not Applicable.

BOP 13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]

BOP 14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.

BOP 15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next page of this guide)

Depending on timing, this attachment may have already been completed.

BOP 16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Identify failure of 1-VS-MOD-103A CLOSES the MOD.

Unit 2 Operator will state that Unit 2 is at 100% power (if asked)

Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 61 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Time Position Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 BOP NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.

ATTACHMENT 2 of 1-E-0 BOP 1. Check opened or open CHG pump suction from RWST MOVs.

  • 1-CH-MOV-1115B
  • 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 BOP 2. Check closed or close CHG pump suction from VCT MOVs.
  • 1-CH-MOV-1115C
  • 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 BOP 3. Check running or start at least two CHG pumps. (listed in preferred order)
  • 1-CH-P-1C
  • 1-CH-P-1B
  • 1-CH-P-1A ATTACHMENT 2 of 1-E-0 BOP 4. Check opened or open HHSI to cold legs MOVs.
  • 1-SI-MOV-1867C
  • 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 BOP 5. Check closed or close CHG line isolation MOVs.
  • 1-CH-MOV-1289A
  • 1-CH-MOV-1289B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 62 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

ATTACHMENT 2 of 1-E-0 BOP 6. Check closed or close Letdown orifice isolation valves.

  • 1-CH-HCV-1200A
  • 1-CH-HCV-1200B
  • 1-CH-HCV-1200C RO/BOP will CLOSE 1-CH-HCV-1200A and 1-CH-HCV-1200B ATTACHMENT 2 of 1-E-0 BOP 7. Check opened or open LHSI suction from RWST MOVs.
  • 1-SI-MOV-1862A
  • 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 BOP 8. Check opened or open LHSI to cold legs MOVs.
  • 1-SI-MOV-1864A
  • 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 BOP 9. Check running or start at least one LHSI pump.
  • 1-SI-P-1A
  • 1-SI-P-1B BOP Would have started 1-SI-P-1B as part of attachment 1.

ATTACHMENT 2 of 1-E-0 BOP 10. check High Head SI flow to cold legs indicated.

  • 1-SI-FI-1961
  • 1-SI-FI-1962
  • 1-SI-FI-1963
  • 1-SI-FI-1943 or 1-SI-FI-1943A

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 63 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

ATTACHMENT 2 of 1-E-0 BOP 11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.

  • Alternate SI to Cold legs
  • Hot leg injection

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 64 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 65 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 66 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 67 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

If asked, Unit 2 has throttled Chilled Water flow as required by CAUTION prior to Step 10.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 68 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

If asked, pressure indicated on PDI-118, 116, 215, and 206 equals the pressure indicated on PDI-100/101/200/201 pressure indicators.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: 9 Page 69 of 92 Event

Description:

BOP Failures. 1-SI-P-1B not auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOV-103A not close, 1-MS-TV-109 and 1-DA-TV-100 A/B not close.

Cue: Pre-load Malfunctions.

Unit 2 will assume responsibility for this attachment at this point.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 70 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 71 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 72 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 73 of 92 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 74 of 92 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:

Recall IC -261 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.

Acknowledge AAC System Alarm on Waste Disposal Panel Open the monitor window and add the following points to it:

  • asp_ao_off
  • MS-120, B Steam Supply to TDAFW Pump Enter the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Type (Auto or Manual)

RC4903 PRZR LEVEL XMTR CH 10 20 1 0.0 -0.2 Manual 3 FAILURE (461)

FW1803 B S/G MN FD FLOW 10 0 3 0.0 1 Manual XMTR FT-1487 FAILS SD0201 HP HTR DRN PP SD-P-1A 10 0 5 FALSE TRUE Manual TRIPS: OVR-CURRENT RC2402 STEAM GENERATOR B 10 60 9 0.0 8 Manual TUBE RUPTURE PCV455C_OPEN PCV-1455C 0 0 11 OFF OFF Manual PRZR RELIEF VALVE OPEN PCV455C_CLOSE PCV-1455C 0 0 11 OFF ON Manual PRZR RELIEF VALVE CLOSE RCMOV535_BKR RC-MOV-535 0 0 16 1 0 AUTO PORV Block Valve RC5601 RC-P-1A BKR 15A3 0 0 17 FALSE TRUE AUTO SPURIOUS TRIP RC5602 SPURIOUS TRIP RCP 1B 0 0 17 FALSE TRUE AUTO RC5603 SPURIOUS TRIP RCP 1C 0 0 17 FALSE TRUE AUTO AS02 DISABLE SV-TV-102 OPEN 0 0 30 FALSE TRUE ACTIVE AS05 DISABLE SV-TV-103 0 0 30 FALSE TRUE ACTIVE CLOSE SI2409 SI RELAY CI1A FAILS TO 0 0 30 FALSE TRUE ACTIVE ACTUATE SI2505 SI RELAY SI5B FAILS TO 0 0 30 FALSE TRUE ACTIVE ACTUATE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 75 of 92 SIMULATOR OPERATORS GUIDE Enter the following EVENT TRIGGERS:

Trigger# EVENT Command Trigger setup to trip 1-RC-MOV1535 breaker when control switch in open to stroke test open time, Event 1.

Trigger 14 sets when 1-RC-MOC-1535 closed. Trigger 15 sets when 1-RC-MOV-1535 control switch taken to open. Trigger 16 set when both Trigger 14 and 15 are TRUE. Trigger 16 implements Remote Function trip of 1-RC-MOV-1535 breaker.

14 "rcmov535 .le. 0.0002" Sets Trigger 14 15 "mov535_open" Sets Trigger 15 16 "et_array(14) .and. et_array(15)" Sets Trigger 16 Trigger setup to trip A, B, C, RCPs when Generator Output breakers open. (EL2 Auto Trigger). Actuates Trigger which implements Malfunction RC5601/5602/5603.

17 ".not. (elg102_bkr(2) .and. Sets Trigger 17 elg1t240_bkr)"

Trigger setup to override 1-RC-LCV-1460A and B control switch to Open to simulate removing PRZR level control output fuses.

20 "chw180<500.0" Set Trigger 20 when Letdown flow < 1 gpm.

21 "chlcv460a_open" Set Trigger 21 when 1-CH-LCV-1460A switch taken to Open.

22 "chlcv460b_open" Set Trigger 22 when 1-CH-LCV-1460B switch taken to Open.

23 "et_array(20) .and. et_array(21)" Sets Trigger 23 when Trigger 20 and 21 are ACTIVE.

Actuates override for 1-CH-LCV-1460A switch in Open 24 "et_array(20) .and. et_array(22)" Sets Trigger 24 when Trigger 20 and 22 are ACTIVE.

Actuates override for 1-CH-LCV-1460B switch in Open Enter the following Remote Functions:

Override Set Condition Trigger AAC_SMS_MODE OFF AAC DG OFF 30 LOCAL MODE SWITCH POSITION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 76 of 92 SIMULATOR OPERATORS GUIDE Enter the following Switch Overrides:

Override Set Condition Trigger Override CH LCV-460A OPEN ON 23 Override CH LCV 460B OPEN ON 24 TRIGGER TYPE DESCRIPTION 1 MAN Fails PZR Level CH III to ~34%.

3 MAN B SG MN Feed Flow Transmitter fails high.

5 MAN Trip running High Pressure Drain Pump Steam Generator Tube Leak, 74 gpm 9 MAN 11 MAN Overrides 1-RC-PCV-1455C control switch Open OFF, Close ON 16 AUTO Open Breaker to 1-RC-MOV-1535 17 AUTO Spurious Trip A/B/C RCPs when Gen. Output Bkrs open 23 AUTO Overrides 1-CH-LCV-1460A control switch Open.

24 AUTO Overrides 1-CH-LCV-1460B control switch Open.

AS02 DISABLE SV-TV-102 OPEN AS03 DISABLE SV-TV-103 CLOSE SI2409 SI RELAY CI1A FAILS TO ACTUATE 30 ACTIVE SI2505 SI RELAY SI5B FAILS TO ACTUATE AAC_SMS_MODE OFF AAC DG LOCAL MODE SWITCH POSITION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 77 of 92 SIMULATOR OPERATORS GUIDE Verify the following control room setup:

Place the simulator in RUN and verify normal 100% power operation indications.

Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:

Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).

Verify Ovation System operating.

Reset ICCMs.

Verify Component Switch Flags.

Verify Brass Caps properly placed.

Verify SG PORVs set for 1035 psig.

Verify Rod Control Group Step Counters indicate properly.

Verify Ovation CRT display.

Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)

Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:

AP-53.00 AP-18.00 AP-23.00 AP-16.00 E-0 E-3 (2) ECA-3.3 OP-CH-007 Reactivity Sheet OP-ZZ-002 PT-18.6I Verify Reactivity Placard is current.

Verify ALL PINK MAGNETS are accounted for.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 78 of 92 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

Ask for and answer questions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 79 of 92 SIMULATOR OPERATORS GUIDE Conduct shift turnover:

The initial conditions have Unit 1 at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance. In accordance with VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training. A BAST boron concentration is 8.0 w/%.

Shift orders are to maintain 100% power on Unit #1 and upon relieving the watch, perform PT-18.6I, Pressurizer Block Valve Stroke Test. Performance of PT-18.6I has been authorized and has been PSA analyzed for current plant conditions.

When the team has accepted the shift, proceed to the Session Conduct Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 80 of 92 SIMULATOR OPERATORS GUIDE Session Conduct:

  • Ensure conditions in Simulator Set-up are established.
  • Ensure Trigger 30 is active prior to team entering the simulator.
  • Verify Exam Security has been established and ASP_AO_OFF = True.

EVENT 1 Test Cycle PORV Block Valves, 1-PT-18.6I BOOTH:

30 minutes prior to the beginning of the scenario, provide the team with a copy of 1-PT-18.6I, Pressurizer Block Valve Stroke Test. The team will pre-brief the PT prior to entering the simulator.

Trigger setup to trip 1-RC-MOV1535 breaker when control switch in open to stroke test open time, Event 1. Monitor the following triggers as 1-RC-MOV-1535 is closed/opened.

Trigger 14 sets (becomes Active) when 1-RC-MOC-1535 closed.

Trigger 15 sets (becomes Active) when 1-RC-MOV-1535 control switch taken to open.

Trigger 16 sets when both Trigger 14 and 15 are TRUE.

Trigger 16 implements Remote Function to trip 1-RC-MOV-1535 breaker.

Operations Supervisor/Management/Work Week Coordinator:

  • If contacted, will acknowledge 1-RC-MOV-1535 breaker tripped when the valve was re-opened, suspension of the PT, and Tech Spec Clock identified (1 hour/72 hour).

Field Operator: (3 minute delay from request to answer)

  • If Contacted, as Service Building Operator, to check the status of 1-RC-MOV-1535 breaker, 1H1-2S 6A; report that the breaker has tripped (in the trip free position).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 81 of 92 SIMULATOR OPERATORS GUIDE EVENT 2 PRZR Level Transmitter 1-RC-LI-1461 Fail to 34%, 0-AP-53.00.

When cued by examiner, implement Trigger #1.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00.
  • If contacted, ask for SRO recommendation for performing 1-OP-RP-001, Shift Manager will call back).
  • If contacted, will take responsibility for writing the CR.

STA:

  • If contacted, will acknowledge the failure of 1-RC-LI-1461. The individual(s) contacted will also acknowledge (but not confirm/deny) any TS LCOs.
  • If asked, the STA will report that 1-RC-LI-1461 is a Reg. Guide 1.97 component. The STA will also report that review of CEP 99-0029 has been discussed with the Shift Manager.
  • If asked, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Field Operators:

Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge instrumentation failure and commence investigations and/or efforts to place the channel in trip.

Unit 2 Operator:

  • No action for this event.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 82 of 92 SIMULATOR OPERATORS GUIDE EVENT 3 Feed Flow Channel Fails High, 0-AP-53.00.

When cued by examiner, implement Trigger #3.

Operations Supervisor/Management:

  • If contacted, acknowledge feed flow channel failure. The individual(s) contacted will also acknowledge any TS LCOs.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into AP-53.00.
  • If contacted, will ask SRO for recommendation concerning performance 1-OP-RP-001. Shift Manager will call back.

STA:

  • If contacted, will acknowledge feed flow channel failure. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
  • If contacted, will take responsibility for writing the CR.
  • When asked: Failed channel is a RG 1.97 variable.
  • When asked, CEP-0029 has been reviewed and discussed with the Shift Manager. VPAP-2802 and TRM section 3.3 have been reviewed and discussed with the Shift Manager.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Field Operators:

  • Will perform actions as directed.

Maintenance/ Work Week Coordinator:

  • If contacted, will acknowledge the feed flow channel failure and contact I&C to commence preparation to place the failed channel in trip.

Unit 2:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 83 of 92 SIMULATOR OPERATORS GUIDE

  • If contacted, will acknowledge the failure of the feed flow channel.

Role-play as other individuals as needed.

EVENT 4 Loss of HPD, 1-AP-18.00.

When the Evaluator indicates Ready, Activate Trigger #5.

Operations Supervisor/Management:

  • If contacted, will acknowledge the trip of 1-SD-P-1A, and the need to ramp at 1%/minute to 75%

power.

  • If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC, the Shift Manager will direct a 1%/minute ramp rate.

STA:

  • If contacted, will acknowledge the trip of 1-SD P-1A and the need to ramp at 1%/minute to 75%

power.

  • If asked, the STA will acknowledge the need to borate and use rods (will acknowledge the team review of pre-planned reactivity plans and OP-RX-010, if performed). If asked to perform the OP-RX-010 review, the STA will state that he is not able to at this time.
  • After directed, the STA will report that VPAP-2802 has reviewed and discussed with the hift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
  • When contacted: EPIPs have been reviewed with the Shift Manager.

Maintenance/ Work Week Coordinator:

  • If contacted, will acknowledge the failure and notify electrical maintenance to investigate.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 84 of 92 SIMULATOR OPERATORS GUIDE

  • If contacted, will acknowledge the requirements to reduce reactor power.

Field Operators: (Wait three (3) minutes from direction of a local action to the report of local condition found.)

  • If contacted, the condensate polishing building operator will acknowledge the need to ramp the unit.
  • If asked, the condensate polishing building operator acknowledge bypass of the polisher.
  • When contacted, as the Service Building Operator concerning the status of 1-SD-P-1A power supply breaker, 1-EP-BKR-15B6, report that the breaker is open with a timed overcurrent drop on A phase.
  • When contacted, as the Turbine Building Operator to check the status of 1-SD-P-1A, report that there are no apparent abnormalities other than the A HPD pump has tripped and HPD tank high level divert, 1-SD-FCV-107, is diverting to the condenser.

Unit 2:

  • If contacted, will acknowledge the trip of 1-SD-P-1A and the need to ramp at 1%/minute to 75%

power.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 85 of 92 SIMULATOR OPERATORS GUIDE EVENT 5 Ramp to 75%, 0-AP-23.00.

Operations Supervisor/Management:

  • If contacted, will acknowledge Ramp to 75% required due to the loss of 1-SD-P-1A.
  • If contacted, will take responsibility for writing the CR.
  • When contacted: The Shift Manager will review EPIPs for applicability. They are not applicable.

STA:

  • If contacted, will acknowledge the impending ramp to 75% power.
  • If contacted, will take responsibility for writing the WR and CR.
  • When contacted: The STA reports that VPAP-2802 has been reviewed discussed with the Shift manager.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them. STA will acknowledge reactivity plan developed by RO/SRO.

Unit 2 Operator:

  • If notified of Ramp: Acknowledge ramp of Unit 1.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 86 of 92 SIMULATOR OPERATORS GUIDE EVENT 6 SGTL 74 gpm, A/E RM Auto Actions Fail, RCPs Trip on swap to RSST.

When the Evaluator is ready and the Blender is in AUTO, implement Trigger # 9.

Note: It would be preferable to wait until power is <80% to implement this failure to allow for ramp stabilization prior to creating RCS leak to allow the team to assess leakrate with more precision.

Operations Supervisor/Management:

  • If contacted, will acknowledge RCS leakage into the B SG. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.
  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into AP-16.00.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 87 of 92 SIMULATOR OPERATORS GUIDE STA:

  • If contacted, will acknowledge the RCS leakage into the B SG.
  • If asked to calculate the RCS leak rate, state that it is difficult to ascertain at this time, but you will continue to monitor as time permits.
  • If contacted, will take responsibility for writing the WR and CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.

Health Physics:

  • If contacted, will acknowledge B SGTL.

Role play as other individuals as needed.

Operations Supervisor/Management:

  • If contacted, will acknowledge the SGTR on B SG.
  • If contacted, will acknowledge the isolation of B SG (if informed).

Field Operators:

  • If contacted, to report abnormalities on RCPs, report no 86 devices drops apparent on RCP breakers, but the Speed Sensing Panel appears to be malfunctioning; lights blinking on and off.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 88 of 92 SIMULATOR OPERATORS GUIDE EVENT 7 SGTL becomes SGTR (710) gpm). 0-AP-16.00, E-0, E-3.

Notify Examiner when B SG NR level reaches 12%. To increase SGTL to SGTR, double click on RC2402, set DEG at 79%, 60 sec ramp, Insert.

After the SGTR implemented, Actuate Trigger 11 to fail PORV 1455C control switch.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will acknowledge entry into 1-E-0, 1-E-3.
  • If contacted, will acknowledge the SGTR on B SG.
  • If contacted, will acknowledge the isolation of B SG (if informed).

STA:

  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.

Unit Two:

  • If asked, blowdown and air ejector RM readings are [as indicated at the time].
  • If requested, acknowledge RM alarms, and perform ARP actions.
  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
  • If asked: Unit 2 RWST cross-ties are open.
  • If asked: take responsibility to notify HP of B SG PORV lifting.

Field Operators:

  • If contacted, field operators will perform valve manipulations as required:
  • 1-MS-120 - set ms_120 to zero upon request

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 89 of 92 SIMULATOR OPERATORS GUIDE

  • Acknowledge direction to place Number 1 and 2 Turbine Building Sump pumps in OFF locally, and initiate 0-OSP-PL-003, Turbine Building Sump Pump Status Verification.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 90 of 92 SIMULATOR OPERATORS GUIDE EVENT 8 PZR PORV 1-RC-PCV-1455C not open, 1-ECA-3.3.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will acknowledge entry into 1-ECA-3.3.
  • If contacted, will acknowledge the SGTR on B SG.
  • If contacted, will acknowledge the isolation of B SG (if informed).

STA:

  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.

Unit Two:

  • If asked, blowdown and air ejector RM readings are [as indicated at the time].
  • If requested, acknowledge RM alarms, and perform ARP actions.
  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.

Field Operators:

  • If contacted, field operators will perform vale manipulations as required:
  • 1-MS-120 - set ms_120 to zero upon request

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 91 of 92 SIMULATOR OPERATORS GUIDE EVENT 9 BOP Failures, 1-SI-P-1B no auto start, 1-CH-HCV-1200 A/B not close, 1-VS-MOD-103A not close, 1-MS-TV-109 and 1-DA-TV-100A/B not close.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.

Unit Two:

  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.
  • If asked, MRC differential pressure is a found.
  • If asked, Unit 2 has throttled Chilled Water flow IAW E-0, Attachment 3 guidance.

Field Operators:

  • If contacted, field operators will perform valve manipulations as required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Page 92 of 92 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge the failures and commence investigations.

HP:

  • If contacted, will acknowledge B SGTR.

STA:

  • If asked, will report that he will calculate the time to B fill, time permitting.
  • If contacted, will enter the control room and commence reviewing status trees and prepare for the transient brief (items are reported as you see them or previously reported).
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. Radiological conditions are as indicated. He will also state that containment conditions and the electrical conditions are as you see them.

Role play as other individuals as needed.

The scenario will end upon reaching Step 11 of 1-ECA-3.3 or at the lead examiners discretion.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 Facility: Surry Power Station Scenario No.: 3 Op-Test No.: 2014-001 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Time in Core Life - Middle of Life; Core Cycle - Cycle 26 Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportablility is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
  • A BAST at 8.0 W/%; Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.

Event Malf. Event Event No. No. Type* Description N - BOP 1 N/A N - SRO Deleted.

2 RC0801, I - RO Failure of Median Tave in the Low Direction, AP-53.00.

-1 Deg 3 I - BOP MS0801, TS - SRO Failure of Steam Flow Channel III Low, A SG. AP-53.00

-1 Deg C - RO 4 EL4902 TS - SRO 1J 4160V emergency Bus Off-site Power Supply Breaker Trips.

Switch Test Button on Main Turbine Control Fails causing the LP Turbine 5 R - RO O/R, TEST_IR R - SRO 1 Intercept and Reheat Stop Valve Closure. AP-23.00 Ramp to N - BOP 71% Power.

L_IIL RC04, RCS leak of 35 gpm. AP-16.00.

6 3.5% Deg C - RO TS- SRO RM0202, 7 +.1 Deg, RM0201, C - BOP Containment Particulate and Gas RM auto actions on High Alarm

+.1 Deg fail to function CA03 CA04 RC0101, 8 .6% Deg M - All SBLOCA. AP-16.00, E-0.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 SETPT 9 for Hi-Hi CLS change to 60 psia.

O/R M - All CLS_AC Hi and HI-HI CLS fail to function, requiring manual alignments of T_TRA C - BOP components, and FR-Z.1 entry.

O/R CLS_AC T_TRB

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
1) Deleted Normal Evolution.

Event #2: Median Tave Fails Low. (I - RO)

The RO will diagnose this failure due to Rod motion and alarms received. The RO will place Rod Control to manual and place charging flow to manual IAW the Immediate Actions Steps of 0-AP-53.00, Loss of Vital Instrumentation/Controls. Following a short brief, the Team will complete AP-53.00.

Verifiable Actions:

1) RO/BOP will place Rod Control in manual to stop outward rod motion.
2) RO will place charging flow in manual and maintain Pressurizer level at program.

Technical Specifications:

1) Should the SRO review Tech Specs, no items will be found.

Technical Requirements Manual/RG 1.97

1) No TRM or RG 1.97 requirements are associated with this failure.

Event #3: Steam Flow Channel III Fails Low on A SG. (I - RO, TS-SRO)

The BOP will diagnose the failure based upon alarms and indications received, place the A FRV in manual to control A SG NR level, and restore SG NR level to program IAW 0-AP-53.00, Loss of Vital Instrumentation/Controls.

The affected channel of Steam Flow will be de-selected and the A FRV returned to automatic.

Verifiable Actions:

1) The BOP will place the A FRV in manual and restore the A SG NR level to program.
2) The RO will de-select the failed channel.
3) The BOP will return the A FRV to automatic.

Technical Specifications:

SRO will Review Technical Specifications and determine:

1) Tech Spec Table 3.7-1, Item 17, Operator Action 6. With the Number of Operable Channels less than the Total Number of channels, Operation may continue provided the channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, The channel may

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 be bypassed for 12 for surveillance testing, and if the requirement cannot be met be in at least Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

2) Tech Spec Table 3.7-2, Item 1.e. High Steam flow in 2/3 steam lines coincident with Low Tavg or low steam line pressure, Operator Action 20. With the number of Operable channels less than the Total number of channels, Operation may continue provided the channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the channel may be bypassed for surveillance for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If these conditions are not satisfied in the time permitted, be in Hot Shutdown in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to < 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3) Tech Spec Table 3.7-3, Item 2a, Steam line Isolation, refers to requirements listed in 2) above.

Technical Requirements Manual/R.G. 1.97.

1) TRM - No requirements listed for this failure in section 3.3.2, Appendix R Instrumentation.
2) RG 1.97 - Attachment 1, D-19 Variable, 1 Channel per SG required.

Event #4: Loss of 1J 4160V Emergency Bus, Breaker 15J8 opens, #3 EDG Starts and Loads on 1J Bus. (C - RO, TS - SRO).

The Team will diagnose the loss of the 1J Emergency Bus and Start and Load of #3EDG on the bus based on alarms and indications received. The SRO will enter 1-AP-10.07, Loss of Unit 1 Power and proceed through the procedure until the end is reached.

Verifiable Actions:

1) BOP/RO will start the B CH pump to provide load to the #3EDG.
2) BOP/RO will secure the A and C CH pumps.
3) RO will place the B CC pump in PTL in order to re-close the J stub bus tie breaker.
4) RO will start A CC pump.

Technical Specifications:

1) The SRO will consult Tech Specs 3.16.B.2 and determine the Unit may be operated for 7 days provided the dependable alternate source can be OPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. SRO will consult with the Shift Manager concerning whether the Dependable alternate source can be Operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
2) SRO may refer to Tech Spec 3.6.I and determine AFW cross-tie clock is not required.
3) SRO will identify 6/30 clock Tech Spec 3.16, while the alignment of running charging pumps is made using 1-AP-10.07, Attachment 4.

Technical Requirements Manual / RG 1.97:

1) No TRM or RG 1.97 requirements are affected by this event. (The identification of TRM items is normally an STA function - follow-up question post-scenario is recommended at Lead Evaluator discretion.)

Event #5: #1 LP Turbine Left Intercept and Reheat Stop Valve Close, (R - RO, R - SRO, N -

BOP)

The RO/BOP will diagnose this failure based Indications received. The Team will initiate AP-53.00/AP-38.00 and determine that a power reduction to 71% is required using 0-AP-23.00, Rapid Load Reduction.

Verifiable Actions:

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3

1) RO will manipulate the CVCS system to Emergency Borate and establish a continuous boration to control RCS Tave during the Turbine Ramp.
2) RO will use control rods to adjust delta flux and assist in RCS Tave control.
3) BOP will operate Turbine controls to reduce turbine load.

Technical Specifications/TRM/RG-1.97:

1) None associated with this Failure.

Event #6: RCS leak of 35 gpm. (C - RO, TS-SRO)

Following completion of the ramp, the RCS leak will be initiated. The RO will perform 1-AP-16.00, Excessive RCS Leakage, Immediate Actions to quantify the leakage.

Verifiable Actions:

1) The RO will isolate letdown and control charging flow in manual to quantify RCS leakage.

Technical Specifications:

1) The SRO should consult Tech Specs Section 3.1.C, RCS leakage, and identify that RCS leakage is in excess of the allowed maximum and enter a second 6/30 clock to be in HSD/CSD.

Event #7: Failure of RM-159/160 auto actions. (C - BOP)

As the Team is responding to the RCS leak, RM-159/160 for containment Particulate and Gas Rad Monitors will alarm. The BOP will respond using the associated ARPs and determine that the auto functions for these RMs have not occurred. The BOP will follow the ARP guidance and swap containment Instrument Air compressor suction to the external source.

Verifiable Actions:

1) The BOP will swap containment instrument air compressors to outside suction by closing 1-IA-TV-101A and 1-IA-TV-101B.

Technical Specifications:

1) The SRO may consult Tech Specs and find no requirement for this failure.

Event #8: SBLOCA. (M - ALL)

The RO will diagnose the increase in RCS leakage due to the alarms and indications received, and re-perform the Immediate Actions of 1-AP-16.00. When leakage is determined to be greater than the capacity of a single CH pump, The RO will trip the reactor, perform the Immediate Actions of E-0, and manually safety inject on Step 4.

Due to the size of the RCS leak, several minutes will elapse before RCP trip criteria are met following the reactor trip.

Verifiable Actions:

1) RO will raise charging flow and determine leakage is beyond the capacity of single charging pump.
2) RO will trip the reactor and perform the Immediate Action Steps of E-0, including manual Safety Injection actuation.

Critical Task:

CT-1: WOG E-1C: Trip all RCPs so that CET temperatures do not become superheated when forced circulation in RCS stops; Trip all

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 RCPs within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).

Event #9: Failure of Hi and Hi-Hi CLS auto and manual actuation The RO and SRO will continue with E-0 actions; the BOP will be assigned to perform Attachments 1, 2, and 3 of E-0. Upon transition to 1-E-1, Loss of Reactor or Secondary Coolant, containment pressure will have increased to the Hi and HI-HI CLS setpoint (~13 minutes following Event initiation), and CLS Train A and Train B pushbuttons overridden OFF will force entry into FR-Z.1 to start Containment Depressurization equipment.

Verifiable Actions:

1) BOP will reset SI, block SI signals when conditions permit, secure one of the three running CH pumps, and secure one of the two running LHSI pumps.
2) RO will throttle AFW to the SGs as directed in E-0.
3) RO will operate the CS pumps and valves to align CS to containment for depressurization in FR-Z.1, Response to High Containment Pressure.
4) BOP will continue manual alignment of valves for Hi and Hi-Hi CLS failure in Attachment 4 of E-0 following transition from FR-Z.1 to 1-E-1.

Critical Task:

CT-2: WOG E-0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (red-path) challenge develops to the CSF. Establish CS flow from at least one CS pump before containment pressure exceeds 60 psia AND at least one RS train before RMT.

Scenario should continue until Lead Evaluator Cue or Step 18 of 1-E-1.

Follow-up Classification: Site Area Emergency FS-1.1.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 Initial Conditions: IC #1 100%, MOL - Cycle 26. The unit has been at 100% power for > 30 days Pre-load malfunctions: (Trigger 30s) o Override Hi CLS Act pushbutton - TRA o Override HI CLS Act pushbutton - TRB o AC_SMS_MODE, OFF, AAC DG LOCAL MODE SWITCH POSITION o RS0901, TRN A HI CLS FAILS TO ACTIVATE o RS0902, TRN B HI CLS FAILS TO ACTIVATE Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

. Unit 1 is at 100% power. All systems and crossties are operable with the following exception:

o AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Turnover:

Unit 1 is at 100% power. All systems and crossties are operable with the following exception:

AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. . IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

  • A BAST 8.0 w/%.

Event Malf. #s Severity Instructor Notes and Required Feedback 1 N/A Deleted 2 RC0801 -1 Deg Failure of Median Tave in the Low Direction, AP-53.00.

3 MS0801 -1 Deg Failure of Steam Flow Channel III Low, A SG. AP-53.00 4 EL4902 TRUE 1J 4160V emergency Bus Off-site Power Supply Breaker Trips.

Switch 5 O/R, Test Button on Main Turbine Control Fails causing the LP Turbine 1 ON TEST_IRL Intercept and Reheat Stop Valve Closure. AP-23.00 Ramp to 71% Power.

_IIL 6 3.5%

RC04 Deg RCS leak of 35 gpm. AP-16.00.

RM0202 +.1 Deg

7. RM0201, +.1 Deg Containment Particulate and Gas RM auto actions on High Alarm fail to CA03 TRUE function.

CA04 TRUE

.6 DEG, 8 RC0101 600 Sec SBLOCA Ramp

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #3 SETPT for 9 Hi-Hi CLS 60 psia O/R CLS_ACT ACTIVE

_TRA Hi and HI-HI CLS fail to function, requiring manual alignments of components, and FR-Z.1 entry.

O/R CLS_ACT ACTIVE

_TRB Scenario Objectives:

A. Deleted.

B. Given a failure of Median Tave in the Low Direction, respond IAW AP-53.00.

C. Given a failure of the selected Steam Flow channel on the A SG, respond IAW AP-53.00 to take manual control of the A FRV, control A SG NR level and return the A FRV to automatic.

D. Given the trip of the off-site power supply breaker to the 1J 4160V Bus and the subsequent start and load of #3 EDG on the bus, respond IAW AP-10.07 to restart/verify proper loads on the 1J bus.

E. Given the malfunction of the 1RL/1LL test pushbutton, respond IAW AP-53.00, AP-38.00, and AP-23.00 to ramp the Unit to 71 % power.

F. Given an RCS leak of 35 gpm, respond IAW AP-16.00 to quantify the leakrate.

G. Given a containment Gas High RM Alarm, respond IAW ARP to verify/perform the associated automatic actions.

H. Given a SBLOCA inside containment with the failure of Hi-Hi-CLS to actuate, respond IAW E-0 and E-1 to respond to the RCS transient; and restore containment depressurization equipment IAW FR-Z.1.

SHIFT TURNOVER INFORMATION OPERATING PLAN:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1.

The last shift performed two 35 gallon alt dilutions followed by a manual makeup for training.

A BAST at 8.0 W/%. .

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 1 Page 9 of 103 Event

Description:

Swap Running EH Pumps, 1-OP-EH-001, Section 5.6.

Cue: When team ready.

Time Position Applicants Action or Behavior EVENT #1 DELETED.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 10 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

Note: An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.

The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.

A facility representative will be present for consultation with the Evaluation Team, as needed.

Time Position Applicants Action or Behavior Diagnoses failure of median Tave with the following indications/alarms:

Team Alarms:

  • 1H-A4, T AVG > < T REF DEVIATION
  • 1G-F8, ROD BANK D WITHDRAW
  • 1C-C8, PRZR HIGH LEVEL HEATERS ON Indications:
  • Median Tave (recorder and indicator) off-scale low
  • Individual Loop Taves indicating NORMAL
  • Control Rods stepping OUT and reactor power decreasing SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS RO [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL RO identifies individual loop Tave indications are normal

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 11 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION RO takes manual control of the control rods to stop the outward rod motion and also takes manual control of pressurizer level control (1-CH-FCV-1122) to maintain pressurizer level at program.

It should be noted that charging might not be placed in manual until procedurally directed.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

SRO Directs BOP to perform Annunciator Response Procedure 1G-F8.

Completes Brief and continues with AP-53.00.

NOTE: 1G-F8 response located at the end of this section.

SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

  • Median Tave, Step 9 RO Identify that Median Tave has failed LOW.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 12 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

SRO Caution prior to step 9:

CAUTION: Delta flux must be monitored and maintained within band if rods have moved.

Note Prior to Step 9:

NOTE: Depending on the instrumentation failure, the TAVE input to the Steam Dumps may be invalid, causing the Steam Dumps to stay open longer or never open at all.

SRO 9. CHECK LOOP/MEDIAN T/Tave - NORMAL a) Median Tave - NORMAL a) RNO - Do the following:

1) Place ROD CONT MODE SEL switch in MANUAL, as required.

RO will report that Rod Control is already in manual.

2) Take manual control of charging, as necessary to maintain pressurizer level at program.

RO will report that charging flow is in manual or will place charging flow in manual.

3) Refer to Attachment 4 (Describes Tave control system)
4) If no other instrumentation failure exists, then go to step 13.

Goes to Step 13 0-AP-53.00 SRO 13. CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001 RO Checks 1-OPT-RX-001, Attachment 4, and determines that the Calorimetric program is unaffected.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 13 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE SRO directs STA to review Reg. Guide 1.97. The STA will report that Median Tave is not a Reg. Guide 1.97 component.

13. RNO - GO TO Step 16 SRO 16. Review the following:
  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA reports that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

SRO 17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS RO Reports no other instrument failure exists.

GOES TO STEP 19 SRO 19. PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC

- END -

Note: If Control Rods stepped out greater than 230 steps, the team will perform ARP 1G-F8. 1G-F8 Actions are contained on the next two pages

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 14 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

1G-F8 (Rod Bank D Withdrawal)

BOP 1. CHECK ALARM - ROD DEMAND POSITION GREATER THAN OR EQUAL TO 228 STEPS ON CONTROL BANK D - GP 1 DEMAND POSITION.

Identifies that Bank D is greater than 230 steps.

1G-F8 (Rod Bank D Withdrawal)

BOP

2. PUT ROD CONTROL MODE SEL SWITCH IN MANUAL.

Verifies that Rod Control is in Manual.

1G-F8 (Rod Bank D Withdrawal)

BOP

3. VERIFY ROD MOTION - STOPPED 1G-F8 (Rod Bank D Withdrawal)
4. CHECK BOTH CONTROL BANK D STEP COUNTERS - LESS THAN OR EQUAL TO 230 STEPS.

If less than 230 steps proceed to Step 5.

RNO -

a) Step rods out to make both Bank D Step Counters equal. (Group step counters must be equalized by stepping out only, to prevent Rod Group Sequence Error).

Steps Rods out as needed to equalize group step counters.

b) Reset Bank D Step Counters to 230 steps.

Uses a stylus to reset the Bank D Step Counters to 230 steps.

1G-F8 (Rod Bank D Withdrawal)

BOP NOTE:

Rods may have to be stepped in as many as two steps below the fully withdrawn position to clear Annunciator 1G-F8.

5. STEP CONTROL BANK D RODS IN AS NECESSARY TO CLEAR 1G-F8, ROD BANK D WITHDRAW.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 2 Page 15 of 103 Event

Description:

Failure of Median Tave in the Low Direction, 0-AP-53.00.

Cue: By Examiner.

BOP 1G-F8 (Rod Bank D Withdrawal)

6. POSITION CONTROL BANK D RODS AS DETERMINED BY SHIFT SUPERVISION 1G-F8 (Rod Bank D Withdrawal)

BOP NOTE:

Both group step counters for Control Bank D should be the same before performing Step 7.

7. LOCALLY CHECK THE BANK OVERLAP COUNTER - AT 384 PLUS CURRENT CONTROL BANK D DEMAND POSITION.

Contacts a field operator to determine the bank overlap counter.

384 + 228 = 612 Field operator will report bank overlap position as indicated on the simulator.

1G-F8 (Rod Bank D Withdrawal)

BOP

8. NOTIFY SHIFT SUPERVISION END OF EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 16 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior Diagnoses failure 1-MS-FT-1474 with the following indications/alarms:

BOP Alarms:

Indications:

  • Step decrease in 1A SG Steam Flow indication CH-III
  • Decreasing level on A SG.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS BOP [1] VERIFY REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies Channel IV indication for steam flow is NORMAL.

BOP [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of A SG feed reg valve and increases demand (FF >

SF) to restore level to program.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 17 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

Note: Based on the feed flow > steam flow mismatch established by the BOP, Calorimetric power may exceed 100% during restoration of A SG NR level to program.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

SG Steam Flow, Step 7 BOP States A Steam Flow affected.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 18 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.

SRO 7. CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS -

NORMAL

  • Steam Pressure BOP
  • Steam Flow
  • Feed Flow

BOP Step 7. RNO IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level BOP Control system has failed, THEN do the following:

a) Place the associated Feed Reg Valve in MANUAL.

RO Verifies A SG MFRV controller, 1-FW-FCV-1478, in manual b) Control SG level at program level (44%, a band will be given).

BOP Verifies A SG NR level is returning to program level.

c) Select the redundant channel for affected SG(s)

RO Selects Channel IV Steam Flow for A SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV).

d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.

BOP Places A SG FRV controller, 1-FW-FCV-1478, in automatic control

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 19 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

SRO Step 7. RNO (Continued)

Perform follow-up actions:

a) Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.

b) Refer to the following Tech Spec 3.7 items:

  • Table 3.7-1, 12 and 17
  • Table 3.7-2, 1.c, 1.e, and 3.a
  • Table 3.7-3, 2.a, and 3.a Determines Table 3.7-1 item 17, 3.7-2 item 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).

c) Refer to Attachment 1.

d) IF no other instrumentation failure exists, THEN GO TO Step 13.

SRO 13. Review OPT-RX-001, Rx Power Calorimetric using PCS computer program, Attachment 4, to determine operability of calorimetric and need to perform OPT-RX-007, Shift Average Power Calculation.

SRO/RO determines that OPT-RX-001 is NOT impacted and OPT-RX-007 will NOT need to be performed.

If it appears that the SRO/RO will take action to perform 1-OPT-RX-007, the Unit 2 Operator will state that he will perform 1-OPT-RX-007.

Note: Lead Evaluator must concur with Unit 2 action to perform 1-OPT-RX-007.

SRO 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 14 if not Reg. Guide 1.97)

SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-MS-FT-1474 is a Reg. Guide 1.97 component.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 3 Page 20 of 103 Event description: Steam Flow Channel III Fail Low, 0-AP-53.00.

Cue: By Examiner.

SRO 15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report review of CEP 99-0029 is complete and has been reviewed with the Shift Manager.

[CEP 99-0029 requires one channel of steam flow indication per SG, with channel available, no further action is required.]

SRO 16. Review the following:

  • TS 3.7 Determines Table 3.7-1 item 17, 3.7-2 item 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).
  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

SRO 17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS BOP Reports no additional failure exists SRO GOES TO Step 19 SRO 19. PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC

- END EVENT #3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 21 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 1-AP-10.07 TEAM Diagnose the failure based on the following:

Alarms:

1K-B8, UPS SYSTEM 1B TROUBLE 1K-D5, CC PP 1B IN LOCAL CONTROL OR OL TRIP 1K-E7, CC PPS DISCH HDR LO PRESS 1B-G5, INST AIR DRYER TROUBLE Indications:

  1. 3 EDG Start and Load on 1J 4160 V Bus.

1-CC-P-1B GREEN and AMBER Breaker Indication Lights LIT.

1-AP-10.07 SRO SRO will hold a Transient Brief and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Directs the BOP to review ARPs for Lit annunciators, SRO/RO will continue with 1-AP-10.07.

Directs RO/BOP to contact Service Building Operator to check local status of Breaker 15 J8.

Completes Brief and continues with AP-10.07.

Step 1, 1-AP-10.07 SRO NOTE:

  • If both units are affected, local actions should be coordinated.
  • The AAC Diesel Generator will automatically start if an undervoltage occurs on Transfer Buses D and F.
  • With Degraded Voltage or Undervoltage on 2J Bus, or a loss of Unit 2B DC Bus, Breaker 15J3 will not close automatically, except with a valid Unit 1 SI signal.
1. CHECK UNIT - BLACKOUT HAS OCCURRED
  • Transfer Buses D and F - DEENERGIZED AND
  • All Station Service Buses - DEENERGIZED RO Reports Blackout has not occurred.

SRO GOES TO Step 39.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 22 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 39, 1-AP-10.07 SRO 39 CHECK THE FOLLOWING BREAKERS - ANY OPEN:

  • 15J8 RO Reports Breaker 15J8 Open.

Step 40, 1-AP-10.07 SRO 40 CHECK 4160V EMERGENCY BUSES - BOTH ENERGIZED RO Reports both Emergency Buses Energized.

Step 41, 1-AP-10.07 SRO 41 CHECK SI OR HI HI CLS - NOT ACTUATED RO Reports SI or HI HI CLS NOT Actuated Step 42, 1-AP-10.07 SRO CAUTION: To prevent overload of EDG 1, the UV trip of 1-CH-P-1A should NOT be reset if 1-CH-P-1C is running on the normal feeder AND the UV trip of 1-CH-P-1C (Normal) should NOT be reset if 1-CH-P-1A is running.

NOTE: A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading..

NOTE: The CHG pumps powered from the 1H Bus receive an auto-start signal when the 1J Bus is deenergized.

42 INITIATE ATTACHMENT 4 TO ALIGN EMERGENCY BUS LOADS TO PREVENT EDG OVERLOADING SRO Directs BOP to perform Attachment 4 of 1-AP-10.07.

Note: Attachment 4 actions listed at the end of this section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 23 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 43, 1-AP-10.07 SRO 43 GO TO STEP 45 Step 45, 1-AP-10.07 SRO NOTE: At least one method of communications should be established before commencing local actions.

45 CHECK COMMUNICATIONS CAPABILITY:

  • Gaitronics OR
  • Station Radios RO Reports Gaitronics and / or Station Radios Available.

Step 46, 1-AP-10.07 SRO 46 CHECK EDG - HAS REENERGIZED AFFECTED EMERGENCY BUS

  • 15H3 - CLOSED OR
  • 15J3 - CLOSED RO Reports 15J3 Breaker closed.

Step 47, 1-AP-10.07 SRO 47 RESTORE EMERGENCY BUS STUB BUS:

a) Put CC PUMP control switch in PTL RO Places 1-CC-P-1B control switch in PTL.

b) Put RHR PUMP control switch in PTL RO Checks 1-RH-P-1B in PTL.

c) Locally close Stub Bus feeder breakers on energized Emergency Buses

  • 15H9 SRO Directs RO to contact Service Building Operator to Close 15J9.

RO Contacts Service Building Operator to Close breaker 15J9 When local report of Breaker 15J9 closed, RO holds Focus Brief to inform the Team, and checks Annunciator 1K-H4 Clear.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 24 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 48, 1-AP-10.07 SRO CAUTION:

  • When the EDG is the only source of power to an Emergency Bus, the associated Component Cooling Pump should NOT be in service if a HI-HI CLS is in progress.
  • Restrictions on CC pump operation do NOT apply below RCS temperature of 350°F.

48 CHECK CC PUMPS - AT LEAST ONE RUNNING RO Reports No CC Pumps running on Unit 1.

SRO Holds Team brief to discuss the start of 1-CC-P-1A. Since CC system is cross-tied and the CC header is pressurized, throttling the CC pump discharge valve prior to start is unnecessary. Team will concur and the brief closed.

SRO Direct RO to Start 1-CC-P-1A.

RO Makes Gaitronics Announcement and Starts 1-CC-P-1A.

Step 49, 1-AP-10.07 SRO 49 PLACE STANDBY CC PUMP IN AUTO-AFTER-STOP SRO Direct RO to Place 1-CC-P-1B in Auto after Stop.

RO Places 1-CC-P-1B in AUTO.

Evaluator Note: At Evaluator discretion, the next Event (Event 5) may be initiated at this time.

Step 50, 1-AP-10.07 SRO 50 CHECK RHR - WAS IN SERVICE RO Reports RHR NOT in service.

SRO GOES TO Step 52.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 25 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 52, 1-AP-10.07 SRO CAUTION:

  • If a HI-HI CLS has occurred on Unit 1, 1-FC-P-1A must not be started on EDG 1 if 1-CS-P-1A is running.
  • If a HI-HI CLS has occurred on Unit 2, 1-FC-P-1B must not be started on EDG 2 if 2-CS-P-1A is running.

NOTE:

52 CHECK SFP COOLING - EITHER PUMP RUNNING RO Reports 1-FC-P-1B Running Step 53, 1-AP-10.07 SRO 53 CHECK INTAKE CANAL LEVEL - STABLE OR INCREASING RO Reports Intake Canal Level 29 feet and Stable.

Step 54, 1-AP-10.07 SRO NOTE: If two CHG pump CC pumps or two CHG pump SW pumps are running, one pump should be secured and placed in AUTO.

54 CHECK CHG PUMP AUXILIARIES:

  • CHG pump CC pump - RUNNING
  • CHG pump SW pump - RUNNING RO Reports 1-CC-P-2A and 1-SW-P-10A Running.

Step 55, 1-AP-10.07 SRO 55 CHECK SEMI-VITAL BUS - POWER HAS BEEN INTERRUPTED RO Reports Semi-Vital Bus Power has not been interrupted.

SRO GOES TO Step 57 Step 57, 1-AP-10.07 SRO 57 CHECK BOTH PRZR PORV BLOCK VALVES - ENERGIZED RO Reports Both PRZR Block Valves energized

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 26 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 58, 1-AP-10.07 SRO 58 CHECK CC TO EXCESS LETDOWN HX - NOT TRIPPED

  • FI-CC-109 RO/BOP Reports FI-CC-109 Flow is Approximately 160 gpm and Stable.

Step 59, 1-AP-10.07 SRO 59 CHECK IA SYSTEM ANNUNCIATORS - NOT LIT:

  • 1B-G5, INST AIR DRYER TRBL

SRO Directs BOP to review the ARPs for the lit annunciators.

BOP Directs Turbine Building Operator to investigate cause for alarms in IA System.

Step 60, 1-AP-10.07 SRO 60 CHECK UNIT CONDITIONS a) PRZR level - STABLE b) PRZR pressure - STABLE c) RCS TAVE - STABLE RO Reports Parameter normal with no abnormal trends.

Step 61, 1-AP-10.07 SRO 61 CHECK VENTILATION FANS - OPERATING

  • Auxiliary BLDG Central
  • Safeguards BOP Reports Auxiliary Building Central and Safeguards fans operating normally

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 27 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 62, 1-AP-10.07 NOTE: Any MCR Chiller that was operating prior to the loss of power will have tripped and the compressor will not automatically restart. The Chiller must be shutdown and then restarted IAW 0-OP-VS-006, Control Room and Relay Room Ventilation System.

SRO 62 CHECK THE FOLLOWING MCR VENTILATION EQUIPMENT -

OPERATING:

  • One Control Room Chiller (Two Control Room Chillers if SI initiated on either unit AND any MCR or ESGR temperature indicator greater than 84°F)

BOP Reports 1-VS-E-4C and 1-VS-E-4E Running.

SRO

  • One Unit 1 Control Room AHU
  • One Unit 2 Control Room AHU

Step 63, 1-AP-10.07 SRO 63 CHECK CRDM FANS - THREE RUNNING BOP Reports Three CRDM Fans Running Step 64, 1-AP-10.07 SRO 64 CHECK CONTAINMENT AIR RECIRC FANS - THREE RUNNING BOP Reports three fans running.

Step 65, 1-AP-10.07 SRO CAUTION:

  • If a HI-HI CLS has occurred on Unit 1, 1-FC-P-1A must not be started on EDG 1 if 1-CS-P-1A is running.
  • If a HI-HI CLS has occurred on Unit 2, 1-FC-P-1B must not be started on EDG 2 if 2-CS-P-1A is running.

NOTE:

65 CHECK SFP COOLING - EITHER PUMP RUNNING RO Reports 1-FC-P-1B Running

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 28 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 66, 1-AP-10.07 SRO 66 CHECK AFW MOVS - BOTH TRAINS ENERGIZED BOP Reports all AFW MOVs energized.

Step 67, 1-AP-10.07 SRO 67 CHECK BORIC ACID ALIGNMENT:

  • One Tank in service
  • One BATP in service BOP Reports 1-CH-P-2A running and aligned to the A BAST.

Step 68, 1-AP-10.07 SRO 68 CHECK CVCS HEAT TRACING PRIMARY AND BACKUP PANELS - ALL ENERGIZED

  • Primary panels 2A1, 2A2, and 2A3 - powered from 1H 480V Bus RO Reports heat tracing panels energized.

Step 69,1-AP-10.07 NOTE: The N-16 and MGPI Radiation Monitors are powered from Breaker 1H1 4B2 or 2H1-1-2D-2 depending on the position of throw-over switch 1-EP-TRS-DB-101 located near MCC 1H1-1.

SRO 69 CHECK RADIATION MONITORS - OPERABLE

  • No sample pump deenergized
  • No flow faults
  • No monitors deenergized
  • Annunciator 0-RMA-C5, PROCESS VENT RAD MON TRBL - NOT LIT
  • Annunciator 0-RMA-D5, VENT STACK #2 RAD MON TRBL - NOT LIT BOP Reports sample pumps energized, No flow faults, No monitors deenergized.

Reports Annunciators 1A-C3, RMA-C5, RMA-D5 - not LIT.

Step 70, 1-AP-10.07 NOTE: The CTMT Particulate and Gas Rad Monitor skids are powered from 1MR1A, Breaker 43, which is supplied from 480V MCC 1C1-2. These monitors are required to comply with Tech Spec 3.1.C.1.

SRO 70 LOCALLY CHECK CTMT PARTICULATE AND GAS RAD MONITOR -

OPERABLE (SKID/ SAMPLE PUMP ENERGIZED) (IF MCC 1C1-2 CONFIRMED TO BE DEENERGIZED, NO NEED TO CHECK LOCALLY)

SRO Directs BOP to dispatch Aux Building Operator to check local RM skid.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 29 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 71, 1-AP-10.07 SRO 71. ___ CHECK SW SUPPLY MOVS - ALL ENERGIZED RO Reports SW MOVS energized.

Step 72, 1-AP-10.07 SRO 72 CHECK TECH SPEC LCOS:

  • Tech Spec 3.16 SRO The SRO will consult Tech Specs 3.16.B.2 and determine the Unit may be operated for 7 days provided the dependable alternate source can be OPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. SRO will consult with the Shift Manager concerning whether the Dependable alternate source can be Operable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SRO may refer to Tech Spec 3.6.I and determine AFW cross-tie clock is not in effect.

SRO will identify 6/30 clock Tech Spec 3.16, while the alignment of running charging pumps is made using 1-AP-10.07, Attachment 4.

SRO will brief the Team on Tech Spec requirements.

Step 73, 1-AP-10.07 CAUTION: If any EDG has operated below 570 KW for three days, additional loading will be required to prevent exhaust system souping. Refer to Attachments 7 and 8.

SRO 73 CHECK 4160V EMERGENCY BUS 1H - ENERGIZED FROM OFFSITE POWER

  • 15F1 - CLOSED
  • 15H8 - CLOSED RO/BOP Reports 15F1 and 15H8 breakers closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 30 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 74, 1-AP-10.07 CAUTION:

  • Shift Supervision should direct the loading of EDG 3 to 1J or 2J Emergency Bus to best support plant recovery.
  • If any EDG has operated below 570 KW for three days, additional loading will be required to prevent exhaust system souping. Refer to Attachments 7 and 8.

NOTE:

  • The RSS transformer cooling fans, heaters, and load tap changer controls are powered from 1J1-1-3B2 or 2J1-1-4A2 depending on position of the throwover switch near 1-SA-TK-2 in Unit 1 Turbine BLDG basement. The switch shall be aligned to an energized bus.
  • Until the throwover switch is aligned to an energized bus, the RSST load tap changers are inoperable. Tech Spec 3.16.B.2 should be reviewed for required actions.

SRO 74 CHECK AC EMERGENCY BUS 1J - ENERGIZED FROM OFFSITE POWER

  • 15D1 - CLOSED
  • 15J8 - CLOSED RO/BOP Reports breaker 15D1 closed, breaker 15J8 Open.

Step 74, RNO Do the following:

a) IF 1J Bus energized from EDG 3, THEN do the following:

1) Monitor EDG 3 parameters IAW Attachment 8.

SRO SRO Directs RO/BOP to contact Service Building Operator to monitor #3 EDG using Attachment 8 of 1-AP-10.07.

2) Continue efforts to restore normal Emergency Bus power.
3) WHEN cause of power loss identified and corrected, THEN initiate 0-AP-10.08, STATION POWER RESTORATION.

Step 75, 1-AP-10.07 SRO 75. ___ CHECK ANY STATION SERVICE BUS - DEENERGIZED:

  • 15A1 and 15A2 - OPEN OR
  • 15B1 and 15B2 - OPEN OR
  • 15C1 and 15C2 - OPEN BOP Reports All Station Service Buses energized.

SRO Step 75, RNO IF ALL 480V Station Service Buses are energized, THEN GO TO Step 97.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 31 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 97, 1-AP-10.07 SRO 97 NOTIFY THE FOLLOWING:

  • OMOC
  • Electrical Foreman SRO Notifies Shift Manager that 1-AP-10.07 complete and request notification to OMOC, STA, and Electrical Foreman be made.

Attachment 4 of 1-AP-10.07 on next page.

END EVENT #4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 32 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Time Position Applicants Action or Behavior Step 1, Attachment 4, 1-AP-10.07 BOP CAUTION: An EDG can NOT initially be loaded to greater than 1300 KW prior to an SI or HI HI CLS, with the exception of loads that will trip when a HI HI CLS occurs, or loads which are running yet assumed to start on a HI HI CLS.

CAUTION: Total EDG load shall not exceed 2750 KW.

NOTE:

  • The purpose of this Attachment is to limit EDG loading so that a subsequent HI HI CLS actuation will not overload the EDG.
  • EDG load must be monitored closely during pump operations.
  • A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading.

BOP

1. IF EDG 1 is the sole source of power to Emergency Bus 1H, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.

Identifies #1 EDG NOT the sole source to 1H Emergency Bus and GOES TO Step 2.

Step 2, Attachment 4, 1-AP-10.07 BOP NOTE: A 6/30 hour TS 3.0.1 LCO is in effect until one CHG pump is running on an Emergency Bus supplied by an EDG, AND the non-running CHG pump is incapable of auto-start (locked-out or in PTL). This Tech Spec LCO is entered due to an inoperable Emergency Bus due to EDG loading.

Notifies SRO of 6/30 hour TS 3.16 clock in effect until 1-CH-P-1B running on #3 EDG.

BOP

2. IF EDG 3 is the sole source of power to Emergency Bus 1J, THEN do the following to limit the amount of instantaneous loading that could occur in the event of a HI HI CLS.
a. Check running or start 1-CH-P-1B or 1-CH-P-1C on Emergency Bus 1J IAW Shift Supervision direction.

BOP Starts 1-CH-P-1B with concurrence of SRO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 33 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 2, Attachment 4, 1-AP-10.07 BOP b. IF a CHG pump can NOT be started on Emergency Bus 1J, THEN do the following. Otherwise, enter N/A.

Enters N/A for substeps b.1, b.2, and b.3.

c. Check or place the remaining CHG pump supplied from Emergency Bus 1J in PTL.

Identifies 1-CH-P-1C (Alternate) in PTL.

d. IF Emergency Bus 1H is supplied by offsite power, and 1-CH-P-1A or 1-CH-P-1C is running, THEN stop CHG pump(s) supplied from Emergency Bus 1H and place in Auto.

RO/BOP Confer with SRO and secures 1-CH-P-1A and 1-CH-P-1C.

e. Determine Emergency Bus 1J load limit IAW the following equation, where (x) equals the total of the KW ratings of all RUNNING equipment from the table below.
  • ___________ + 1300 KW = _________________

(x) EDG Load Limit BOP BOP will write 100 in the (x) blank, and write 1400 in the EDG Load Limit blank.

f. IF existing EDG load is greater than the limit calculated in Substep e.

above, THEN reduce EDG load to less than or equal to the calculated load.

BOP will identify ~950kW load on #3 EDG.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 4 Page 34 of 103 Event

Description:

1J 4160V emergency bus off-site power supply breaker trips, 1-AP-10.07.

Cue: By Evaluator.

Step 3. Attachment 4, 1-AP-10.07 BOP 3. Notify Auxiliary Building Operator to increase monitoring of CHG pump lube oil temperature.

BOP contacts the Aux Building Operator to monitor CHG pump lube oil temperature Step 4, Attachment 4, 1-AP-10.07 BOP 4. Increasing monitoring of CHG pump bearing temperatures using the Plant Computer system.

BOP will monitor CHG pump bearing temperatures using the Plant Computer system.

BOP returns the Attachment to the SRO and provides a short brief of Attachment results.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 35 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

Time Position Applicants Action or Behavior Team Identify the failure of the Test Button based on the following:

Alarms:

PCS Alarm for MSR Indications:

~ 9 MW step decrease indicated on MW Videographic Recorder.

0.2 °F increase in RCS Tave Test 1RL 1IL Button on turbine control panel 1RL CLOSED indicating light LIT on turbine control panel 1IL CLOSED indicating light LIT on turbine control panel.

Note: Team may directly enter 1-AP-38.00 (see page 39).

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS NOTE: SRO may directly enter AP-38.00, MAIN STEAM SYSTEM CONTROL MALFUNCTION. See Page 39.

BOP [1] VERIFY REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies Valve Position Indications are NORMAL.

BOP [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP Identifies no controls need to be placed in Manual.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 36 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

Turbine Valve Position, Step 10 BOP Reports #1 LP Turbine Left Intercept and Reheat Stop Valves are closed.

CAUTION: If Reactor power has been affected by a secondary transient, Turbine adjustment may be needed to control Tave.

SRO 10. ___ CHECK STEAM SYSTEM CONTROLS - NORMAL

  • Turbine Controls
  • Turbine Valve Positions
  • Turbine Monitoring Lights BOP Reports Turbine Valve positions are abnormal.

SRO Initiates AP-38.00

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 37 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

Time Position Applicants Action or Behavior Step 1, 1-AP-38.00 SRO 1 CHECK STEAM DUMP VALVES - CLOSED BOP Reports Steam Dump Valves closed / normal.

Step 2, 1-AP-38.00 SRO 2 CHECK SG PORVS - CLOSED BOP Reports SG PORVs closed Step 3, 1-AP-38.00 SRO 3 CHECK THE FOLLOWING CONDITIONS:

  • Reactor power - LESS THAN OR EQUAL TO 100%
  • Turbine load - NORMAL BOP Reports reactor power < 100%

RO Reports Turbine Load NOT Normal SRO Stabilize Reactor power and Turbine load less than 100% using Attachment 2.

NOTE: No Actions required in Attachment 2 for this event.

Step 4, 1-AP-38.00 NOTE: The power reductions required by Step 4 are intended for failures causing full or partial closure of a control valve, or if valve closure is required for maintenance.

SRO 4 CHECK MAIN TURBINE AND MSR STEAM CONTROL VALVES:

a) MSR Steam supply MOVs and FCVs - NORMAL BOP Report MSR MOVs and FCVs normal.

b) Turbine Governor Valves and Stop Valves - NORMAL BOP Report Turbine GVs and SVs normal.

c) Reheat Stop and Intercept Valves - NORMAL BOP Report Reheat Stop and Intercept Valves ABNORMAL RNO c) Reduce Reactor power to less or equal to 71% IAW 0-AP-23.00, RAPID LOAD REDUCTION, OR 1-OP-TM-005, UNIT RAMPING OPERATIONS.

SRO INITIATES 0-AP-23.00 to reduce load to less than 71%.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 38 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

RO Reactivity control during AP-23.00 Ramp:

146 gallons of Boric Acid needed to reduce power to 71%. 50 gallons added during Emergency Boration, leaving 96 gallons to be added using normal boration at an average rate of 5.8 gpm. Control Bank D rod height at end of ramp 197 Steps.

Gallons of PG to be added to stabilize at end of ramp 1957.

SRO Completes Brief and continues with AP-23.00.

EVALUATOR NOTE: RO Emergency borates for 25 seconds which corresponds to

~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.

SRO Caution Prior to Step 1:

  • Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.

Notes Prior to Step 1:

  • Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
  • When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
  • Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
  • The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
  • For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.

0-AP-23.00 RO 1. TURN ON ALL PRZR HEATERS

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 39 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:

BOP a) Verify turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.

RO b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5°F.

SRO/BOP c) Verify or place turbine in IMP IN or IMP OUT as determined by Shift Supervision The SRO can choose IMP IN or IMP OUT.

BOP d) Adjust SETTER to desired power level e) Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute) f) Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) g) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.

SRO 3. CHECK EMERGENCY BORATION - REQUIRED The team may decide to emergency borate after the ramp has progressed to the point that Tave and Tref are matched (or close).

SRO Note Prior to Step 4:

  • Step 4 or Step 5 may be performed repeatedly to maintain Tave and Tref matched, Flux in band, and control rod position above the LO-LO insertion limit.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 40 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

0-AP-23.00 RO 4. PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:

a) Verify or raise CHG flow to greater than 75 gpm b) Transfer the in-service BATP to FAST c) Open ( )-CH-MOV-( )350 (~25 seconds) d) Monitor EMRG BORATE FLOW

  • ( )-CH-FI-( )110 e) After required emergency boration, perform the following:
1) Close ( )-CH-MOV-( )350
2) Transfer the in-service BATP to AUTO
3) Restore Charging flow control to normal RO 5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS IAW ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.

SRO Notes Prior to Step 6:

  • If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
  • RCS Tave must be maintained less than or equal to 577°F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
  • I & C should be contacted to provide assistance with adjusting IRPIs.

RO 6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG RO *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.

BOP 8. MONITOR STEAM DUMPS FOR PROPER OPERATION

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 41 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

0-AP-23.00 SRO 9. NOTIFY THE FOLLOWING:

  • Energy Supply (MOC)
  • Polishing Building
  • Chemistry
  • OMOC SRO 10. EVALUATE THE FOLLOWING:
  • VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.

[VPAP-2802 and EPIP are not applicable for this event.]

SRO 11. CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR When reactor power has decreased >15%, then chemistry will be notified.

END EVENT #5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 42 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Adjust 1-CH-YIC-1113 to desired total gallons RO 3. Adjust 1-CH-FC-1113A to desired flow rate.

RO 4. Place the MAKE-UP MODE SEL switch in the BORATE position.

RO 6. Check proper valve positions.

5. Place the MAKE-UP MODE CNTRL switch in the START position RO RO 7. Adjust boration rate using 1-CH-FC-1113A, as necessary.

RO 8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.

a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.

b) Enter N/A for the remaining steps in this Attachment.

Attachment 5 is on the next page RO 9. Check controllers for Primary Grade water and Boric Acid are set correctly.

RO 10. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 11. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 12. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 3 Event No.: 5 Page 43 of 103 Event

Description:

Test Button Failure, LP Turbine 1RL/1IL; 0-AP-23.00 ramp to 71% power.

Cue: 1-CC-P-1B in Auto and Examiner Ready.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions

1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
5. Place the MAKE-UP MODE CNTRL switch in the START position.
6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
7. Check proper valve positions.
8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position
9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
10. Check or place the control switches in the AUTO position.
11. Check controllers for Primary Grade water and Boric Acid are set correctly.
12. Place the MAKE-UP MODE SEL switch in the AUTO position.
13. Place the MAKE-UP MODE CNTRL switch in the START position.
14. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 44 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

Time Position Applicants Action or Behavior Team Diagnoses the failure with the following indications:

Alarms:

  • RM-Q7 - CTMT PART ALERT/FAILURE
  • RM-Q8 - CTMT GAS ALERT/FAILURE
  • RM-R8 - CTMT GAS RM-RI-160 HIGH Indications:
  • 1-DA-P-4A running continuously Unit 2 will perform RM ARPs, but will be unable to perform Auto Action verification.

1-AP-16.00 SRO Direct initiation of 1-AP-16.00, EXCESSIVE RCS LEAKAGE SRO Notes Prior to Step 1:

  • RCS average temperature has a direct impact on pressurizer level.

RO [1] MAINTAIN PRZR LEVEL:

  • Isolate Letdown
  • Control Charging flow RO closes 1-CH-LCV-1460A and 1-CH-LCV-1460B to isolate letdown. The RO will take manual control of 1-CH-FCV-1122 to stabilize pressurizer level.

SRO The team will hold a short transient brief which may simply be stated as An RCS Leak is in progress, are there any other higher priorities? (words to the effect).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 45 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

1-AP-16.00 RO 2. CHECK THE FOLLOWING PARAMETERS - STABLE OR INCREASING

  • PRZR Level
  • PRZR Pressure
  • RCS Subcooling Identifies all parameters are stable under the control of the operator. Team should identify RCS leak rate less than 50 gpm.

Note: Due to ramp previously in progress and Tave trend, the RCS leakrate will be more difficult to calculate.

RO 3. PLACE THE FOLLOWING COMPONENTS IN OFF:

  • CTMT vacuum pumps RO will place the Containment Sump and Vacuum Pumps in OFF.

SRO Note Prior to Step 4:

  • Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.

RO *4. CHECK REACTOR TRIP - REQUIRED

  • Leak rate - GREATER THAN 50 GPM OR
  • Adequate makeup not being provided by blender RO will identify that the leak rate is less than 50 gpm. Note: this can be complicated by temperature trend associated with ramp (may take more time).

4., RNO GO to Step 7.

Evaluator Note: If the Team Identifies RCS leakage > 50 gpm and manually trips the reactor, notify the Simulator Operator to Initiate Event #8, SBLOCA).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 46 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

SRO 7 CHECK SECONDARY RADIATION - NORMAL OR STABLE IF THERE IS PRE-EXISTING TUBE LEAK

  • Air Ejector Rad Monitor
  • SG Blowdown Rad Monitors
  • Secondary sample
  • N-16 Rad Monitors Unit 2 Report Unit 1 Air Ejector and Blowdown Rad Monitors - Normal BOP Reports Main Steam, and N-16 Rad Monitor Normal (using PCS)

SRO 8 CHECK RCS LEAK RATE - LESS THAN 10 GPM RO Reports leak rate > 10 GPM SRO Step 8 RNO Do the following:

a) Initiate unit shutdown IAW the appropriate operating procedure.

b) Control charging flow and seal injection to maintain PRZR level.

c) Evaluate EPIP applicability

[TS 3.1.C, RCS Operational Leakage. The following specifications are applicable to RCS operational LEAKAGE whenever Tavg (average RCS temperature) exceeds 200°F (200 degrees Fahrenheit).

1. RCS operational LEAKAGE shall be limited to:
a. No pressure boundary LEAKAGE
3. If RCS pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within the limit specified in 3.1.C.1.d, the unit shall be brought to HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.]

SRO 9 CHECK UNIT CONDITIONS

  • PRZR level - STABLE OR INCREASING
  • PRZR pressure - STABLE OR INCREASING
  • Tave - STABLE RO Reports PRZR Level, Pressure and RCS Tave Stable.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 47 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

SRO 10 CHECK LETDOWN LEAK - INDICATED BOP

  • Aux Bldg radiation - HIGH
  • CTMT radiation - HIGH RO/BOP
  • Local Report of leak RO
  • Leak rate decrease following isolation in Step 1 RO
  • Abnormal Letdown flow indication prior to isolation in Step 1 RO
  • Non-Regenerative HX tube leak - INDICATED BOP
  • CC Surge Tank level - INCREASING Unit 2
  • CC Activity - INCREASING All indication checked for leak identification are NO SRO Goes to Step 12 12 CHECK RCS LEAKRATE WITH LETDOWN SECURED - REDUCED 12 RNO Do the following:

a) Return letdown to service IAW the following, if desired:

  • Normal letdown, IAW Attachment 2 OR
  • Excess letdown, IAW 1-OP-CH-006, SHIFTING LETDOWN b) GO TO Step 15.

[TS 3.1.C, RCS Operational Leakage. The following specifications are applicable to RCS operational LEAKAGE whenever Tavg (average RCS temperature) exceeds 200°F (200 degrees Fahrenheit).

1. RCS operational LEAKAGE shall be limited to:
a. No pressure boundary LEAKAGE
3. If RCS pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within the limit specified in 3.1.C.1.d, the unit shall be brought to HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 6 Page 48 of 103 Event

Description:

RCS Leak 35 gpm, 1-AP-16.00.

Cue: By Evaluator.

END OF EVENT #6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 7 Page 49 of 103 Event

Description:

Containment particulate and gas RM fail, no Auto Actions.

Cue: Initiated by Event 6.

Time Position Applicants Action or Behavior 1-RM-R8 Actions BOP NOTE: BOP will be handed Steps 3 and 4 of ARP to verify auto actions of CTMT GAS High alarm.

BOP 3 VERIFY CTMT PURGE SYS - ISOLATED a) CTMT PURGE SUP - CLOSED

  • 1-VS-MOV-100A
  • 1-VS-MOV-100B
  • 1-VS-MOV-100C
  • 1-VS-MOV-100D BOP will verify Purge valves closed on the Unit 1 Ventilation Panel by observing RED and GREEN lights extinguished, and GREEN magnet over Shut position indicating light signifying Valve Closed.

b) CTMT PURGE SUP fans - STOPPED

  • 1-VS-F-4A
  • 1-VS-F-4B BOP will identify Purge Supply Fans secured by observing RED and GREEN indicating lights extinguished.

c) CTMT PURGE BYP valve - CLOSED

  • 1-VS-MOV-101 BOP 4 VERIFY CTMT IA SYSTEM ALIGNMENT:
  • 1-IA-TV-101A - CLOSED
  • 1-IA-TV-101B - CLOSED Identifies 1-IA-TV-101A / B Open by observing position indicating lights on Unit 1 Vertical board RED Light LIT.

Step 4 RNO Manually Align Valves BOP will close the valves by depressing and holding the GREEN indicating light until only the GREEN indicating light is lit.

NOTE: When either 1-IA-TV-101A / B are closed, 1-IA-AOV-103 will open (checked in Step 5 below).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 7 Page 50 of 103 Event

Description:

Containment particulate and gas RM fail, no Auto Actions.

Cue: Initiated by Event 6.

BOP 5 CHECK CTMT IA COMPR OUTSIDE SUCT - OPEN

  • 1-IA-AOV-103 BOP will observe 1-IA-AOV-103 OPEN by observing RED position indicating light LIT.

End EVENT #7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 51 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior Team Diagnose escalation of RCS Leak by the following:

Alarms:

1C-B8, PRZR LO PRESS 1B-A3, CTMT SUMP HI LVL Indications:

Lowering RCS Pressure PRZR Level decreasing SRO Direct RO to re-perform Immediate Actions of AP-16.00.

RO [1] MAINTAIN PRZR LEVEL:

  • Isolate Letdown
  • Control Charging flow RO checks 1-CH-LCV-1460A and 1-CH-LCV-1460B closed.

The RO will increase flow using 1-CH-FCV-1122 to control PRZR level.

SRO The team will hold a short transient brief which may simply be stated as An RCS Leak is in progress, are there any other higher priorities? (words to the effect).

1-AP-16.00 SRO 2. VERIFY THE FOLLOWING PARAMETERS - STABLE OR INCREASING

  • PRZR Level
  • PRZR Pressure
  • RCS Subcooling Identifies all parameters are stable under the control of the operator. Team should identify RCS leak rate greater than 50 gpm.

NOTE: SRO may direct RO to manually trip the reactor and safety inject at this point due to degrading plant parameters.

RO 3. PLACE THE FOLLOWING COMPONENTS IN OFF:

  • CTMT vacuum pumps RO will check the Containment Sump and Vacuum Pumps in OFF.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 52 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

SRO Note Prior to Step 4:

  • Shift Supervision and STA must remain informed of RCS leak rate for EPIP applicability.

SRO *4. CHECK REACTOR TRIP - REQUIRED

  • Leak rate - GREATER THAN 50 GPM OR
  • Adequate makeup not being provided by blender RO will identify that the leak rate is greater than 50 gpm.

SRO 5 ALIGN CHG PUMP SUCTION TO RWST a) Open 1-CH-MOV-1115B and 1-CH-MOV-1115D b) Close 1-CH-MOV-1115C and 1-CH-MOV-1115E RO Evaluator Note: Team may or may not manually align these valves depending on timing.

SRO 6 GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION SRO Directs RO to trip the reactor, perform E-0, and Manually Safety Inject on Step 4.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 53 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior 1-E Reactor Trip or Safety Injection RO [1] CHECK REACTOR TRIP:

a) Manually trip reactor Pushes the reactor trip push buttons.

b) Check the following:

  • All Rods On Bottom light - LIT
  • Neutron flux - DECREASING RO [2] CHECK TURBINE TRIP:

RO a) Manually trip the turbine Pushes the turbine trip push buttons.

b) Verify all turbine stop valves - CLOSED c) Isolate reheaters by closing MSR steam supply SOV

  • 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)

RO [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 54 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

[4] CHECK IF SI INITIATED:

RO a) Check if SI is actuated:

  • LHSI pumps - RUNNING
  • A-F-3 SI INITIATED - TRAIN A
  • A-F-4 SI INITIATED - TRAIN B RO 4b) Manually initiate SI The RO will manually initiate SI at step 4 by pushing both SI pushbuttons.

After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal, with the exception of the alarms already received. He will also state that containment conditions and the electrical conditions are as you see them (or as reported by the RO/BOP).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 55 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

SRO The team will hold a transition brief. During the brief it will be identified that SI was initiated and the RCS leak has degraded into a LOCA.

SRO/BOP 5. Initiate Attachment 1 (Attachment 1, 2, and 3 actions contained the end of Event 8).

SRO/RO SRO may direct the RO to perform Attachment 8 of 1-E-0 for Transient AFW Control, or opt to throttle AFW as part of E-0, Step 6.

RO *6. CHECK RCS AVERAGE TEMPERATURE

  • STABLE AT 547°F OR
  • TRENDING TO 547°F The team will identify that RCS temperature is decreasing. The team should attribute this to the injection of SI into the RCS and AFW flow to the SGs. It is acceptable for the team to enter the RNO portion of this step and perform the applicable steps (summarized below):

Stop dumping steam Reduce AFW flow to the SGs Close MSTVs if cooldown continues

7. CHECK PRZR PORVs AND SPRAY VALVES:

RO a) PRZR PORVs - CLOSED b) PRZR spray controls

  • Demand at Zero (or)
  • Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 56 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

SRO NOTE: Seal injection flow should be maintained to all RCPs.

RO *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS Two or three Charging pumps will be running and flowing to the RCS.

b) RCS subcooling - LESS THAN 30°F [85°F]

RCS subcooling may or may not be less than 30 °F at this time.

RNO for the step is to go to step 9.

Critical Task:

CT-1: WOG E-1C: Trip all RCPs so that CETC temperatures do not become superheated when forced circulation in RCS stops; Trip all RCPS within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).

NOTE: If RCP trip Criteria are met prior to reaching this Step, the Continuous Actions Page (CAP) contains these criteria. After this Step is read, this step or the CAP can be used for criteria as long as the Team is performing E-0.

RO 9. CHECK IF SGs ARE NOT FAULTED:

  • Check pressures in all SGs a) STABLE OR INCREASING AND b) GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 57 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

SRO 10. CHECK IF SG TUBES ARE NOT RUPTURED:

Unit 2

  • Condenser air ejector radiation - NORMAL Unit 2
  • SG blowdown radiation - NORMAL
  • SG MS radiation - NORMAL
  • TD AFW pump exhaust radiation - NORMAL
  • SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER RO RO will use PCS indication for MS and TDAFW Exhaust radiation.

Unit 2 will be used to report Condenser A/E and SG Blowdown radiation trend.

SRO 11 CHECK RCS - INTACT INSIDE CTMT

  • CTMT radiation - NORMAL
  • CTMT pressure - NORMAL
  • CTMT RS sump level - NORMAL RO Identify CTMT conditions as abnormal SRO GO TO 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

SRO The team will hold a transition brief. During the brief the SRO will set priorities. The RO and BOP will state the parameters associated with the brief placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified alarms. He will also state that containment conditions and the electrical conditions are as you see them.

The SRO will complete the Brief and continue with E-1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 58 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior Step 1, 1-E-1 SRO NOTE: Criteria for FR-Z.1 Entry may be met at any time during performance of 1-E-1. (FR-Z.1 Actions in Section 9).

1 CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO identify 2 CH pumps running.

b) RCS subcooling - LESS THAN 30°F [85°F]

RO reports actual subcooling.

c) Stop all RCPs RO Stops RCPs if not already tripped.

d) RCS pressure - LESS THAN 1275 PSIG [1475 PSIG]

e) Close CHG pump miniflow recirc valves:

  • 1-CH-MOV-1275A
  • 1-CH-MOV-1275B
  • 1-CH-MOV-1275C RO closes or verifies closed mini-flow recirc valves.

Critical Task:

CT-1: WOG E-1C: Trip all RCPs so that CET temperatures do not become superheated when forced circulation in RCS stops; Trip all RCPs within 5 minutes of reaching RCP Trip and Mini-flow Recirc Criteria (KOA).

NOTE: Critical Task copied from E-0 if timing of scenario leads to RCP trip criteria identified on entry to 1-E-1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 59 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

1-E-1 SRO 2 CHECK IF SGs ARE NOT FAULTED:

  • Check pressures in all SGs:
  • STABLE OR INCREASING AND
  • GREATER THAN 100 PSIG RO reports SGs are not faulted.

NOTE: SG pressures may be decreasing due to cooldown. RO may report SG pressure as lowering. The SRO will obtain Team concurrence that SG pressure decrease is related to RCS cooldown not a SG fault. The brief is closed.

1-E-1 SRO *3 CHECK INTACT SG LEVELS:

a) Narrow range level - GREATER THAN 12% [18%]

b) Check emergency buses - BOTH ENERGIZED c) Control feed flow to maintain narrow range level between 22% and 50%

1-E-1 SRO 4 CHECK IF SG TUBES ARE NOT RUPTURED:

  • Condenser air ejector radiation - NORMAL
  • SG blowdown radiation - NORMAL
  • TD AFW pump exhaust radiation - NORMAL
  • SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER Unit 2 may be used to report Unit 1 condenser air ejector and blowdown radiation monitor readings.

RO Report MS and TDAFW RM readings using PCS. Identify SG NR levels NOT increasing in an uncontrolled manner.

1-E-1 CAUTION: If any PRZR PORV opens because of high PRZR pressure, the PORV must be verified closed or isolated after pressure decreases to less than 2335 psig.

SRO *5 CHECK PRZR PORVs AND BLOCK VALVES:

a) Power to PRZR PORV block valves - AVAILABLE RO Report PRZR block valves both available.

b) PRZR PORVs - CLOSED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 60 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

RO Report PRZR PORVs closed.

c) PRZR PORV block valves - AT LEAST ONE OPEN RO Report PRZR block valves both open.

1-E-1 SRO *6. ___ CHECK IF SI FLOW SHOULD BE REDUCED:

a) RCS subcooling based on CETCs - GREATER THAN 30°F [85°F]

RO Reports indicated subcooling.

b) Secondary heat sink:

RO

  • Total feed flow to INTACT SGs - GREATER THAN 350 GPM [450 GPM]

OR

  • Narrow range level in at least one intact SG - GREATER THAN 12% [18%]

RO Reports SGs have adequate level and AFW flow.

RO c) RCS pressure - STABLE OR INCREASING RO Reports RCS pressure decreasing.

SRO RNO a) OR c) GO TO Step 7.

1-E-1 SRO *7 CHECK IF HI HI CLS INITIATED:

  • CS pump(s) - RUNNING OR
  • Any Hi Hi CLS annunciator - LIT NOTE: At this Point CTMT pressure may have increased to the HI and/or Hi-Hi CLS setpoint. The Team should identify that Hi and Hi-Hi CLS do not automatically initiate and take manual action to perform the automatic actions. (FR-Z.1 Actions in Section 9)

When the Team identify that Hi-Hi CLS has not actuated, a transition to FR-Z.1 will be made. When the transition is made Critical Task 2 begins:

CRITICAL TASK:

(Actions for FR-Z.1 will follow 1-E-1, Step 18). Page 77

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 61 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

1-E-1 SRO 8 CHECK SERVICE WATER AVAILABLE:

a) Check Intake Canal level - BEING MAINTAINED BY CW PUMPS RO Reports Intake Canal level is 29 feet and Stable.

b) GO TO Step 12 1-E-1 SRO *12 CHECK IF CS PUMPS CAN BE STOPPED:

a) Check the following:

  • RWST level - LESS THAN 3%

AND

  • CS Pump amps - FLUCTUATING RO Reports actual RWST Level.

RNO a) GO TO Step 14. WHEN the following conditions are met, THEN do Steps 12b through 12f.

  • RWST level - LESS THAN 3%

AND

  • CS Pump amps - FLUCTUATING 1-E-1 SRO CAUTION: RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 250 psig [400 psig], one LHSI pump must be manually restarted to supply water to the RCS.
  • 14 CHECK IF LHSI PUMPS SHOULD BE STOPPED:

a) Check RCS pressure:

1) Pressure - GREATER THAN 250 PSIG [400 PSIG]

RO Reports RCS pressure > 250 PSIG [400 PSIG]

2) Pressure - STABLE OR INCREASING Reports RCS pressure Lowering.

RNO 2) GO TO Step 15.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 62 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

1-E-1 15 CHECK RCS AND SG PRESSURES:

  • Check pressure in all SGs - STABLE OR INCREASING
  • Check RCS pressure - STABLE OR DECREASING NOTE: SG pressures may be decreasing due to coodown. RO may report SG pressure as lowering. The SRO will obtain Team concurrence that SG pressure decrease is related to RCS cooldown not a SG fault. The brief is closed 1-E-1 SRO 16 CHECK IF EDGs CAN BE STOPPED:

a) Check AC emergency buses - ENERGIZED BY OFFSITE POWER RO Reports that H Emergency bus energized by off-site power, and J emergency powered from #3 EDG.

b) Reset both trains of SI if necessary RO RO presses SI reset pushbuttons.

c) Check CTMT pressure - LESS THAN 14 PSIA RO Reports actual containment pressure (pressure will be greater than 14 psia).

RNO c) GO TO Step 17. WHEN pressure less than 14 psia, THEN do Steps 16d and 16e.

1-E-1 SRO 17 CHECK INSTRUMENT AIR AVAILABLE:

a) Check annunciator B-E NOT LIT RO Reports B-E-6 NOT LIT.

b) Check at least one CTMT IA compressor - RUNNING

  • 1-IA-C-4A or 1-IA-C-4B RO Reports 1-IA-C-4A running.

c) Check 1-IA-TV-100 - OPEN RO Reports 1-IA-TV-100 position.

NOTE: When BOP performs Attachment 4 of E-0, 1-IA-TV-100 may be closed; SRO/BOP may confer over closure of the valve since Hi-Hi CLS actions are being

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 63 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

manually performed.

1-E-1 SRO 18 INITIATE EVALUATION OF PLANT STATUS:

END OF EVENT 8 END OF SCENARIO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 64 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior Attachment 1 of E-0 1 CHECK FW ISOLATION:

  • Feed pump discharge MOVs - CLOSED
  • 1-FW-MOV-150A
  • 1-FW-MOV-150B
  • MFW pumps - TRIPPED
  • Feed REG valves - CLOSED
  • SG FW bypass flow valves - DEMAND AT ZERO
  • SG blowdown TVs - CLOSED Attachment 1 of E-0 2 CHECK CTMT ISOLATION PHASE I:
  • Phase I TVs - CLOSED
  • 1-CH-MOV-1381 - CLOSED
  • 1-SV-TV-102A - CLOSED
  • PAM isolation valves - CLOSED
  • 1-DA-TV-103A
  • 1-DA-TV-103B Attachment 1 of E-0 3 CHECK AFW PUMPS RUNNING:

a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY Attachment 1 of E-0 BOP 4. CHECK SI PUMPS RUNNING:

  • CHG pumps - RUNNING
  • LHSI pumps - RUNNING

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 65 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Attachment 1 of E-0 BOP

5. CHECK CHG PUMP AUXILIARIES:
  • CHG pump CC pump - RUNNING
  • CHG pump SW pump - RUNNING Attachment 1 of E-0 BOP 6. CHECK INTAKE CANAL:
  • Level - GREATER THAN 24 FT
  • Level - BEING MAINTAINED BY CIRC WATER PUMPS Attachment 1 of E-0
7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:

a) Check if ANY of the following annunciators - HAVE BEEN LIT

  • E-F-10 (High Steam Flow SI)

BOP

  • B-C-4 (Hi Hi CLS Train A)
  • B-C-5 (Hi Hi CLS Train B)

Identifies annunciators not lit and goes to step 8.

Attachment 1 of E-0 BOP

  • 8. CHECK IF CS REQUIRED:

a) CTMT pressure - HAS EXCEEDED 23 PSIA Identifies pressure has not exceeded 23 or 17.7 psia and goes to step 10.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 66 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Attachment 1 of E-0 BOP *10. BLOCK LOW PRZR PRESS SI SIGNAL:

a) Check PRZR pressure - LESS THAN 2000 psig b) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c) Check Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.

Attachment 1 of E-0 BOP *11. BLOCK LOW TAVE SI SIGNAL:

Step may not be performed at this time (if Tave is greater than 543°F).

a) Check RCS Tave - LESS THAN 543°F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c) Check Permissive Status light F LIT Attachment 1 of E-0 NOTE:

  • CHG pumps should be run in the following order of priority: C, B, A.
  • Subsequent SI signals may be reset by re-performing Step 12.

BOP

12. CHECK SI FLOW:

a) HHSI to cold legs - FLOW INDICATED

  • 1-SI-FI-1961 (NQ)
  • 1-SI-FI-1962 (NQ)
  • 1-SI-FI-1963 (NQ)
  • 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c) Reset SI.

d) Stop one CHG pump and out in AUTO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 67 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Step 12, Attachment 1 of E-0, Continued e) RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:

1) Verify reset or reset SI.
2) Stop one LHSI pump and put in AUTO.
3) GO TO Step 13.

Attachment 1 of E-0 BOP

13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]

Attachment 1 of E-0 BOP

14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.

Attachment 1 of E-0 BOP

15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next Page of this guide)

Depending on timing, this attachment may have already been completed.

Attachment 1 of E-0 BOP

16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2 on next page Unit 2 Operator will state that Unit 2 is at 100% power (if asked)

Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 68 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Time Position Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 SRO NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.

ATTACHMENT 2 of 1-E-0 RO/BOP 1. Check opened or open CHG pump suction from RWST MOVs.

  • 1-CH-MOV-1115B
  • 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 RO/BOP 2. Check closed or close CHG pump suction from VCT MOVs.
  • 1-CH-MOV-1115C
  • 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 RO/BOP 3. Check running or start at least two CHG pumps. (listed in preferred order)
  • 1-CH-P-1C
  • 1-CH-P-1B
  • 1-CH-P-1A ATTACHMENT 2 of 1-E-0 RO/BOP 4. Check opened or open HHSI to cold legs MOVs.
  • 1-SI-MOV-1867C
  • 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 RO/BOP 5. Check closed or close CHG line isolation MOVs.
  • 1-CH-MOV-1289A
  • 1-CH-MOV-1289B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 69 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

ATTACHMENT 2 of 1-E-0 RO/BOP 6. Check closed or close Letdown orifice isolation valves.

  • 1-CH-HCV-1200A
  • 1-CH-HCV-1200B
  • 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 RO/BOP 7. Check opened or open LHSI suction from RWST MOVs.
  • 1-SI-MOV-1862A
  • 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 RO/BOP 8. Check opened or open LHSI to cold legs MOVs.
  • 1-SI-MOV-1864A
  • 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 RO/BOP 9. Check running or start at least one LHSI pump.
  • 1-SI-P-1A
  • 1-SI-P-1B ATTACHMENT 2 of 1-E-0 RO/BOP 10. Check High Head SI flow to cold legs indicated.
  • 1-SI-FI-1961
  • 1-SI-FI-1962
  • 1-SI-FI-1963
  • 1-SI-FI-1943 or 1-SI-FI-1943A

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 70 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

ATTACHMENT 2 of 1-E-0 RO/BOP 11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.

  • Alternate SI to Cold legs
  • Hot leg injection

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 71 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 72 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 73 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 74 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Unit 2 will prompt BOP: Chilled Water has been aligned IAW CAUTION prior to Step 1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 75 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Unit 2 will prompt BOP: MCR Boundary DP is the same as DP indicated on Unit 2 Ventilation Panel.

Unit 2 will prompt BOP: Unit 2 remains operating at 100%

power.

Unit 2 will assume responsibility for the Attachment action from this point.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 8 Page 76 of 103 Event

Description:

SBLOCA, 1-AP-16.00, 1-E-0.

Cue: By Evaluator or if the Team manually trips the reactor during Event #6.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 77 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

Time Position Applicants Action or Behavior 1-FR-Z.1 Actions CAUTION: If 1-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, is in effect, containment spray systems should be operated as directed by 1-ECA-1.1, instead of Step 1 below.

SRO 1 CHECK IF CS REQUIRED:

a) Check CTMT pressure - HAS INCREASED TO GREATER THAN 23 PSIA b) Check CS pumps - RUNNING b) IF RWST level greater than 3%,

THEN start CS pumps. IF any CS pump can NOT be started, THEN monitor OSRS pumps for cavitation.

RO Starts 1-CS-P-1A / 1B IF cavitation is indicated, THEN put affected OSRS pump in PTL c) Check CS system valves - OPEN c) Manually align CS valves.

  • 1-CS-MOV-100A
  • 1-CS-MOV-100B
  • 1-CS-MOV-101A and B
  • 1-CS-MOV-101C and D
  • 1-CS-MOV-102A and B RO Opens Valves Listed Above (BOLDED).

d) Stop all RCPs RO Stops RCPS and acknowledges Loop Low Flow Alarms.

Critical Task:

CT-2: WOG E-0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (red-path) challenge develops to the CSF. Establish CS flow from at least one CS pump before containment pressure exceeds 60 psia AND at least one RS train before RMT.

Evaluator Note: To meet the CT, One Train of CTMT Depressurization must be aligned. One CS pump with either of its associated discharge MOVs open.

1-CS-P-1A Running, with 1-CS-MOV-101A or 1-CS-MOV-101B OPEN. OR 1-CS-P-1B Running, with 1-CS-MOV-101C or 1-CS-MOV-101D OPEN.

CRITICAL TASK:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 78 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

1-FR-Z.1 Actions SRO 2 CHECK SW FLOW TO RS HXs - Align valves as necessary.

GREATER THAN 4750 GPM RO Checks flow > 4750 GPM following the Opening of the SW Valves Listed below.

a) Check the following valves - OPEN

  • 1-SW-MOV-103A, B, C, and D
  • 1-SW-MOV-104A, B, C, and D
  • 1-SW-MOV-105A, B, C, and D RO Open the SW MOVs listed above.

1-FR-Z.1 Actions SRO 3 CHECK RS SYSTEMS:

a) Check RWST level -LESS THAN 60% a) Do the following:

1) Monitor RWST level.
2) WHEN RWST level is less than 60%, THEN perform Steps 3b and 3c.

1-FR-Z.1 Actions SRO 4 CHECK INTAKE CANAL LEVEL - GREATER THAN 24 FT RO Reports Intake Canal Level 29 feet and Stable.

1-FR-Z.1 Actions SRO 5 CHECK CTMT ISOLATION VALVES -

CLOSED IAW ATTACHMENT 1 IF flow path NOT necessary, THEN close valves BOP Aligns Valves as necessary.

NOTE: BOP and SRO may confer on leaving 1-IA-TV-100 open.

NOTE: FR-Z.1 Actions located at the end of this section.

1-FR-Z.1 Actions SRO 6. ___ CHECK MSTVs - CLOSED Manually close MSTVs.

RO/BOP Closes MSTVs if not already performed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 79 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

1-FR-Z.1 Actions CAUTION:

  • At least one SG must be maintained available for RCS cooldown.
  • If all SGs are faulted, at least 60 gpm [100 gpm] feed flow should be maintained to each SG.

SRO 7. ___ CHECK IF FEED FLOW SHOULD BE ISOLATED TO ANY SG(s):

a) Check pressures in all SGs: a) GO TO Step 8

  • ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR
  • ANY SG COMPLETELY DEPRESSURIZED RO/BOP Reports SGs NOT Faulted.

1-FR-Z.1 Actions SRO 8 CHECK SERVICE WATER AVAILABLE:

a) Check Intake Canal level - BEING MAINTAINED BY CIRC WATER PUMPS RO/BOP Reports Intake Canal Level 29 feet and Stable. Being maintained by CW pumps.

b) RETURN TO procedure and step in effect SRO Returns to 1-E-1, Step In Effect.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 80 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

Valves Operated for Hi CLS Failure.

Valves Operated for Hi Hi CLS Failure.

Valve BOP/SRO may confer and leave open.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 81 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

Valves Operated for Hi CLS Failure.

Valves Operated for Hi Hi CLS Failure.

Valve BOP/SRO may confer and leave open.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Event No.: 9 Page 82 of 103 Event

Description:

Hi and Hi-Hi CLS Fail, FR-Z.1.

Cue: By Event 8.

Section Not Performed for this Scenario.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 83 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 84 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 85 of 103 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 86 of 103 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:

Recall IC -263 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.

Open the monitor window and add the following points to it:

  • asp_ao_off
  • set sphhcntprs_k1 = 60
  • iadryer_reset
  • ??

Enter the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Type (Auto or Manual)

RC0801 TAVE TAYLOR MATH 10 0 1 0 -1 MAN UNIT FAILURE HI/LOW MS0801 SG A STM FLOW 10 30 3 0 -1 MAN TRNSMTR MS-FT-475 FAILURE EL4902 BKR 15J8 SPURIOUS TRIP 10 0 5 FALSE TRUE MAN RC04 RCS LEAK NONISOLABLE 10 0 9 0 3.5 MAN (0 - 1200 GPM)

RM0202 PROCESS RAD 10 0 9 0 0.1 MAN MONITOR RI-RMS-159 FAILURE RM0201 PROCESS RAD 10 0 9 0 0.1 MAN MONITOR RI-RMS-160 FAILURE CA03 Disable IA-TV-101A Auto 0 0 9 FALSE TRUE MAN Closure CA06 Disable IA-TV-101B Auto 0 0 9 FALSE TRUE MAN Closure RC0101 RCS COLD LEG A PIPE 10 600 11 0 .6 MAN RUPTURE RS0901 TRN A HI CLS FAILS TO 0 0 30 FALSE TRUE ACTIVE ACTIVATE RS0902 TRN B HI CLS FAILS TO 0 0 30 FALSE TRUE ACTIVE ACTIVATE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 87 of 103 SIMULATOR OPERATORS GUIDE Enter the following Remote Functions:

Override Set Condition Trigger AC_SMS_MODE OFF 30 Enter the following Override:

Override Set Condition Trigger TEST_IRL_IIL EHC ON, 10 Sec TD 7 TEST 1RL 1IL CLS_ACT_TRA OFF 30 CLS_ACT_TRB OFF 30 TRIGGER TYPE DESCRIPTION 1 MAN TAVE TAYLOR MATH UNIT FAILURE LOW 3 MAN SG A STM FLOW TRNSMTR MS-FT-475 FAILURE 5 MAN BKR 15J8 SPURIOUS TRIP 7 MAN IRL/ILL TEST PUSHBUTTON FAILURE RCS LEAK NONISOLABLE (35 GPM) with AUTO ACTIONS RM-MAN 9 159/160 FAILURE 11 MAN LBLOCA WITH HI and HI HI CLS FAILED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 88 of 103 SIMULATOR OPERATORS GUIDE Verify the following control room setup:

Place the simulator in RUN and verify normal 100% power operation indications.

Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:

Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).

Verify Ovation System operating.

Reset ICCMs.

Verify Component Switch Flags.

Verify Brass Caps properly placed.

Verify SG PORVs set for 1035 psig.

Verify Rod Control Group Step Counters indicate properly.

Verify Ovation CRT display.

Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)

Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:

AP-53.00 AP-16.00 AP-23.00 1-OPT-RX-007 (3)

E-0 E-1 (2)

OP-CH-007 MOL OP-RX-010 OP-ZZ-002 Verify Reactivity Placard is current.

Verify ALL PINK MAGNETS are accounted for.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 89 of 103 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

Ask for and answer questions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 90 of 103 SIMULATOR OPERATORS GUIDE Conduct shift turnover:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1.

The last shift performed two 35 gallon alt dilutions followed by a manual makeup for training.

A BAST at 8.0 W/%.

When the team has accepted the shift, proceed to the Session Conduct Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 91 of 103 SIMULATOR OPERATORS GUIDE Session Conduct:

  • Ensure conditions in Simulator Set-up are established.
  • Ensure Trigger 30 is active prior to team entering the simulator.
  • Verify Exam Security has been established and ASP_AO_OFF = True.

EVENT 1 Deleted.

EVENT 2 Failure Median Tave Low, 0-AP-53.00.

When cued by examiner, implement Trigger #1.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of Median Tave. The individual(s) contacted will also acknowledge entry into AP-53.00.
  • If contacted, will take responsibility for writing the CR.
  • If asked, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.

STA:

  • If contacted, will acknowledge the failure of Median Tave.
  • If asked, the STA will report that upon review of CEP 99-0029, Median Tave is NOT listed in CEP 99-0029.
  • If asked, the STA will review VPAP-2802 and TRM Section 3.3 and report that the results of the review have been discussed with Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 92 of 103 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge instrumentation failure and commence investigation of the failure.

Unit 2 Operator:

  • If contacted, will acknowledge the failure.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 93 of 103 SIMULATOR OPERATORS GUIDE EVENT 3 Failure of Steam Flow Channel Low, A SG. 0-AP-53.00.

When cued by examiner, implement Trigger #3.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of 1-MS-FT-1474. The individual(s) contacted will also acknowledge any TS LCOs.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to place the channel in trip.
  • If contacted, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.

STA:

  • If contacted, will acknowledge the failure of 1-MS-FT-1474. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
  • If contacted, will take responsibility for writing the CR.
  • If asked, 1-MS-FT-1474 is a RG 1.97 variable
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
  • When directed, STA review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

Field Operators:

  • Will perform actions as directed.

I&C:

  • If notified by MCR to place the channel in trip, state that you will review the procedure and notify the Shift Manager when ready to brief.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 94 of 103 SIMULATOR OPERATORS GUIDE Maintenance/ Work Week Coordinator:

  • If contacted, will notify I&C of the failure.

Unit 2:

  • If contacted, will acknowledge the channel failure.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 95 of 103 SIMULATOR OPERATORS GUIDE EVENT 4 1J 4160V emergency bus off-site power supply breaker trips. 1-AP-10.07.

When the Evaluator is ready, Implement Trigger #5 for the failure. Evaluator may go to next event (event #5) when 1-CC-P-1B is placed in Auto.

Operations Supervisor/Management:

  • If contacted, will acknowledge the loss of 1J 4160 V bus, and the start and load of #3 EDG.
  • If contacted, will inform OM on Call and Electrical Foreman.

STA:

  • If contacted, will acknowledge the loss of 1J 4160V bus and the start and load of #3 EDG.
  • After directed, the STA will report that VPAP-2802 has been reviewed and discussed with the Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Maintenance/ Work Week Coordinator:

  • If contacted, will acknowledge the failure and commence investigations.

Field Operators:

  • If contacted, will check status of 15J8 breaker and find an individual in the area that reports he bumped the cabinet while cleaning and heard a loud noise. 1-CC-P-1B must have been returned to Auto before this report is made.
  • If asked, the condensate polishing building operator will report current polishing building DP (read from simulator screen).
  • When Directed, to check status of IA compressors (1B-E6 ARP), CA6 1-IA-C-1 IA Local Panel, the local panel will have an Alarm light lit. Depress U1_IAC1_SET button to clear alarm.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 96 of 103 SIMULATOR OPERATORS GUIDE

  • When Directed, to check status of IA Dryer (1B-E5 ARP), the dryer will be bypassed, use IADRYER_RESET on monitor to reset the dryer.
  • When contacted, to close 15J9 breaker, EL11, Unit 1 - 4160 Breakers, 15J9, scroll to bottom of pop-up box, double click on SW_15J9_RF, select close, INSERT.
  • When contacted, RM-159/160 Particulate and Gas RM skid is normal.
  • When contacted, concerning monitoring of #3 EDG parameters, follow instructions.

Unit 2:

  • If contacted, acknowledge start and load of #3 EDG on Unit 1.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 97 of 103 SIMULATOR OPERATORS GUIDE EVENT 5 Test Button failure, 1RL/1IL close, 0-AP-23.00 ramp to 71%.

When 1-CC-P-1B in Auto and examiner ready, implement Trigger #7.

Operations Supervisor/Management:

  • If contacted, will acknowledge closure of 1RL/1IL. Also acknowledge the entry into AP-53.00/AP-38.00 for the failure.
  • If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC (Lead Evaluator), the Shift Manager will direct a 1%/minute ramp rate.
  • If contacted, will take responsibility for writing the CR.

Unit 2 Operator:

  • If notified, acknowledge the failure and impending ramp of Unit 1.

STA:

  • If contacted, will acknowledge the closure of 1RL/1IL, and entry into AP-53.00/AP-38.00.
  • If contacted, will take responsibility for writing the WR and CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.
  • The STA will acknowledge the Reactivity Plan reported by the RO.
  • If contacted, STA review of VPAP-2802 complete and reviewed with Shift Manager.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 98 of 103 SIMULATOR OPERATORS GUIDE Field Operators:

  • If contacted, as the Turbine Building Operator to walkdown the Turbine during the ramp, acknowledge the direction.
  • If contacted, as the polishing building operator, acknowledge the direction to monitor polisher DP.
  • If contacted, as Turbine Building operator, the 1RL/1IL valves are closed, no external abnormalities noted.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 99 of 103 SIMULATOR OPERATORS GUIDE EVENTS 6 RCS Leak 35 gpm. 1-AP-16.00.

Note: It would be preferable to wait until power is <80% to implement this failure to allow for ramp stabilization prior to creating RCS leak; this will allow the team to assess leakrate with more precision.

When the Evaluator is ready, implement Trigger # 9. If the Team manually trips the reactor, the Evaluator may prompt initiation of Event #8.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will acknowledge entry into AP-16.00.
  • If contacted, will acknowledge Unit shutdown imminent due to excessive RCS leakage.
  • If contacted, will acknowledge EPIPs require evaluation.

STA:

  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal with the exception of the previously identified radiation monitor alarms. He will also state that containment conditions and the electrical conditions are as you see them.
  • When Notified, acknowledge that EPIPs require evaluation.
  • If contacted, will enter the control room and and prepare for the transient brief (items are reported as you see them or previously reported).

Unit Two:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 100 of 103 SIMULATOR OPERATORS GUIDE

  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO/BOP.
  • If asked, blowdown and air ejector RM readings are [as indicated at the time].
  • When required, assist Unit by acknowledging Fire Panel Alarms.
  • If contacted, Unit Two has implemented AP-50.00, and all conditions on U2 are normal.

Field Operators:

  • If contacted, field operators will perform valve manipulations as required:

Health Physics:

  • If contacted, will acknowledge the leak of RCS coolant into containment.

Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge the failure.

Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge the failure.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 101 of 103 SIMULATOR OPERATORS GUIDE EVENT 7 Particulate and gas RM fail, No Auto Actions.

Implemented with Trigger #9.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of the automatic actions on RM-160 High alarm.
  • If contacted, will take responsibility for writing the WR and CR.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
  • If directed, perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.

Field Operators:

  • If directed, field operators will perform local manipulations as required.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 102 of 103 SIMULATOR OPERATORS GUIDE EVENT 8 SBLOCA, 1-AP-16.00, 1-E-0.

When the Evaluator is ready, actuate Trigger #11. Prompt the Evaluator when RCS Subcooling reaches 35 °F and decreasing so that start time for CT-1 is monitored.

Operations Supervisor/Management:

  • If contacted, will acknowledge the reactor trip and Entry into E-0.
  • If contacted, will take responsibility for writing the WR and CR.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.

STA

  • Enter MCR when called and standby to monitor CSFSTs.
  • When entry conditions for Containment Orange Path identified, circle the appropriate Path and show to the SRO.

Field Operators:

  • If directed, field operators will perform local manipulations as required.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 3 Page 103 of 103 SIMULATOR OPERATORS GUIDE EVENT 9 Hi and HI-CLS Failure, FR-Z.1.

Implemented by ACTIVE Triggers.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of Hi and Hi-Hi CLS.

STA:

  • When the Team identifies containment pressure has exceeded 23 psia, use CSFSTs to mark flowpath to FR-Z.1, ORANGE path and present to SRO.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms and report the alarm to the Unit 1 SRO.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
  • When BOP performs Attachment 3 of E-0, MCR Boundary DP readings are the same as the indication on Unit 2 Ventilation Panel. Unit 2 has initiated 0-AP-50.00. Unit 2 remains at 100% power. Assume responsibility for E-0, Attachment 3, monitoring of SFP.
  • If asked, Unit 2 RWST cross-ties are open.

Field Operators:

  • If directed, field operators will perform local manipulations as required.

Role play as other individuals as needed.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Facility: Surry Power Station Scenario No.: 4 Op-Test No.: 2014-001 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Time in Core Life - Middle of Life; Core Cycle - Cycle 26 Unit 1 and 2 operating at 100%. All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
  • 1-CC-P-1D tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4)

RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.

  • Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
  • A BAST at 8.0 W/%.

Event Malf. Event Event No. No. Type* Description 1 N/A Deleted 2 RC4802, I - RO 1-RC-PT-1445 fails high, PRZR Pressure channel fail high. AP-31.00,

+1 Deg TS - SRO Increasing or Decreasing RCS Pressure.

3 MS1305, I - BOP Steam Pressure Channel III, B SG fails High. 0-AP-53.00, Loss of Vital

+1 Deg TS-SRO Instrumentation/Controls.

CH2101, 4 +1 Deg I - RO Failure of VCT Level Channel LT-115 High.

CC0302 5 CC0802 C - BOP Overcurrent on B CC pump with breaker mechanically stuck closed SW_15J9_ TS - SRO causing the trip of Stub Bus Supply breaker.

RF, TRIP C - RO 6 TS - SRO RD1236 R - RO / Dropped Rod Control Bank C, Group 1; AP-1.00, Rod Control SRO Malfunction, AP-23.00, Rapid Load Reduction.

N - BOP 7 RC MOV RC Loop C Tc MOV disc falls into flow stream, Valid First-Out 595, 30% M - All received, No Auto or Manual Reactor Trip. 1-FR-S.1, Response to Nuclear Generation/ATWS.

RD17 SI1502, 8 40% Deg LOCA outside of Containment in Unit 1 Valve Pit Area.

SI1603 M - All SI1606 SI2402 9 SI2405 SI Relay SI2A fails to Actuate, SI Relay SI5A Fails to Actuate; 1-SI-P-1A CC1801 not auto start; MOV-1115D, CH-MOV-115C, CH-MOV1289A, CV-TV-C - BOP 150A, and CH-TV-1204A fail to re-position on SI. 1-CC-P-1A Auto Start Disabled.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Event #1: Deleted.

Event #2: 1-RC-PT-1445 Fails High. (I - RO, TS-SRO)

The RO will respond to the alarms and indications received by performing the Immediate Actions of AP-53.00, Loss of Vital Instrumentations/controls; or 1-AP-31.00, Increasing or Decreasing RCS pressure. RCS pressure is expected to lower to less than 2205 psig for a short time period resulting in a Tech Spec consultation.

Verifiable Actions:

1) RO will place control switch for 1-RC-PCV-1456 in close.
2) BOP may place Rod Control in manual to stop rod motion caused by the reactivity inserted by the pressure coefficient.
3) RO will close 1-RC-MOV-1535 due to Technical Specification requirements.

Technical Specifications:

1) The SRO will consult Tech Specs, TS Section 3.1.A.6, and determine that 1-RC-PCV-1456 is Inoperable but capable of being manually cycled, and enter a one hour clock to close the block valve for the PORV. The block valve will remain energized.
2) Further consultation will find Tech Spec 3.12.F.1 to restore RCS pressure >2205 psig in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce Thermal Power to less than 5% in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The Core Operating Limits Report (COLR, DRP-21) provides the reference for 2205 psig RCS pressure.

Technical Requirements Manual/R.G. 1.97

1) No TRM or R.G. 1.97 requirements apply.

Event #3: Steam Pressure Channel III Fails High on B steam line causing B steam flow increase and B FRV to open. (I - BOP, TS - SRO)

The BOP will respond to the alarms and indication received by placing the B FRV in manual and restoring B SG NR level to program IAW 1-AP-53.00, Loss of Vital Instrumentation/Controls. The Abnormal Procedure will require the Controlling Steam Flow channel to be swapped to Channel IV so that the B FRV can be restored to Auto.

Verifiable Actions:

1) BOP will place the B FRV in manual and restore B SG NR level to program.
2) RO will shift controlling channel.

Technical Specifications The SRO should consult Tech Specs and determine the following:

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4

1) Tech Specs Section 3.7, Table 3.7-1, Item 17, Low steam generator water level with steam/feedwater flow mismatch, Operator Action 6. With the number of Operable channels on less than the total number of channels, Power Operation may proceed provided the channel is placed in the trip condition in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the channel may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance; if these requirements are not met, the Unit must be placed in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2) Tech Spec 3.7, Table 3.7-2, Item 1.c., High differential pressure between any steam line and the steam header, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the channels may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to less than 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3) Tech Spec 3.7, Table 3.7-2, Item 1.e.1 and 1.e.3, High Steam line flow in 2/3 steam lines coincident with low Tavg or low line pressure, Operator Action
20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the channels may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to less than 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4) Tech Spec Table 3.7-3, item 2a, Steam Line Isolation. Refers to Tech Spec Table 3.7-2, Item 1.e. See Above.
5) Tech Spec Table 3.7-6, Item 16, SG Pressure, 2 per SG are required. This condition is met.

Technical Requirements Manual/R.G. 1.97:

1) The TRM Section 3.3 2, Appendix R Instrumentation, Table 3.3.2-1, Steam Generator Pressure 1-MS-PI-1485 is a Primary indicator. One of the three listed transmitters must be Functional to meet the requirement. Two of the three are Functional. No TRM requirements for this failure. (The TRM review is normally performed by the STA in consultation with the Shift Manager; if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).

RG-1.97

1) RG-1.97 variables, Steam Generator pressure is an A-02 variable, 2 channels per SG are required, table refers to Tech Spec Table 3.7-6. (The RG 1.97 review is normally performed by the STA in consultation with the Shift Manager; if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).

Event #4: VCT Level Transmitter LT-115 Fails High. (I - RO)

The RO is expected to diagnose this failure based upon alarms and indications received.

The RO will perform the Immediate Action Steps of 0-AP-53.00, Loss of Vital Instrumentation/Controls and place the VCT divert valve, 1-CH-LCV-1115A, in the NORM position to stop divert of Letdown flow to the PDTT. The Team will continue through the abnormal procedure.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Verifiable Actions:

1) RO will place the control switch for 1-CH-LT-1115A in the NORM position to stop letdown diversion to the PDTT.

Technical Specifications:

1) There are no Tech Spec or TRM actions required for this failure.

Technical Requirements Manual:

1) None for this failure.

Reg. Guide 1.97:

1) RG 1.97 requirements: 1-CH-LI-1115 is a D-29 variable, Category 2. 1 channel is required. Required Action C from Attachment 2; restore the required channel to functional status and use alternate indication to accomplish this function, if possible (VCT level channel 1-CH-LI-1112 functional and meets this requirement). Completion Time 60 days if no alternate indication available OR on or before the next planned outage if an alternate indication is available. (The RG 1.97 review is normally performed by the STA in consultation with the Shift Manager, if this item is required to be verified by the Evaluator, it is recommended to be performed as a follow-up after scenario end).

Event #5: Overcurrent of the B CC pump with the Breaker Stuck closed, resulting in the trip of the stub bus breaker 15J9 on overcurrent. (C - BOP, TS-SRO)

The BOP is expected to diagnose this failure based on alarms and indications received.

The BOP will place the B CC pump in PTL.

Verifiable Actions:

1) BOP will place the control switch for 1-CC-P-1B in PTL.
2) BOP will start 1-CC-P-1A.

Technical Specifications:

1) The SRO will consult Tech Specs 3.13.A.2 and 3.13.B, and determine that the minimum Operable CC pumps requirement is not met. For 2 Unit operation 3 CC pumps must be operable, and TS 3.13.B cannot be met, the SRO should identify a TS 3.01 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> clock to HSD, and a 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> clock to CSD.
2) Consult Tech Spec 3.5.A.1 and determine the Minimum Operable RHR pumps requirement is not met. This requires, IAW TS 3.5.B, that a 14 day clock be entered to restore A RHR pump to an Operable condition.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Technical Requirements Manual

1) IAW IAW TRM 3.7.9.A additional 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clocks are in effect to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status. Normally an STA function in consult with Shift Manager, recommend use of follow up question.

Event #6: Dropped Control Rod, M-4, Control Bank C, Group 1. (C - RO, R - RO, TS - SRO, R

- SRO, N - BOP)

The RO is expected to diagnose this failure based on alarms and indications received and place Rod Control in manual to stop outward rod motion IAW 0-AP-1.00, Rod Control Malfunction.

The Team will continue in AP-1.00 to the point where 0-AP-23.00, Rapid Load Reduction will be used to reduce reactor power to 70-74% to meet the TS requirement to be <75%

of Rated Power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Verifiable Actions:

1) RO will place rod control in manual.
2) BOP will perform actions of Annunciator Response Procedure 1G-F8, Bank D WITHDRAWAL to realign group step counters.

Technical Specifications:

1) The SRO will determine that the dropped control rod is Inoperable since it is misaligned from its Bank > +/- 12 steps. IAW Tech Spec 3.12.C.3, power must be reduced to < 75% Rated Power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and the High Neutron Flux trip setpoint shall be reduced to 85% of Rated Power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2) Shutdown margin must be determined to be satisfactory within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
3) Hot channel factors are shown to be within limits of TS 3.12.B.1 in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and it shall be demonstrated that the value of Fxy(Z) used in the Constant Axial Offset Analysis is still valid.
4) Reevaluation of each accident analysis of Table 3.12-1 is performed within 5 days, to confirm the previous analysis of these accidents remain valid.
5) If, except for operation at THERMAL POWER < 50% or for physics and control rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2%, then:
a. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either the hot channel factors shall be determined and the power level adjusted to meet the requirement of Specification 3.12.B.1, or

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4

b. The power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
6) If the QUADRANT POWER TILT exceeds 10%, the power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Event #7: Tcold Loop stop disc detaches and drops into the flowstream, Valid First-Out indication, No automatic or manual reactor trip, FR-S.1. (M - ALL)

This Event begins the Major Accident sequence. The RO will identify a First-Out alarm is received, the alarm is valid (Low Flow Condition in C RCS Loop), the reactor has not automatically tripped, attempt a manual reactor trip, and then perform the Immediate Action of 1-FR-S.1, Response to Nuclear Power Generation/ATWS.

The reactor trip breakers will be opened locally two (2) minutes after the Team directs an Operator to perform this action (based upon time critical operator action time requirement for locally tripping the reactor trip breakers).

The Team will complete 1-FR-S.1, transition to 1-E-0, Reactor Trip or Safety Injection to perform the Immediate Operator Actions, Transition to 1-ES-0.1, Reactor Trip Response, and perform a brief.

Verifiable Actions:

1) RO will attempt to trip the reactor using both reactor trip pushbuttons.
2) RO will check or place rods control in automatic.
3) RO will manually trip the turbine.
4) RO verifies control rods inserting at >48 steps per minute.
5) When rod speed lowers to < 48 steps per minute; RO places rod control in manual and inserts rods.

Critical Task:

CT-1: DRP-049 E-12, Insert negative reactivity into the core by at least one of the following methods before completing the Immediate Action Steps of FR-S.1.

Insert Control Rods in auto or manual within 30 seconds of the onset of the ATWS event.

Event #8: LOCA Outside of Containment. (M - ALL)

The Team will be alerted to this condition based upon alarms and indications received, return to 1-E-0, and manually Safety Inject.

The RO and SRO continue with E-0 while the BOP performs Attachments 1, 2, and 3 of E-0. The Team will transition from 1-E-0 to 1-ECA-1.2, LOCA Outside Containment. In 1-ECA-1.2, the LOCA will be isolated by closing 1-SI-MOV-1890C, common LHSI pump discharge to RCS Cold Legs. The Team will transition to 1-E-1, Loss of Reactor or Secondary Coolant.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Verifiable Actions:

1) RO will manually initiate SI.
2) During performance of 1-E-0 Attachments the BOP will identify and correct the following items: 1-SI-P-1A not auto start, 1-CH-MOV-1115D not auto open, 1-CH-MOV-1115C not auto close, 1-CH-MOV-1289A not auto close, 10CV-TV-150A and 1-CH-TV-1204A not auto close.

Critical Task:

CT-2: Critical Task: E 1.2. Trip all RCPs within 5 minutes of reaching RCP Trip Criteria. (WOG E-1-C).

CT-3: WOG ECA-1.2A, Isolate the LOCA outside containment before transition out of ECA-1.2, or cavitation of any LHSI pump. SPS- Isolate LOCA outside containment before transition out of ECA-1.2 (PSA).

Post Scenario Classification:

Follow-up Classification: Site Area Emergency, FS-1.1.

The Scenario can be terminated upon 1-E-1 entry or Lead Evaluator Cue.

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 Initial Conditions: IC #1 100%, MOL - Cycle 26. The unit has been at 100% power for > 30 days Pre-load malfunctions: (Trigger 30s) o SI2402, SI RELAY SI2A FAILS TO ACTUATE o SI2405, SI RELAY SI5A FAILS TO ACTUATE o AAC_SMS_MODE, OFF, AAC DG LOCAL MODE SWITCH POSITION o CC1801, DISABLE CCP1A AUTO START o SW_25J10_RF, 1-CC-P-1D CONTROL SWITCH, PTL Equipment Status/ Procedures/ Alignments/ Data Sheets/ etc.:

Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:

AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

1-CC-P-1D id tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.

Turnover:

Unit 1 and 2 operating at 100% power. All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days. . IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.
  • 1-CC-P-1D, D CC pump tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.
  • Last Shift performed two (2) 35 gallon alt dilutes followed by a manual makeup for training.
  • A BAST at 8.0 W/%.

Event Malf. #s Severity Instructor Notes and Required Feedback 1 N/A N/A Deleted.

2 RC4802, +1 Deg 1-RC-PT-1445 fails high, PRZR Pressure channel fail high. AP-31.00, Increasing or Decreasing RCS Pressure.

3 MS1305, +1 Deg Steam Pressure Channel III, B SG fails High. 0-AP-53.00, Loss of Vital Instrumentation/Controls.

4 CH2101, +1 Deg Failure of VCT Level Channel LT-115 High.

CC0302 TRUE 5 CC0802 Overcurrent on B CC pump with breaker mechanically stuck closed causing the TRUE trip of Stub Bus Supply breaker.

SW_15J9_

RF TRIP 6 RD1236 Dropped Rod Control Bank C, Group 1; AP-1.00, Rod Control Malfunction, AP-TRUE 23.00, Rapid Load Reduction.

7. RC MOV 30%

RC Loop C Tc MOV disc falls into flow stream, Valid First-Out received, No Auto 595 or Manual Reactor Trip. 1-FR-S.1, Response to Nuclear Generation/ATWS.

TRUE RD17 SI1502, 40% Deg 8 SI1603 TRUE LOCA outside of Containment in Unit 1 Valve Pit Area.

SI1606 TRUE

Appendix D Scenario Outline Form ES-D-1 NRC EXAM - SCENARIO #4 9 SI2402 SI Relay SI2A fails to Actuate, SI Relay SI5A Fails to Actuate;1-SI-P-1A not auto SI2405 C - BOP start, CH-MOV-1115D, CH-MOV-115C, CH-MOV1289A, CV-TV-150A, and CH-TV-1204A fail to re-position of SI.

Scenario Objectives:

A. Deleted.

B. Given a failure of 1-RC-PT-1445 in the high direction respond IAW AP-53.00/AP-31.00 to regain control of RCS pressure.

C. Given the failure of Steam Pressure Channel III, B SG fails High repons IAW 0-AP-53.00, Loss of Vital Instrumentation/Controls.

D. Given the failure of VCT level 1-CH-LI-1115 high, respond IAW AP-53.00 to secure the divert of letdown flow to the PDTT.

E. Given the loss of the 1J stub bus, respond IAW 1K-H4 to restore CC flow to normal on Unit 1.

F. Given a dropped rod, respond IAW AP-1.00 and AP-23.00 to ramp the Unit to 70-74%.

G. Given a valid reactor trip signal with no automatic reactor trip respond IAW FR-S.1 to shutdown the reactor.

H. Given a LOCA outside of Containment respond IAW E-0 and ECA-1.2 to isolate the RCS leak path.

I. Given various component failing to reposition utilize E-0 Attachments to identify and place the components in the correct position.

SHIFT TURNOVER INFORMATION OPERATING PLAN:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

  • 1-CC-P-1D is tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training.

A BAST at 8.0 W/%.

PSA is Green.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 1 Page 11 of 98 Event

Description:

Perform 1-OP-RP-001. Section 5.2, Preparation for Channel II Testing.

Cue: When team ready.

Time Position Applicants Action or Behavior EVENT 1 - Deleted

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 12 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

Note: An unanticipated critical task may be created in a scenario should a Candidates action or lack of action cause an unexpected RPS or ESFAS actuation. A critical task may be assigned and graded as unsatisfactory even if corrected by another Team member prior to the unanticipated RPS/ESFAS actuation. Should the Candidate self-correct the action or inaction prior to the unanticipated plant response, a critical task failure should not be assigned to the Candidate.

The Assigned Evaluator shall use follow-up questioning to document the Candidates action or lack of action so that the Evaluation Team may determine the grading of the issue.

A facility representative will be present for consultation with the Evaluation Team, as needed.

Time Position Applicants Action or Behavior RO Diagnoses the event using the following:

Alarms:

1C-F8, PRZR HI PRESS 1D-H4, PRZR SFTY VV PWR RELIEF VV OPEN Indications:

1-RC-PCV-1456, PRZR PORV, RED Open Lights LIT.

RCS Pressure Decreasing.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS Note: SRO may directly enter 1-AP-31.00, Increasing or Decreasing RCS Pressure, Page 14.

RO [1] Check REDUNDANT INSTRUMENT CHANNEL(S) INDICATION - NORMAL Identifies RCS Pressure decreasing using 1-RC-PI-1444 or RCS Wide Range Pressure Indicated on A / B ICCM Display.

RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION Places 1-RC-PV-1456 control switch in Close. Verifies 1-RC-PCV-1456 closes by GREEN Light LIT, RED Light off.

RO/BOP During pressure transient, the Rod Control Switch may be placed in MANUAL due to Rods stepping OUT due to pressure coefficient.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 13 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00 SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

  • PRZR Pressure Control, Step 5 RO The RO will identify that 1-RC-PI-1445 failed high.

NOTE: RCS pressure decrease will cause a slight decrease in RCS Tave due to negative reactivity from the moderator pressure coefficient.

SRO 5 CHECK PRZR SPRAY VALVE CONTROLLERS - NORMAL RO RO identifies PRZR Spray Valves controllers normal.

SRO 6 GO TO ( )-AP-31.00, INCREASING OR DECREASING RCS PRESSURE SRO announces transition to AP-31.00.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 14 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 1-AP-31.00 SRO [ 1 ] ___ CHECK PRZR PORVS - CLOSED RO Identifies 1-RC-PCV-1456 closed.

1-AP-31.00 Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-31.00 1-AP-31.00 CAUTION: A Safety Injection may occur if the unit is not tripped prior to RCS pressure decreasing below 2100 psig.

SRO 2 CHECK RCS PRESSURE - DECREASING RO Identifies RCS Pressure rising following PORV Closure.

2 RNO IF RCS pressure is stable or increasing following PORV closure, THEN GO TO Step 10.

Note: If the RO responds to Step as conditions were prior to PORV closure, this flow path is incorrect and a follow-up may be required.

1-AP-31.00 SRO 10 CHECK RCS PRESSURE - STABILIZING AT OR TRENDING TO 2235 PSIG RO Identifies RCS pressure trending to 2235 psig.

1-AP-31.00 SRO 11. GO TO STEP 17

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 15 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

1-AP-31.00 SRO 17 CHECK MASTER CONTROLLER GO TO Step 19

- IN MANUAL RO Identifies Master Pressure Controller in Auto 1-AP-31.00 SRO 19 CHECK PRZR PORVS - EITHER INOPERABLE

  • 1-RC-PCV-1455C

1-AP-31.00 20 CLOSE BLOCK VALVE FOR INOPERABLE PORV SRO

  • 1-RC-MOV-1535 if 1-RC-PCV-1456 inoperable RO Places 1-RC-MOV 1535 control switch in close. Monitors MOV until GREEN indicating light LIT and RED Light out.

1-AP-31.00 SRO 21 CHECK PRZR PORVS - EITHER GO TO Step 23 INCAPABLE OF BEING MANUALLY CYCLED

  • 1-RC-PCV-1455C
  • 1-RC-PCV-1456 RO States Both PORVs are capable of being manually cycled.

1-AP-31.00 SRO 23 NOTIFY THE FOLLOWING:

  • OM on call
  • I&C Notifies Shift Manager of the Event and requests notifications be made.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 2 Page 16 of 98 Event

Description:

1-RC-PT-1445 Fails High, 1-AP-31.00/0-AP-53.00.

Cue: By Examiner.

1-AP-31.00 SRO 24 REFER TO TECH SPECS:

  • 3.1.A.5
  • 3.1.A.6
  • 3.1.C
  • 3.12.F
1) The SRO will consult Tech Specs, TS Section 3.1.A.6, and determine that 1-RC-PCV-1456 is Inoperable but capable of being manually cycled, and enter a one hour clock to close the block valve for the PORV. The block valve will remain energized.
2) Further consultation will find Tech Spec 3.12.F.1 to restore RCS pressure >2205 psig in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce Thermal Power to less than 5% in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The Core Operating Limits Report (COLR, DRP-21) provides the reference for 2205 psig RCS pressure.

NOTE: Following closure of block valve the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tech Spec clock clears. RCS pressure decreases to < 2205 psig during the transient; once the PORV has been closed, pressure recovers quickly and goes above 2205 psig.

SRO updates the Team concerning the identified items in Tech Specs and updates the Shift manager.

1-AP-31.00 SRO 25 REVIEW APPLICABILITY:

  • VPAP-2802
  • EAL Matrix SU6.1 SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.

1-AP-31.00 SRO 26 RESTORE PRESSURE CONTROL SYSTEM(S) TO NORMAL END EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 17 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior 0-AP-53.00 BOP Diagnoses failure 1-MS-PT-1485 with the following indications/alarms:

Alarms:

Indications:

  • Step increase in 1B SG Steam Flow indication CH-III
  • Increasing level on B SG.

0-AP-53.00 SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS 0-AP-53.00 BOP [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL BOP identifies Channel IV indication for steam flow/Steam Pressure is NORMAL 0-AP-53.00 BOP [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION BOP takes manual control of B SG feed reg valve and lowers demand (FF < SF) to restore level to program

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 18 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00.

0-AP-53.00 SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

Note: Based on the feed flow > steam flow mismatch during initial stage of the Event, Calorimetric power may exceed 100% during restoration of B SG NR level to program.

0-AP-53.00 SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

0-AP-53.00 SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

SG Pressure, Step 7 BOP States B SG Pressure affected.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 19 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 CAUTION: When CALCALC is based on Feedwater, changes in feed flow will affect calorimetric power. Reactor power must be monitored when adjusting feed flow.

SRO 7. CHECK STEAM GENERATOR LEVEL CONTROL INSTRUMENTS -

NORMAL

  • Steam Pressure
  • Steam Flow
  • Feed Flow

Step 7. RNO IF the selected steam flow, steam pressure, or feed flow input to the SG Water Level Control system has failed, THEN do the following:

a) Place the associated Feed Reg Valve in MANUAL.

BOP Verifies B SG MFRV controller, 1-FW-FCV-1488, in manual b) Control SG level at program level (44%, a band will be given).

BOP Verifies B SG NR level is returning to program level.

c) Select the redundant channel for affected SG(s)

RO Selects Channel IV Steam Flow for B SG using two-position selector switch on Vertical Board 1-2 (applicant may also place the associated Steam Flow channel in Channel IV).

d) WHEN SG level returned to normal, THEN place the Feed Reg Valve in AUTOMATIC.

BOP Places B SG FRV controller, 1-FW-FCV-1488, in automatic control

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 20 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO Step 7. RNO (Continued)

Perform follow-up actions:

a) Consult with Shift Manager on need to initiate ( )-OP-RP-001, ALIGNING CONTROL SYSTEM FOR PERFORMANCE OF CHANNEL I, II, III, AND IV PROCESS AND PROTECTION TESTING.

b) Refer to the following Tech Spec 3.7 items:

  • Table 3.7-1, 12 and 17
  • Table 3.7-2, 1.c, 1.e, and 3.a
  • Table 3.7-3, 2.a, and 3.a
1) Tech Specs Section 3.7, Table 3.7-1, Item 17, Low steam generator water level with steam/feedwater flow mismatch, Operator Action 6. With the number of Operable channels one less than the total number of channels, Power Operation may proceed provided the channel is placed in the trip condition in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the channel may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance; if these requirements are not met, the Unit must be placed in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2) Tech Spec 3.7, Table 3.7-2, Item 1.c., High differential pressure between any steam line and the steam header, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the channels may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to less than 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3) Tech Spec 3.7, Table 3.7-2, Item 1.e.1 and 1.e.3, High Steam line flow in 2/3 steam lines coincident with low Tavg or low line pressure, Operator Action 20. With the number of Operable channels less than the total number of channels, Operation may continue provided the failed channel is placed in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; the channels may be bypassed for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing; and if the requirements cannot be met, be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS temperature and pressure to less than 350°F/450 psig in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4) Tech Spec Table 3.7-3, item 2a, Steam Line Isolation. Refers to Tech Spec Table 3.7-2, Item 1.e. See Above
5) Tech Spec Table 3.7-6, Item 16, SG Pressure, 2 per SG are required. This condition is met (2 of 3 channels still Operable).

c) Refer to Attachment 1.

d) IF no other instrumentation failure exists, THEN GO TO Step 13.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 21 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO 13. CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001.

SRO/RO reviews OPT-RX-001, Attachment 4, and determines Calorimetric is NOT impacted and OPT-RX-007 will NOT need to be performed.

0-AP-53.00 SRO 14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 VARIABLE (Go to Step 16 if not Reg. Guide 1.97)

SRO directs STA to review Reg. Guide 1.97. The STA will report that 1-MS-PT-1485 is a Reg. Guide 1.97 component.

0-AP-53.00 SRO 15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.

[CEP 99-0029 requires two channels of Steam Pressure indication per steam generator, refers to Tech Spec 3.7, Table 6, Item 16, 2 required per SG.]

0-AP-53.00 SRO 16. Review the following:

  • TS 3.7 Determines Table 3.7-1 item 17, 3.7-2 item 1.c. and 1e, and 3.7.3 item 2a are applicable (place channel in trip w/in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). Also TS-3.7, Table 6, item 16, two SG Pressure Indicators per SG.
  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

[VPAP-2802 and TRM Section 3.3 are not impacted by this failure.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 3 Page 22 of 98 Event description: Steam Pressure Channel III, B SG Fails High, 0-AP-53.00.

Cue: By Examiner.

0-AP-53.00 SRO 17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS BOP Reports no additional failure exists SRO GOES TO Step 19 0-AP-53.00 SRO 19. PROVIDE NOTIFICATIONS AS NECESSARY:

  • Shift Supervision
  • OMOC
  • I&C END EVENT #3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 4 Page 23 of 98 Event

Description:

Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.

Cue: When initiated by Team Time Position Applicants Action or Behavior Diagnoses failure 1-CH-LT-1115 with the following indications/alarms:

BOP Alarms:

  • 1-CH-LCV-1115A Amber Divert light LIT.
  • Decreasing VCT level on channel 1-CH-LI-1112.

SRO Enters 0-AP-53.00 LOSS OF VITAL INSTRUMENTATION / CONTROLS RO [1] CHECK REDUNDANT INSTRUMENT CHANNEL(S) INDICATION -

NORMAL RO identifies Channel LI-1112 VCT Level indication is NORMAL.

RO [2] PLACE AFFECTED CONTROL(S)/COMPONENT(S) IN MANUAL CONTROL AND STABILIZE PARAMETER USING REDUNDANT INDICATION RO places the control switch for 1-CH-LCV-1115A in NORM position to close the VCT Divert Valve. Monitors to ensure amber light extinguishes and VCT level stabilizes.

SRO Conducts a Brief summarizing the Event and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Completes Brief and continues with AP-53.00.

SRO Note: Discusses with RO control of VCT level and monitoring of channel 1-CH-LT-1112 to ensure that VCT level will not drop to the point where the CH pumps could air bind. The SRO will set a band for manual makeup to the VCT and a minimum VCT level where the manual swap to the RWST will be required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 4 Page 24 of 98 Event

Description:

Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.

Cue: When initiated by Team SRO *3 VERIFY REACTOR POWER - LESS THAN OR EQUAL TO 100%

RO Identify that reactor power is less than 100%.

SRO Notes Prior to Step 4:

  • Step 4 failures are listed in order of performance priority. Only the failed instrument/control and associated step number should be read aloud.
  • When the affected instrument/controller malfunction(s) has been addressed by this procedure, recovery actions should continue at Step 13.

SRO *4 DETERMINE THE FAILED INSTRUMENT / CONTROL AND GO TO APPROPRIATE STEP OR PROCEDURE:

VCT Level, Step 12e RO SRO 12 e) VCT level Instrumentation - NORMAL RO States 1-CH-LT-1115, VCT Level Channel affected.

SRO Refer to Attachment 6 Attachment 6, 0-AP-53.00 SRO If ( )-CH-LT-( )115 fails high, ( )-CH-LCV-( )115A will open. Manual control of the blender will be required. Automatic swap-over of the CHG pump suction from the VCT to the RWST will not function.

a. VCT High level divert of ( )-CH-LCV-( )115A to PDT at 85%
b. VCT High level alarm at 82%
c. Auto makeup to VCT stop at 34%
d. Auto makeup to VCT start at 27%
e. VCT Low level alarm at 24%
f. CHG pump suction swap over to the RWST at 13% (2/2)

SRO Note: Discusses with RO control of VCT level and monitoring of channel 1-CH-LT-1112 to ensure that VCT level will not drop to the point where the CH pumps could air bind. The SRO will set a band for manual makeup to the VCT and a minimum VCT level where the manual swap to the RWST will be required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 4 Page 25 of 98 Event

Description:

Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.

Cue: When initiated by Team SRO 13 CHECK CALORIMETRIC - FUNCTIONAL IAW ( )-OPT-RX-001 SRO/RO SRO/RO determines that OPT-RX-001, Attachment 4, is NOT impacted and OPT-RX-007 will NOT need to be performed.

14. CHECK FAILED INSTRUMENT - IS A REGULATORY GUIDE 1.97 SRO VARIABLE (Go to Step 16 if not Reg. Guide 1.97)

The STA will report that 1-CH-LI 1115 is a Reg. Guide 1.97 component.

SRO 15. REVIEW CEP 99-0029, REG GUIDE 1.97 OPERABILITY, REPORTABILITY, AND ALTERNATE INDICATIONS SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.

[CEP 99-0029 requires 1 channel of VCT level indication. 1-CH-LT-1112 may be used as an alternate indication. Restore 1-CH-LT-1115 before the next outage.]

SRO 16. Review the following:

  • VPAP-2802
  • TRM Section 3.3, Instrumentation SRO SRO will consult Tech Specs and find no items affected.

SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.

[VPAP-2802 and TRM Section 3.3 are not impacted by this failure.]

0-AP-53.00 SRO 17 CHECK ADDITIONAL INSTRUMENT / CONTROLLER MALFUNCTION -

EXISTS BOP Reports no additional failure exists SRO GOES TO Step 19

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 4 Page 26 of 98 Event

Description:

Failure of VCT Level Channel LT-1115, High, 0-AP-53.00.

Cue: When initiated by Team

19. PROVIDE NOTIFICATIONS AS NECESSARY:

SRO

  • Shift Supervision
  • OMOC
  • I&C END EVENT #4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 27 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

Time Position Applicants Action or Behavior TEAM Diagnose the failure using the following:

Alarms:

1K-D5, CC PP 1B IN LOCAL CONTROL OR OL TRIP 1K-E7, CC PPS DISCH HDR LO PRESS 1K-H4, 4KV EMERG BUS STUB BUS TIE BKR TRIP Indications:

Breaker 15J9, 1J Stub Bus Breaker, indicates Open on PCS Breaker 15J10, 1-CC-P-1B breaker indication RED and GREEN Light OFF.

1-CC-P-1B amps indication at 0. 1-CC-P-1A not running.

Note: ARP Steps start on Page 30.

Note: If the Team opts to trip the reactor, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-AP-10.07 SRO SRO will hold a Transient Brief and Establish priorities.

RO will provide Critical Parameters using Brief Placard.

BOP will provide Critical Parameters using Brief Placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. STA will also state that containment conditions and the electrical conditions are as you see them.

Directs the BOP to review ARPs for Lit annunciators, SRO/RO will continue with 1-AP-10.07.

Directs RO/BOP to contact Auxiliary Building Operator to check status of 1-CC-P-1A and 1-CC-P-1B. Direct Service Building Operator to check status of 1-CC-P-1B breaker, BKR 15J10, and the 1J stub bus breaker, 15J9.

Completes Brief and continues with AP-10.07.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 28 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

Step 1, 1-AP-10.07 SRO NOTE:

  • If both units are affected, local actions should be coordinated.
  • The AAC Diesel Generator will automatically start if an undervoltage occurs on Transfer Buses D and F.
  • With Degraded Voltage or Undervoltage on 2J Bus, or a loss of Unit 2B DC Bus, Breaker 15J3 will not close automatically, except with a valid Unit 1 SI signal.
1. CHECK UNIT - BLACKOUT HAS OCCURRED
  • Transfer Buses D and F - DEENERGIZED AND
  • All Station Service Buses - DEENERGIZED RO Reports Blackout has not occurred.

SRO GOES TO Step 39.

Step 39, 1-AP-10.07 SRO 39 CHECK THE FOLLOWING BREAKERS - ANY OPEN:

  • 15J8 RO Reports Breakers Closed.

39 RNO IF all 480V Emergency Buses energized, THEN GO TO Step 75.

SRO Goes to Step 75.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 29 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

Step 75, 1-AP-10.07 SRO 75 CHECK ANY STATION SERVICE BUS - DEENERGIZED:

  • 15A1 and 15A2 - OPEN OR
  • 15B1 and 15B2 - OPEN OR
  • 15C1 and 15C2 - OPEN RO Reports breakers 15A2 / 15B2 / 15C2 closed.

SRO 75 RNO IF ALL 480V Station Service Buses are energized, THEN GO TO Step 97.

SRO Goes to Step 97.

Step 97, 1-AP-10.07 SRO 97 NOTIFY THE FOLLOWING:

  • OMOC
  • Electrical Foreman ARP 1K-D5 BOP 1 CHECK 1-CC-P-1B IN LOCAL CONTROL DUE TO PLANT EVOLUTION 1-CC-P-1B not in Local due to Plant Evolution.

No Plant evolution in progress.

IF 1-CC-P-1B tripped due to leak or rupture, THEN do the following:

No leak or rupture indicated.

IF leak or rupture NOT present, THEN GO TO Step 3.

Go to Step 3

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 30 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

ARP 1K-D5 BOP 3. VERIFY STANDBY CC PP - STARTED

  • 1-CC-P-1A No, 1-CC-P-1A not running Consults SRO concerning Manual start of 1-CC-P-1A.

Announces and Starts 1-CC-P-1A.

ARP 1K-D5 BOP 4 CHECK 1-CC-P-1B - TRIPPED DUE TO UNDERVOLTAGE ON THE 1J EMERGENCY BUS Do the following:

a) IF CC pump NOT tripped, THEN do the following:

b) Locally check breaker 15J10.

c) Locally check 1-CC-P-1B.

BOP When local status of 1-CC-P-1B received, Focus Brief to inform Team that 1-CC-P-1B normal; 1-CC-P-1B breaker is closed, breaker 15J10 closed with an overcurrent trip flag, breaker 15 J9, stub bus breaker, is open with an overcurrent trip flag.

d) IF unable to restore 1-CC-P-1B, THEN do the following:

1) Initiate a Condition Report.
2) Review Tech Spec 3.13.
3) GO TO Step 7.

ARP 1K-D5 BOP 7 VERIFY CC SYSTEM PARAMETERS - NORMAL

  • CC Surge Tank Level - STABLE
  • CC Pump amps - STABLE
  • AUX BLDG and CTMT Sump levels - NORMAL Review parameters, identify no trends exist, report parameters as normal.

ARP 1K-D5 BOP 8 PROVIDE NOTIFICATIONS:

  • OMOC

Move to next ARP.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 31 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

ARP 1K-E7 BOP 1 VERIFY CC HEADER PRESSURE - LESS THAN 90 PSIG

  • PI-CC-100, CC PP DISCH PRESS Reports PI-CC-100 indicates approximately 100 psig.

Step 1 RNO Do the following:

a) Increase surveillance of CC parameters.

b) Initiate a Work Request.

c) GO TO Step 18.

ARP 1K-E7 BOP 18 NOTIFY SHIFT SUPERVISION Notifies SRO, ARP 1K-E7 complete, a CR is required.

Moves to 1K-H4 ARP ARP 1K-H4 BOP 1 VERIFY ALARM - LOSS OF EMERGENCY BUS

  • Bus 1H Undervolt - 15H8 TRIPPED OR
  • Bus 1J Undervolt - 15J8 TRIPPED Identifies 1H and 1J not tripped Step 1 RNO Do the following:

a) Check for loss of Stub Bus loads:

  • RHR Pump Identifies Stub bus loads have been lost.

Step 1 RNO b) IF Stub Bus loads lost, THEN do the following:

1) Start standby pumps IAW Shift Supervision direction.
2) Locally check stub bus tie breaker cubicles in ESGR.
3) IF Stub Bus Breaker Cubicle Relays (Type IAC) orange drop - IN, THEN GO TO Step 4.

Based on Focus Brief - Goes to Step 4.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 32 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

ARP 1K-H4 BOP 4 CHECK RHR AND CC - RESTORED AS NECESSARY Identifies 1-CC-P-1A running.

ARP 1K-H4 BOP 5 PROVIDE NOTIFICATIONS AS NECESSARY:

  • OMOC
  • Electrical Foreman
  • Control Operations
  • Shift Supervision Notifies SRO that in addition to previous individuals notified, the Electrical Forman needs to be notified ARP 1K-H4 BOP 6 SUBMIT A CONDITION REPORT Notifies SRO that a CR is required.

ARP 1K-H4 BOP 7 REVIEW TECH SPECS Notifies SRO to Review Tech Specs SRO The SRO will consult Tech Specs 3.13.A.2 and 3.13.B, and determine that the minimum Operable CC pumps requirement is not met. For 2 Unit operation, 3 CC pumps must be operable, and TS 3.13.B cannot be met, the SRO should identify a TS 3.01, 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> clock to HSD, and a 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> clock to CSD.

Consult Tech Spec 3.5.A.1 and determine the Minimum Operable RHR pumps requirement is not met. This requires, IAW TS 3.5.B, that a 14 day clock be entered to restore A RHR pump to an Operable condition.

[TRM Table 3.7.9-1; IAW TRM 3.7.9.A, additional 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clocks are in effect to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.]

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2012-1 Scenario No.: 4 Event No.: 5 Page 33 of 98 Event

Description:

1-CC-P-1B overcurrent with breaker stuck shut, 15J9 breaker trips open.

Cue: By Examiner.

SRO Directs STA to review Tech Specs and TRM.

STA Acknowledge direction to review Tech Specs and TRM. STA will report TRM has been reviewed and discussed with the Shift Manager.

SRO Contacts the Shift Manager to provide an update on Plant Status, Tech Spec Clocks entered, and request notification of the OMOC and Electrical Foreman.

END EVENT #5

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 34 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

Time Position Applicants Action or Behavior Team Diagnoses the dropped rod with the following indications/alarms:

Alarms:

  • 1G-B5, COMPUTER PRINTOUT ROD CONT SYS.
  • 1G-C4, UPPER ION CHAMBER DEVIATION OR AUTO DEFEAT <50%.
  • 1G-D4, LOWER ION CHAMBER DEVIATION OR AUTO DEFEAT <50%.
  • 1G-H1 - NIS DROPPED ROD FLUX DECREASE > 5% PER 2 SEC
  • 1G-F8, ROD BANK D WITHDRAWAL.

Indications:

RO

  • Outward Rod Motion.
  • RCS Temperature and Pressure decrease.
  • Flux Variations (radial).

In accordance with the immediate actions of 1-AP-1.00 (Rod Control System Malfunction) the RO will place Control Rods in MANUAL to stop the outward rod motion.

RCS pressure <2205 psig places the unit in a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> clock iaw TS. 3.12.F.1 (and COLR) - it is expected that the SRO will track this clock (entry/exit times).

0-AP-1.00 SRO Enters 0-AP-1.00 (Rod Control System Malfunction).

SRO CAUTION prior to Step 1:

  • If Tave decreases below 530 °F, 1-E-0, Reactor Trip or Safety Injection, must be implemented.

RO [1] CHECK FOR EITHER OF THE FOLLOWING:

  • Continuous rod withdrawal
  • Continuous rod insertion RO will note that there was a continuous rod withdrawal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 35 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

RO/BOP [2] STOP ROD MOTION

a. Put ROD CONT MODE SEL switch in MANUAL
b. Verify rod motion - STOPPED RO will place control rods in MANUAL and note that Rods stopped moving.

0-AP-1.00 SRO The team will hold a transient brief. During the brief the dropped rod will be discussed.

The RO and BOP will report out critical parameters, as per placard on Main Control Room Bench Board.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

0-AP-1.00 RO

3. CHECK ROD MOTION - DUE TO INSTRUMENTATION FAILURE
  • First Stage Impulse Pressure
  • Tave/Tref
  • Nuclear Instrumentation RO will note that an instrumentation failure did not exist. The team will transition to the RNO for Step 3.

0-AP-1.00 RO

3. RNO If rod motion due to a dropped rod, THEN GO TO Step 6.

RO will note that dropped rod caused the rod motion.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 36 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

0-AP-1.00 RO

6. CHECK IF ANY ROD DROPPED:

PER 2 SEC - LIT OR

  • Rod Bottom Lights - ANY LIT OR
  • Any Rod On Bottom light - LIT OR
  • Indication of a partially dropped rod in the core The RO will note that they have multiple indications of a dropped rod in the core.

0-AP-1.00 RO

7. CHECK REACTOR STATUS PRIOR TO FAILURE - CRITICAL 0-AP-1.00 RO 8. CHECK ONLY ONE ROD AFFECTED 0-AP-1.00 RO
9. CHECK REACTOR POWER - GREATER THAN 25%

0-AP-1.00 BOP/RO

10. CHECK UNIT CONDITIONS - STABLE 0-AP-1.00 RO
11. PLACE ROD CONTROL IN MANUAL 0-AP-1.00 RO/BOP
12. CHECK POWER RANGE NIs - ANY DROPPED ROD SIGNAL PRESENT 0-AP-1.00 BOP
13. RESET NIS DROPPED ROD SIGNAL IAW ATTACHMENT 4 Note: Attachment 4 of AP-1.00 is located on Page 40.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 37 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

0-AP-1.00 RO

14. CHECK ANNUNCIATOR 1G-F8, ROD BANK D WITHDRAWAL - NOT LIT If alarm is LIT, then the RNO will direct the team to initiate Attachment 5 - This attachment follows attachment 4 at the end of this event.

Note: This may not be lit if the ROBOP quickly placed rods in MANUAL when withdrawing or ARP 1G-F8, Bank D Withdrawal, has been completed.

0-AP-1.00 SRO Note prior to Step 15:

  • Quadrant power tilt may cause unit ramp requirements to be more restrictive.

0-AP-1.00 SRO

15. VERIFY QUADRANT POWER TILT RATIO
  • Initiate Attachment 6, QUADRANT POWER TILT CALCULATION

Summary of applicable Tech Specs are found following Step 18.

0-AP-1.00 SRO Notes prior to Step 16:

  • Checking that the unit is operating between Hot Zero Power and Hot Full Power, that there is only one fully dropped (less than 10 steps) control rod, and that all other rods are above the rod insertion limit, checks that adequate SDM exists.
  • SDM must be re-verified using 1-OP-RX-001 every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the control rod was dropped until the Reactor is shutdown or the rod is declared operable.

0-AP-1.00 SRO

16. VERIFY SHUTDOWN MARGIN (WITHIN ONE HOUR)
  • The fully dropped rod (less than 10 steps) is the only inoperable rod AND
  • All other rods are greater than the Rod Insertion Limit 0-AP-1.00 SRO
17. MAKE NARRATIVE LOG ENTRY THAT SDM IS MET

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 38 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

SRO Caution prior to Step 18:

  • Loop T is the most accurate measure of Reactor power with a mis-aligned rod, and must be monitored during the ramp and used as a basis for stabilizing power.

RO 18. CHECK REACTOR POWER - LESS THAN OR EQUAL TO 75%

Step 18 RNO actions:

Do the following:

a. Reduce Reactor Power to between 70% - 74% within one hour.
b. Reduce NIS High Flux trip setpoints to less than or equal to 85% within the following four hours.
c. WHEN Reactor Power has been reduced, THEN GO TO Step 19.

The team will enter AP-23.00 to reduce reactor power.

Note: 0-AP-23.00, Rapid Load Reduction, actions start on page 42.

Evaluators Note: Go to EVENT 7 when the Examiner has seen a sufficient change in power level during the ramp in AP-23.00.

SRO Applicable Tech Specs for Dropped Rod:

3.12.B.6:

If, except for operation at THERMAL POWER < 50% or for physics and control rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2%, then:

c. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either the hot channel factors shall be determined and the power level adjusted to meet the requirement of Specification 3.12.B.1, or
d. The power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
e. If the QUADRANT POWER TILT exceeds 10%, the power level shall be reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron flux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 39 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

Applicable Tech Specs for Dropped Rod: (Continued) 3.12.C.3:

Startup and POWER OPERATION may continue with one control rod assembly inoperable provided that within one hour either:

a. The control rod assembly is restored to OPERABLE status, as defined in Specification 3.12.C.1 and 2, or
b. the shutdown margin requirement of Specification 3.12.A.3.c is satisfied.
c. POWER OPERATION may then continue provided that:
1) either:

a) power shall be reduced to less than 75% of RATED POWER within one (1) hour, and the High Neutron Flux trip setpoint shall be reduced to less than or equal to 85% of RATED POWER within the next four (4) hours, or b) the remainder of the control rod assemblies in the group with the inoperable control rod assembly are aligned to within 12 steps of the inoperable rod within one (1) hour while maintaining the control rod assembly sequence and insertion limits specified in the CORE OPERATING LIMITS REPORT; the THERMAL POWER level shall be restricted pursuant to Specification 3.12.A during subsequent operation.

2) the shutdown margin requirement of Specification 3.12.A.3.c is determined to be met within one hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 40 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

BOP ATTACHMENT 4 of AP-1.00 - RESETTING NIS DROPPED ROD SIGNALS Perform the following for each NI with a dropped rod status light lit.

1. N41 RESET a) Place the Power Range Test Switch in RESET.

b) Check the Dropped Rod Status Light on N41 - NOT LIT.

c) Return the Power Range Test Switch to NORMAL.

2. N42 RESET a) Place the Power Range Test Switch in RESET.

b) Check the Dropped Rod Status Light on N42 - NOT LIT.

c) Return the Power Range Test Switch to NORMAL.

3 N43 RESET a) Place the Power Range Test Switch in RESET.

b) Check the Dropped Rod Status Light on N43 - NOT LIT.

c) Return the Power Range Test Switch to NORMAL.

4. N44 RESET a) Place the Power Range Test Switch in RESET.

b) Check the Dropped Rod Status Light on N44- NOT LIT.

c) Return the Power Range Test Switch to NORMAL.

5. Check annunciator ( )G-H1, NIS DROPPED ROD FLUX DECREASE >5% PER SEC - NOT LIT
6. Check annunciator ( )G-F8, ROD BANK D WITHDRAWAL - NOT LIT
7. IF ( )G-F8, ROD BANK D WITHDRAWAL is LIT, THEN initiate Attachment 5.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 41 of 98 Event description: Dropped Control ROD, 0-AP-1.00, 0-AP-23.00.

Cue: By Examiner.

BOP ATTACHMENT 5 of AP-1.00 - RESPONSE TO ROD BANK D WITHDRAWAL

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 42 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 0-AP-23.00 TEAM 0-AP-23.00 (RAPID LOAD REDUCTION) Actions SRO The team will hold a transient brief. During the brief, the upcoming ramp will be discussed.

The RO and BOP will report out critical parameters, as per placard on Main Control Room Bench Board. It is expected that the RO will discuss reactivity parameters associated with the ramp from the pre-planned ramp plans taking in account the conditions presented by the dropped rod.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

The following reactivity plan will be discussed for a ramp to 75%:

  • Gallons of boric acid required as per plan - 146 gallons, Rate of 5.8 gpm.
  • D control bank end at 197 steps, 1957 gallons PG to stabilize.
  • Subtracted from the boration will be the equivalent boron added from the dropped rod - 9.5 gallons for each degree of Tave decrease - this should be about 42 gallons based on a 4.4° temp decrease. This will be subtracted from the initial 146 gallons - therefore, approximately 104 gallons of boric acid are required to be added.

EVALUATOR NOTE: RO Emergency borates for 25 seconds which corresponds to

~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.

SRO Caution Prior to Step 1:

  • Conservative decision-making must be maintained during rapid load reductions. Refer to Attachment 1 for trip criteria.

Notes Prior to Step 1:

  • Actions that can be completed independently of preceding steps may be performed out of sequence as directed by the SRO
  • When the Turbine is not being actively ramped, the REFERENCE and SETTER values must remain matched to prevent inadvertent ramp.
  • Pre-planned reactivity plans located in the Main Control Room will be used as guidance for ramping down to the desired power level.
  • The ramp rate in IMP OUT is nonlinear and therefore pre-planned reactivity plans based on IMP IN are not as accurate. However, total amounts of boration and dilution can be used as guidance.
  • For ramp rates greater than or equal to 1%/minute, Rod Control should remain in Automatic if available.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 43 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

0-AP-23.00 RO 1. TURN ON ALL PRZR HEATERS

2. INITIATE PLANT LOAD REDUCTION AT 2%/MINUTE OR LESS:

BOP a) Check turbine valve position - NOT ON LIMITER The turbine is NOT on the limiter.

RO b) Insert control rods in AUTO or MANUAL as necessary to maintain Tave and Tref within 5°F.

SRO/BOP c) Check or place turbine in IMP IN as determined by Shift Supervision The SRO can choose IMP IN or IMP OUT.

d) Adjust SETTER to desired power level BOP e) Adjust LOAD RATE %/MIN thumbwheel to desired ramp rate (1%/minute) f) Initiate Turbine load reduction using OPERATOR AUTO (pushes the GO button) g) Reduce Turbine Valve Position Limiter as load decreases The BOP will periodically reduce the limiter setpoint during the ramp.

SRO 3. CHECK EMERGENCY BORATION - REQUIRED The team may decide to emergency borate after the ramp has progressed to the point that Tave and Tref are matched (or close).

SRO Note Prior to Step 4:

  • Step 4 or Step 5 may be performed repeatedly to maintain Tave and Tref matched, Flux in band, and control rod position above the LO-LO insertion limit.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 44 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

0-AP-23.00 RO 4. PERFORM AN EMERGENCY BORATION IAW THE FOLLOWING:

a) Check or raise CHG flow to greater than 75 gpm b) Transfer the in-service BATP to FAST c) Open ( )-CH-MOV-( )350 d) Monitor EMRG BORATE FLOW

  • ( )-CH-FI-( )110 e) After required emergency boration, perform the following:
1) Close ( )-CH-MOV-( )350
2) Transfer the in-service BATP to AUTO
3) Restore Charging flow control to normal NOTE: RO Emergency borates for 25 seconds which corresponds to ~50 gallons of Boric Acid addition. Blender is set to add remainder of boric acid using normal boration path at a rate adjusted by RO to control Tave/Tref.

RO 5. ESTABLISH A NORMAL BORATION TO MAINTAIN CONTROL ROD POSITION ABOVE THE LO-LO INSERTION LIMITS ATTACHMENT 4 Attachment 4 (Boration) and 5 (Manual Makeups) are at the end of this section.

SRO Notes Prior to Step 6:

  • If at any time plant conditions no longer require rapid load reduction, actions should continue at Step 35.
  • RCS Tave must be maintained less than or equal to 577°F and RCS pressure must be maintained greater than or equal to 2205 psig. Tech Spec 3.12.F.1 should be reviewed if either parameter is exceeded.
  • I & C should be contacted to provide assistance with adjusting IRPIs.

RO 6. CONTROL RAMP RATE TO MAINTAIN RCS PRESSURE GREATER THAN 2205 PSIG

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 45 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

RO *7. CHECK LETDOWN ORIFICES - TWO IN SERVICE Evaluator note: two orifices will already be in service.

BOP 8. MONITOR STEAM DUMPS FOR PROPER OPERATION 0-AP-23.00 SRO 9. NOTIFY THE FOLLOWING:

  • Energy Supply (MOC)
  • Polishing Building
  • Chemistry
  • OMOC SRO 10. EVALUATE THE FOLLOWING:
  • VPAP-2802, NOTIFICATIONS AND REPORTS, applicability SRO directs STA to review VPAP-2802 and EPIP applicability. The STA reports that review of VPAP-2802 and EPIPs are complete and have been reviewed with the Shift Manager.

[VPAP-2802 and EPIP are not applicable for this event.]

SRO 11. CHECK REACTOR POWER - HAS DECREASED MORE THAN 15% IN ONE HOUR When reactor power has decreased >15%, then chemistry will be notified.

END EVENT #6

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 46 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 4 (NORMAL BORATION) Actions RO 1. Place the MAKE-UP MODE CNTRL switch in the STOP position.

RO 2. Adjust 1-CH-YIC-1113 to desired total gallons RO 3. Adjust 1-CH-FC-1113A to desired flow rate.

RO 4. Place the MAKE-UP MOD SEL switch in the BORATE position.

RO 5. Place the MAKE MODE CNTRL switch in the START position.

RO 6. Check proper valve positions.

RO 7. Adjust boration rate using 1-CH-FC-1113A, as necessary.

RO 8. WHEN boration is complete, THEN perform the following. IF boric acid is to remain in the Blender to support ramping the Unit, THEN enter N/A.

a) Manually blend approximately 20 gallons to flush the boration path IAW Attachment 5, Manual Makeups.

b) Enter N/A for the remaining steps in this Attachment.

Attachment 5 is on the next page RO 9. Check controllers for Primary Grade water and Boric Acid are set correctly.

RO 10. Place the MAKE-UP MODE SEL switch in the AUTO position.

RO 11. Place the MAKE-UP MODE CNTRL switch in the START position.

RO 12. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 6 Page 47 of 98 Event

Description:

Dropped Rod, Bank C, Group 1. 0-AP-1.00, 0-AP-23.00.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 0-AP-23.00 Attachment 5 (Manual Makeups) Actions

1. Place the MAKE-UP MODE CNTRL switch in the STOP position.
2. Check controllers for the flow rate of Boric Acid and Primary Grade water are set correctly.
3. Check integrators for the gallons of Boric Acid and Primary Grade water are set correctly.
4. Place the MAKE-UP MODE SEL switch in the MANUAL position.
5. Place the MAKE-UP MODE CNTRL switch in the START position.
6. Open 1-CH-FCV-1113B, BLENDER TO CHG PUMP.
7. Check proper valve positions.
8. WHEN the Manual Makeup operation is complete, THEN place 1-CH-FCV-1 113B in the AUTO position
9. Place the MAKE-UP MODE CNTRL switch in the STOP position.
10. Check or place the control switches in the AUTO position.
11. Check controllers for Primary Grade water and Boric Acid are set correctly.
12. Place the MAKE-UP MODE SEL switch in the AUTO position.
13. Place the MAKE-UP MODE CNTRL switch in the START position.
14. Notify Shift Supervision of blender status.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 48 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

Time Position Applicants Action or Behavior Team Diagnose the failure based on the following:

Alarms:

1E-B10, LOSS OF COOL FLOW PWR > P8, RED 1E-A3, RC LOOP 1C LO FLOW CH 1 1E-B3, RC LOOP 1C LO FLOW CH 2 1E-C3, RC LOOP 1C LO FLOW CH 3 Indications:

Low flow indication on C loop, CH-1, CH-2, CH-3 Reactor - Critical RO Attempt to Trip the Reactor by pressing BB-1 and BB-2 Reactor Trip Pushbuttons.

GO TO FR-S.1 Critical Task: CT-1: DRP-049 E-12, Insert negative reactivity into the core by at least one of the following methods before completing the Immediate Action Steps of FR-S.1. Insert Control Rods in auto or manual within 30 seconds of the onset of the ATWS event.

Critical Step Start Time: ________________

1-FR-S.1 CAUTION: RCPs should not be tripped with Reactor power greater than 5%.

RO [ 1] VERIFY REACTOR TRIP: Verify or place control rods in Auto.

a) Manually trip Reactor b) Check the following:

  • All Rods On Bottom light - LIT

OPEN

  • Neutron Flux - DECREASING RO Identifies Reactor NOT Tripped, Performs RNO Action 1-FR-S.1 RO [2] MANUALLY TRIP THE TURBINE:

RO presses Both Turbine Trip Pushbuttons, Simultaneously.

  • Verify all turbine stop valves - CLOSED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 49 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-FR-S.1 RO [3] VERIFY CONTROL RODS - INSERTING IN AUTO AT GREATER THAN 48 STEPS /

MINUTE Critical Task Stop Time: ____________________

RO/BOP Manually insert control rods.

When Rod Speed lowers, places Rods in MANUAL, and inserts Rods.

4 VERIFY AFW PUMPS RUNNING:

SRO a) MD AFW pumps - RUNNING BOP b) TD AFW pump - RUNNING IF NECESSARY BOP BOP check MD / TD AFW Pumps Running.

SRO 1-FR-S.1 SRO 5 INITIATE EMERGENCY BORATION OF RCS:

a) Verify CHG flow - GREATER THAN 75 GPM RO Check CHG FLOW > 75 gpm.

b) Align boration path:

SRO 1) Put BATP in FAST RO Places 1-CH-P-2A, A BAST Recirc Pump, in FAST.

SRO 2) Open 1-CH-MOV-1350 RO Places control switch 1-CH-MOV-1350 in OPEN.

SRO 3) Verify emergency borate flow RO Checks Flow on 1-CH-FI-1110 rises to 110 gpm.

SRO c) Check PRZR pressure - LESS THAN 2335 PSIG RO Checks RCS Pressure < 2335 psig using RCS NR or WR Pressure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 50 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-FR-S.1 SRO *6 CHECK IF SI INITIATED: GO TO Step 8 RO

  • LHSI pumps - RUNNING
  • A-F-3
  • A-F-4 Identifies SI NOT initiated, SRO GOES TO STEP 8.

1-FR-S.1 SRO 8 CHECK IF THE FOLLOWING TRIPS HAVE OCCURRED:

RO a) Reactor trip b) Turbine trip SRO Directs BOP to contact Service Building Operator to locally open Unit 1 Reactor Trip Breakers.

NOTE: Two (2) Minutes will elapse from the time an Operator is dispatched to open the Reactor Trip breakers until the Simulator Operator Opens the breakers.

Based on Time Critical Operator Action.

1-FR-S.1 NOTE: If adverse CTMT conditions have been exceeded, the Gamma-Metrics Excore Neutron Monitor system (Source and Wide Ranges) should be used to monitor neutron flux for the duration of the event.

  • 9 CHECK REACTOR - SUBCRITICAL SRO a) Check power range channels - LESS THAN 5% [Gamma-Metrics Wide Range Power - LESS THAN 5%]

RO Identifies Reactor Power < 5%.

b) Check Intermediate range channels - NEGATIVE STARTUP RATE [Gamma-Metrics Wide Range Power - DECREASING]

RO Identifies negative SUR on IR Channels.

SRO c) GO TO Step 18

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 51 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-FR-S.1 CAUTION: Boration should be continued to obtain adequate shutdown margin during subsequent actions.

SRO 18 RETURN TO PROCEDURE AND STEP IN EFFECT SRO Announces Transition to E-0.

SRO Directs Reactor Operator to perform E-0 Immediate Actions Steps.

1-E Reactor Trip or Safety Injection RO [1] CHECK REACTOR TRIP:

a) Manually trip reactor Pushes the reactor trip push buttons.

b) Check the following:

  • All Rods On Bottom light - LIT
  • Neutron flux - DECREASING RO [2] CHECK TURBINE TRIP:

RO a) Manually trip the turbine Pushes the turbine trip push buttons.

b) Verify all turbine stop valves - CLOSED c) Isolate reheaters by closing MSR steam supply SOV

  • 1-MS-SOV-104 d) Verify generator output breakers - OPEN (Time Delayed)

Identifies that Output Breakers did open RO [3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 52 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

[4] CHECK IF SI INITIATED:

RO a) Check if SI is actuated:

  • LHSI pumps - RUNNING
  • A-F-3 SI INITIATED - TRAIN A
  • A-F-4 SI INITIATED - TRAIN B RO RO will determine that SI has NOT occurred and perform step 4a RNO actions:

4a RNO Check if SI is required or imminent as indicated by any of the following:

  • Low PRZR pressure
  • High steamline differential pressure
  • High steam flow with low Tave or low line pressure IF SI is required, THEN GO TO Step 4b.

RO reports Immediate Actions of E-0 are complete, SI not in service or required, and recommends transition to ES-0.1.

After the immediate actions of 1-E-0 are reported as complete, the SRO will check off immediate action steps in his copy of 1-E-0. After the immediate actions are verified, the team will conduct a brief.

SRO SRO will lead a brief using the brief checklist.

The RO will provide critical parameters using the Brief placard.

The BOP will provide critical parameters using the brief placard.

The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

The SRO will direct the BOP to perform ES-0.1, Transient AFW Control, Attachment 5 of ES-0.1, while the RO and SRO continue with ES-0.1.

Note: Attachment 5 of ES-0.1 is located at the End of this Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 53 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

1-ES-0.1 NOTE: Team may elect to secure the C RCP.

NOTE: If this procedure is being entered from 1-E-0, REACTOR TRIP OR SAFETY INJECTION, following a tube leak of less than 150 gpm, 1-AP-24.01, LARGE STEAM SRO GENERATOR TUBE LEAK, should be used for guidance instead of this procedure.

  • 1 CHECK RCS TEMPERATURE CONTROL RO a) Check RCPS - ANY RUNNING Reports all three RCPs running, C with abnormally low flow.

b) Monitor RCS Average Temperature

1) STABLE AT 547°F OR RO 2) TRENDING TO 547°F Reports RCS temperature stable at 547 °F.

1-ES-0.1 SRO 2 CHECK FW STATUS:

a) Check RCS Average temperatures - LESS THAN 554°F RO Identifies RCS Temperature < 554 °F b) Check Feed REG valves - CLOSED RO Identifies all FRVs closed.

c) Close SG FW isolation MOVs

  • 1-FW-MOV-154A
  • 1-FW-MOV-154B
  • 1-FW-MOV-154C RO/BOP Close 1-FW-MOV-154 A / B / C d) Check AFW pumps - RUNNING
  • Motor Driven AFW pumps

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 54 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

BOP Identifies MD / TD AFW pump running.

e) Check total AFW flow - GREATER THAN 540 GPM (350 GPM W/O RCPs)

BOP Identifies AFW flow > 540 GPM (IAW band given by SRO) f) Check emergency buses - BOTH ENERGIZED RO Identifies emergency buses energized.

g) Control feed flow to maintain narrow range level between 22% and 50%

BOP Acknowledges direction to control AFW flow to obtain band.

1-ES-0.1 SRO 3 CHECK CHARGING IN SERVICE RO Provides CH flow value and trend to SRO.

Note: If not already implemented, go to Event #8.

1-ES-0.1 SRO 4 CHECK CC SYSTEM STATUS:

a) Check SW to CC HXs - IN SERVICE RO Identifies two (2) CC headers flowing to CC HXs.

b) Check CC pumps - AT LEAST ONE RUNNING RO Identifies 1-CC-P-1A running.

1-ES-0.1 SRO 5 CHECK PRZR LEVEL CONTROL:

a) Check PRZR level - GREATER THAN 15%

RO Reports PRZR level and trend to SRO.

b) Check letdown - IN SERVICE RO Reports Letdown flow and trend to SRO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 7 Page 55 of 98 Event

Description:

RC Loop C Tc disc falls in, Valid First-out, FR-S.1.

Cue: By Evaluator. If the Team opts to trip the reactor on Event #5, notify Simulator Operator to implement Trigger for Event #7 when first reactor trip pushbutton pressed.

Time Position Applicants Action or Behavior ES-0.1, Attachment 5 BOP 1 Maintain minimum AFW flow of 540 gpm with RCP(s) in service until one SG Narrow Range level is greater than 12%.

ES-0.1, Attachment 5 BOP 2 Maintain minimum AFW flow of 350 gpm with NO RCPs running, until one SG Narrow Range level is greater than 12%.

Throttles AFW to band provided by SRO.

ES-0.1, Attachment 5 NOTE: AFW to idle loop(s) (RCP secured), should be throttled to prevent depressurization of the SG and subsequent Header / Line SI. AFW flow between approximately 60 gpm and 100 gpm should be adequate to prevent a Header / Line SI.

BOP 3 When minimum heat sink has been verified, AFW MOVs should be controlled to maintain intact SG Narrow Range levels between 22% and 50% by throttling AFW Isolation MOVs:

  • SG A, 1-FW-MOV-151E and 1-FW-MOV-151F
  • SG B, 1-FW-MOV-151C and 1-FW-MOV-151D
  • SG C, 1-FW-MOV-151A and 1-FW-MOV-151B ES-0.1, Attachment 5 BOP 4. Isolate AFW header with deenergized Emergency Bus MOVs by closing the following header isolation valves:

Emergency Bus H deenergized: 1-FW-141 1-FW-156 1-FW-171 Emergency Bus J deenergized: 1-FW-140 1-FW-155 1-FW-170 Identifies Bus H and J not deenergized.

End EVENT #7

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 56 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

Time Position Applicants Action or Behavior Team Identify Failure based on the following:

Alarms:

1B-F3, SFGDS AREA SUMP HI LEVEL 1C-B-8, PRZR LO PRESS 1C-D8, PRZR LO LEVEL 1D-E5, CHG PP TO REGEN HX HI-LO FLOW RMA-D6, VENT STACK #2PART ALERT/HI RMA-D7, VENT STACK #2 NORM RNG GAS ALERT/HI Indications:

Lowering PRZR Level Rising CH flow NOTE: SRO may direct manual safety injection and return to E-0 due to degrading plant conditions.

1-AP-16.00 SRO Direct RO to perform the Immediate Actions of 1-AP-16.00.

1-AP-16.00 RO NOTE:

  • RCS average temperature has a direct impact on pressurizer level.

[1] MAINTAIN PRZR LEVEL:

  • Isolate Letdown Closes 1-CH-LCV-1460 A / B
  • Control Charging flow Takes Manual control of 1-CH-FCV-1122 and raises CH Flow.

RO Reports that CH flow at maximum value and PZR level decreasing.

SRO Direct RO to Re-perform the Immediate Action Steps of E-0, and Safety Inject on Step 4.

1-E-0 RO [1] CHECK REACTOR TRIP:

1-E-0

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 57 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

RO [2] CHECK TURBINE TRIP:

1-E-0

[3] CHECK BOTH AC EMERGENCY BUSES - ENERGIZED 1-E-0 RO [4] CHECK IF SI INITIATED:

a) Check if SI is actuated:

  • LHSI pumps - RUNNING
  • A-F-3
  • A-F-4 b) Manually initiate SI Report SI has been initiated, SI flow to the core, 1-E-0 Immediate Actions with SI complete.

1-E-0 SRO Will Check off the Immediate Action Steps of 1-E-0.

SRO will conduct a commensurate Brief. Ensure the Team agrees that a LOCA outside of containment is in progress. Poll the Team as to any higher priority than continuing actions for a LOCA outside of containment.

SRO closes the brief.

Directs BOP to perform Attachments 1, 2, and 3 of 1-E-0. Attachment 1, 2, and 3 located in Event 9.

Continues with 1-E-0 with RO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 58 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 1-E-0 RO Identify RCS Subcooling < 30 °F and SI flow indicated to all three loops.

SRO Using 1-E-0 Continuous Actions Page:

1. RCP TRIP CRITERIA Trip all RCPs if BOTH conditions listed below occur:
a. Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS
b. RCS Subcooling - LESS THAN 30°F [85°F]

RO Checks RCP Trip Criteria exist.

SRO Directs RO to Trip all RCPs.

2. MINIFLOW RECIRC CRITERIA
a. CLOSED - When RCS pressure is less than 1275 psig [1475 psig] AND RCP Trip Criteria are met (RCPs OFF).

RO Identifies Criteria are met.

SRO Direct RO to close mini-flow recirc valves.

CT-2: Critical Task: E 1.2. Trip all RCPs within 5 minutes of reaching RCP Trip Criteria. (WOG E-1-C).

CT-2: Start Time: _________. CT-2: Stop Time: _________.

Note: Examiner will be notified by Simulator Operator when RCS Subcooling reaches 35°F and Lowering for CT-2 Monitoring.

SRO *6. CHECK RCS AVERAGE TEMPERATURE

  • STABLE AT 547°F OR
  • TRENDING TO 547°F

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 59 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

SRO 7. CHECK PRZR PORVs AND SPRAY VALVES:

a) PRZR PORVs - CLOSED b) PRZR spray controls

  • Demand at Zero (or)
  • Controlling Pressure c) PORV block valves - AT LEAST ONE OPEN NOTE: Seal injection flow should be maintained to all RCPs.

SRO *8. CHECK RCP TRIP AND MINIFLOW RECIRC CRITERIA:

a) Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS RO Two or three Charging pumps will be running and flowing to the RCS.

b) RCS subcooling - LESS THAN 30°F [85°F]

RCS subcooling will be less than 30 °F c) Stop all RCPs d) RCS pressure - LESS THAN 1275 psig [1475 PSIG]

e) Close CHG pump miniflow recirc valves:

  • 1-CH-MOV-1275A
  • 1-CH-MOV-1275B
  • 1-CH-MOV-1275C Mini-flow recirc valves closed.

SRO 9. CHECK IF SGs ARE NOT FAULTED:

  • Check pressures in all SGs a) STABLE OR INCREASING AND b) GREATER THAN 100 PSIG RO will observe a slightly decreasing trend on SG pressures. This will be attributed to the RCS cooldown. The team will not transition to 1-E-2.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 60 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

SRO 10. CHECK IF SG TUBES ARE NOT RUPTURED:

  • Condenser air ejector radiation - NORMAL
  • SG blowdown radiation - NORMAL
  • SG MS radiation - NORMAL
  • TD AFW pump exhaust radiation - NORMAL
  • SG NR Level - NOT INCREASING IN AN UNCONTROLLED MANNER 11 CHECK RCS - INTACT INSIDE CTMT SRO
  • CTMT radiation - NORMAL
  • CTMT pressure - NORMAL

RO SRO 12 CHECK RCS - HAS BEEN MAINTAINED INTACT OUTSIDE CTMT a) Radiation Monitors - NORMAL

  • MGPI vent-vent
  • Auxiliary Building Control Area RO Reports MGPI Vent-Vent in Alarm b) Sump annunciators - NOT LIT
  • VSP-F-4
  • B-D-1
  • B-D-2
  • B-F-3 Step 12 RNO Determine cause of abnormal conditions.

IF the cause is a loss of RCS inventory outside CTMT, THEN GO TO 1-ECA-1.2, LOCA OUTSIDE CONTAINMENT.

RO Reports conditions caused by LOCA outside CTMT SRO Transitions to ECA-1.2.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 61 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

Time Position Applicants Action or Behavior 1-ECA-1.2 SRO Performs a commensurate brief. Ensures Team assessment confirms event in progress is a LOCA outside CTMT. Polls Team concerning any abnormal condition that needs to be addresses of a higher priority than isolating the LOCA outside CTMT. When any issues are addressed, SRO closes brief and continues with ECA-1.2.

1-ECA-1.2 CAUTION: Depending on break location, higher than normal dose levels should be expected in the Auxiliary Building and the Safeguards after a LOCA outside CTMT.

SRO 1 VERIFY PROPER VALVE ALIGNMENT:

a) Locally unlock and close the following breakers:

  • 1H1-2N 9A for 1-SI-MOV-1890C Directs the BOP to contact the Shift Manager/Desk SRO and have an operator briefed and dispatched to remove tags and close the breakers for 1-SI-MOV-1890 A / B / C.

NOTE: Booth will time compress this action when SM/Desk SRO contacted.

b) LHSI to hot legs - CLOSED

  • 1-SI-MOV-1890A
  • 1-SI-MOV-1890B When Valves Energized, the valves indicate closed.

c) SI accumulator test valves - CLOSED

  • HCV-SI-1850A
  • HCV-SI-1850B
  • HCV-SI-1850C
  • HCV-SI-1850D
  • HCV-SI-1850E
  • HCV-SI-1850F When Checked, Valves Indicate closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 8 Page 62 of 98 Event

Description:

LOCA outside of Containment upstream 1-SI-MOV-1890C.

Cue: By Evaluator.

1-ECA-1.2 NOTE: The SRO is expected to have a Focus Brief prior to this step. The SRO will bring the BOP into the discussion concerning the expected response of the RCS SRO when 1-SI-MOV-1890C is closed. If closure of this valves isolates the RCS break, RCS pressure and LHSI flow is expected to increase. If the break remains isolated, RCS pressure and LHSI flow will remain the same or decrease. The SRO will complete the brief and continue ECA-1.2.

2 TRY TO IDENTIFY AND ISOLATE BREAK:

a) Close LHSI to cold legs RO

  • 1-SI-MOV-1890C Team Shortly after closure of 1-SI-MOV-1890C, the Team should identify that RCS pressure and LHSI flow is increasing.

Critical Task:

CT-3: WOG ECA-1.2A, Isolate the LOCA outside containment before transition out of ECA-1.2, or cavitation of any LHSI pump. SPS- Isolate LOCA outside SRO containment before transition out of ECA-1.2 (PSA).

RO b) Check RCS pressure - INCREASING RO will identify RCS increasing.

c) Place LHSI pumps in PTL RO Places LHSI pumps in PTL.

SRO d) Close LHSI pump suctions from RWST

  • 1-SI-MOV-1862A
  • 1-SI-MOV-1862B Closes 1-SI-MOV-1862A / B.

e) GO TO 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT SRO Transitions to 1-E-1.

CRITICAL TASK STOP TIME ____________________

END EVENT 8 END of Scenario 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 63 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Time Position Applicants Action or Behavior ATTACHMENT 1 OF E-0 BOP 1. CHECK FW ISOLATION:

  • Feed pump discharge MOVs - CLOSED
  • 1-FW-MOV-150A
  • 1-FW-MOV-150B
  • MFW pumps - TRIPPED
  • Feed REG valves - CLOSED
  • SG FW bypass flow valves - DEMAND AT ZERO
  • SG blowdown TVs - CLOSED BOP 2. CHECK CTMT ISOLATION PHASE I:
  • Phase I TVs - CLOSED Identifies 1-CV-TV-150A, 1-CH-TV-1204A OPEN, Closes valves
  • 1-CH-MOV-1381 - CLOSED
  • 1-SV-TV-102A - CLOSED
  • PAM isolation valves - CLOSED
  • 1-DA-TV-103A
  • 1-DA-TV-103B BOP 3. CHECK AFW PUMPS RUNNING:

a) MD AFW pumps - RUNNING (Time Delayed) b) TD AFW pump - RUNNING IF NECESSARY

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 64 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Attachment 1 of E-0 BOP 4. CHECK SI PUMPS RUNNING:

  • CHG pumps - RUNNING
  • LHSI pumps - RUNNING Manually Starts 1-SI-P-1A.

BOP 5. CHECK CHG PUMP AUXILIARIES:

  • CHG pump CC pump - RUNNING
  • CHG pump SW pump - RUNNING
6. CHECK INTAKE CANAL:

BOP

  • Level - GREATER THAN 24 FT
  • Level - BEING MAINTAINED BY CIRC WATER PUMPS
7. CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED:

a) Check if ANY of the following annunciators - HAVE BEEN LIT

  • E-F-10 (High Steam Flow SI)
  • B-C-4 (Hi Hi CLS Train A)

BOP

  • B-C-5 (Hi Hi CLS Train B)

Identifies annunciators not lit and goes to step 8.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 65 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

BOP *8 CHECK IF CS REQUIRED:

a) CTMT pressure - HAS EXCEEDED 23 PSIA 8, a) RNO Do the following:

1) IF CTMT pressure has exceeded 17.7 psia, THEN check or align the following valves:

Identifies CTMT pressure remains at normal pressure

2) GO TO Step 10.

Attachment 1 of E-0 BOP *10. BLOCK LOW PRZR PRESS SI SIGNAL:

a) Check PRZR pressure - LESS THAN 2000 psig b) Turn both LO PRZR PRESS & STM HDR/LINE P switches to block c) Verify Permissive Status light C LIT BOP may block the low pressurizer pressure SI signal depending on current RCS pressure.

BOP *11. BLOCK LOW TAVE SI SIGNAL:

Step may not be performed at this time (if Tave is greater than 543°F).

a) Check RCS Tave - LESS THAN 543°F b) Turn both HI STM FLOW & LO TAVG OR LP switches to block c) Verify Permissive Status light F LIT

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 66 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

NOTE:

  • CHG pumps should be run in the following order of priority: C, B, A.
  • Subsequent SI signals may be reset by re-performing Step 12.

BOP 12. CHECK SI FLOW:

a) HHSI to cold legs - FLOW INDICATED

  • 1-SI-FI-1961 (NQ)
  • 1-SI-FI-1962 (NQ)
  • 1-SI-FI-1963 (NQ)
  • 1-SI-FI-1943 or 1-SI-FI-1943A b) Check CHG pumps - THREE RUNNING c) Reset SI.

d) Stop one CHG pump and out in AUTO Attachment 1 of E-0 e) RCS pressure - LESS THAN 185 PSIG RNO: e) IF two LHSI pumps are running, THEN do the following:

1) Verify reset or reset SI.
2) Stop one LHSI pump and put in AUTO.

BOP 13. CHECK TOTAL AFW FLOW - GREATER THAN 350 GPM [450 GPM]

BOP 14. CHECK AFW MOVs - OPEN BOP will identify that all AFW MOVS are not open and will read the RNO portion of this step and manually align valves as necessary.

BOP 15. INITIATE SI VALVE ALIGNMENT IAW ATTACHMENT 2 See attached copy of Attachment 2. (Next Page of this guide)

Depending on timing, this attachment may have already been completed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 67 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

BOP 16. INITIATE VENTILATION, AC POWER, AND SFP STATUS CHECKS IAW ATTACHMENT 3 Attachment 3 follows Attachment 2.

Unit 2 Operator will state that Unit 2 is at 100% power (if asked)

Unit 2 will also accept responsibility to complete Attachment 3 if it is given to Unit 2 at the point where differential pressure indications are requested.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 68 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Time Position Applicants Action or Behavior ATTACHMENT 2 of 1-E-0 BOP NOTE: Components previously aligned by SI termination steps, must not be realigned by this Attachment.

ATTACHMENT 2 of 1-E-0 BOP 1. Check opened or open CHG pump suction from RWST MOVs.

  • 1-CH-MOV-1115B
  • 1-CH-MOV-1115D ATTACHMENT 2 of 1-E-0 BOP 2. Check closed or close CHG pump suction from VCT MOVs.
  • 1-CH-MOV-1115C
  • 1-CH-MOV-1115E ATTACHMENT 2 of 1-E-0 BOP 3. Check running or start at least two CHG pumps. (listed in preferred order)
  • 1-CH-P-1C
  • 1-CH-P-1B
  • 1-CH-P-1A ATTACHMENT 2 of 1-E-0 BOP 4. Check opened or open HHSI to cold legs MOVs.
  • 1-SI-MOV-1867C
  • 1-SI-MOV-1867D ATTACHMENT 2 of 1-E-0 BOP 5 Check closed or close CHG line isolation MOVs.
  • 1-CH-MOV-1289A
  • 1-CH-MOV-1289B

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 69 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

ATTACHMENT 2 of 1-E-0 BOP 6. Check closed or close Letdown orifice isolation valves.

  • 1-CH-HCV-1200A
  • 1-CH-HCV-1200B
  • 1-CH-HCV-1200C ATTACHMENT 2 of 1-E-0 BOP 7. Check opened or open LHSI suction from RWST MOVs.
  • 1-SI-MOV-1862A
  • 1-SI-MOV-1862B ATTACHMENT 2 of 1-E-0 BOP 8. Check opened or open LHSI to cold legs MOVs.
  • 1-SI-MOV-1864A
  • 1-SI-MOV-1864B ATTACHMENT 2 of 1-E-0 BOP 9. Check running or start at least one LHSI pump.
  • 1-SI-P-1A
  • 1-SI-P-1B ATTACHMENT 2 of 1-E-0 BOP 10. Check High Head SI flow to cold legs indicated.
  • 1-SI-FI-1961
  • 1-SI-FI-1962
  • 1-SI-FI-1963
  • 1-SI-FI-1943 or 1-SI-FI-1943A ATTACHMENT 2 of 1-E-0 BOP 11. IF flow not indicated, THEN manually start pumps and align valves. IF flow NOT established, THEN consult with Shift Supervision to establish another high pressure injection flow path while continuing with this procedure.
  • Alternate SI to Cold legs
  • Hot leg injection End of Event 9 -. End of Scenario 4

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 70 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 71 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 72 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 73 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 74 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Unit 2 will prompt BOP: MCR Boundary DP is the same as DP indicated on Unit 2 Ventilation Panel.

Unit 2 will prompt BOP: Unit 2 remains operating at 100%

power.

Unit 2 will assume responsibility for the Attachment action from this point.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Event No.: 9 Page 75 of 98 Event

Description:

BOP Failures; 1-CH-MOV-1115D, 1-CH-MOV-115C, 1-CH-MOV-1289A fail to re-position.

Cue: Active Failures.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 76 of 98 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 1 Event No.: N/A Page 77 of 98 FOLDOUT PAGES FOR REFERENCED PROCEDURES

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 78 of 98 SIMULATOR OPERATORS GUIDE Simulator Setup Initial Conditions:

Recall IC -264 and implement TRIGGER #30 to activate all passive malfunctions and verify Trigger #30 implemented.

Ensure the Delta T Selector Switch is in the Channel II Position.

Ensure PRZR Level Recorder on Channel II.

Open the monitor window and add the following points to it:

  • asp_ao_off
  • CC_579 set at 0.38 Enter the following MALFUNCTIONS:

Trigger Malfunction Delay Ramp Trigger Value Final Type (Auto or Manual)

RC4802 PRZR PRESS CONT 10 10 1 0 1 MAN XMTR FAILURE (445)

MS1305 SG B STM PRESSURE 10 0 3 0 1 MAN TRNSMTR MS-PT-485 FAILURE CH2101 VCT LEVEL 10 0 5 0 1 MAN TRANMITTER LT-1115 FAILS CC0302 CC PUMP 1-CC-P-1B 10 0 7 FALSE TRUE MAN OVERCURRENT TRIP CC0802 CC-P-1B BKR 15J10 0 0 7 FALSE TRUE MAN MECHANICALLY STUCK CLOSED RD1236 DROPPED RCCA, M-4, 10 0 9 FALSE TRUE MAN CONTROL BANK C RD17 ATWS, WITH MANUAL RX 0 0 11 FALSE TRUE MAN TRIP PB DEFEATED SI1502 SI COLD LEG HDR LEAK 10 0 13 0 40 MAN UPSTRM MOV-SI-890C SI1603 FAIL CHECK VALVES SI- 10 0 13 FALSE TRUE MAN 85 SI1606 FAIL CHECK VALVE SI- 10 0 13 FALSE TRUE MAN 243 LOOP C (LHSI)

SI2402 SI RELAY SI2A FAILS TO 0 0 30 FALSE TRUE MAN ACTUATE SI2405 SI RELAY SI5A FAILS TO 0 0 30 FALSE TRUE MAN ACTUATE CC1801 DISABLE CCP1A AUTO 0 0 30 FALSE TRUE MAN START Enter the following Remote Functions:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 79 of 98 SIMULATOR OPERATORS GUIDE Remotes Set Condition Trigger SW_15J9_RF 4KV Stub TRIP, 20 Sec TD 7 Bus BKR 15J9 Control Switch RCMOV595 RC-MOV- 100 to 30, 0 Ramp, 10 Sec TD 11 595 C Loop Cold Leg Isol SIMOV890A_BKR SI- CLOSED 21 MOV-1890A LHSI To HOT Legs SIMOV890B_BKR SI- CLOSED 22 MOV-1890B LHSI To HOT Legs SIMOV890C_BKR SI- CLOSED 23 MOV-1890C LHSI To Cold Legs RX_RTA_OPEN TRUE 16 RX_RTB_OPEN TRUE 17 AAC_SMS_MODE OFF OFF 30 AAC DG LOCAL MODE SWITCH POSITION EL12, SW_25J10_RF, Bkr PTL 30 25J10 Control Switch, 1-CC-P-1D TRIGGER TYPE DESCRIPTION 1 MAN Przr Press Cont Xmtr Failure (445) Fails High 3 MAN SG B Stm Pressure Trnsmtr MS-FT-485 FAILS High 5 MAN VCT Level Transmitter LT-1115 Fails High OVERCURRENT Trip 1-CC-P-1B, BREAKER Stuck Closed, 15J9 7 MAN Breaker Trips Open

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 80 of 98 SIMULATOR OPERATORS GUIDE TRIGGER TYPE DESCRIPTION 9 MAN Dropped RCCA, M-4, Control Bank C 11 MAN RC-MOV-595 C Loop Cold Leg Isol Disc Falls Into Flow Stream 11 MAN ATWS, WITH MANUAL RX TRIP PB DEFEATED SI Cold Leg HDR Leak Upstrm MOV-SI-890C, With Check Valves 13 MAN Stuck Open

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 81 of 98 SIMULATOR OPERATORS GUIDE Verify the following control room setup:

Place the simulator in RUN and verify normal 100% power operation indications.

Reset the ROD CONTROL SYSTEM Verify Red Magnets on the following components:

Verify 1-RM-RI-112 aligned to A SG and 1-RM-RI-113 aligned to B/C SG (magnets).

Verify Ovation System operating.

Reset ICCMs.

Verify Component Switch Flags.

Verify Brass Caps properly placed.

Verify SG PORVs set for 1035 psig.

Verify Rod Control Group Step Counters indicate properly.

Verify Ovation CRT display.

Advance Charts Verify Turbine Thumb Wheel Settings @120 rpm/min and Position 6 Verify Containment Instrument Air Compressors are on Inside Suction (all RMs reset)

Verify all ARPs have been cleaned Verify CLEAN copies of the following procedures are in place:

AP-53.00 AP-1.00 AP-23.00 AP-16.00 E-0 ECA-1.2 1-OPT-RX-001 AP-1.00, Att 6 (3)

OP-CH-007 Reactivity Sheet OP-ZZ-002 Verify Reactivity Placard is current.

Verify ALL PINK MAGNETS are accounted for.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 82 of 98 SIMULATOR OPERATORS GUIDE Brief This simulator performance scenario is performed in the EVALUATION MODE. You should not direct questions to the evaluators. Otherwise, you should perform as if you were in the MCR.

Your ability to maintain a log is not being graded, but maintaining a rough log is recommended to help during briefs.

If you need to communicate with the Unit 2 operator, verbally state, Unit 2 and an instructor will locate to the Unit 2 area and respond to you as quickly as possible.

In the unlikely event that the simulator fails such that illogical indications result, the session will be terminated. In other words, respond to what you see. If there is a problem with the simulation, the session will be terminated or adjusted as appropriate based on the specific problem.

Assign operating positions.

Ask for and answer questions.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 83 of 98 SIMULATOR OPERATORS GUIDE Conduct shift turnover:

The initial conditions have Unit 1 is at 100% power with RCS boron concentration of 760 ppm.

Unit conditions have been stable at approximately 100% power since the last refueling outage.

All systems and crossties are operable with the following exception:

  • AAC DG is tagged out for maintenance, per VPAP-2802, Notifications and Reports, Section 6.29.1, a review of Reportability is required if the AAC DG is out of service greater than 14 days.

IAW TRM 3.7.9.A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock and a 14 day clock to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 day clocks to restore to functional status.

  • 1-CC-P-1D is tagged out for maintenance. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 14 day clock IAW TRM 3.7.9.A to implement MRule (a)(4) RMAs and App R fire watches, respectively, along with 30 day and 60 days clocks to restore to functional status.

Unit #2 is at 100% power with all systems and crossties operable.

Shift orders are to maintain 100% power on Unit #1.

The last shift performed two 35 gallon dilutions followed by a manual makeup for training.

A BAST at 8.0 W/%.

PSA is Green.

When the team has accepted the shift, proceed to the Session Conduct Section.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 84 of 98 SIMULATOR OPERATORS GUIDE Session Conduct:

  • Ensure conditions in Simulator Set-up are established.
  • Ensure Trigger 30 is active prior to team entering the simulator.
  • Verify Exam Security has been established and ASP_AO_OFF = True.

EVENT 1 Deleted EVENT 2 1-RC-PT-1145 Fails High, 1-AP-31.00/0-AP-53.00 When cued by examiner, implement Trigger #1.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of 1-RC-PT-1445. The individual(s) contacted will also acknowledge any TS LCOs and entry into AP-53.00/AP-31.00.
  • If contacted, acknowledge review of VPAP-2802 and EPIP SU6.1 review required.
  • If contacted, will take responsibility for writing the CR.

STA:

  • If contacted, will acknowledge the failure of 1-RC-PT-1445. The individual(s) contacted will also acknowledge (but not confirm/deny) any TS LCOs.
  • If asked, the STA will review VPAP-2802, TRM Section 3.3, and SU6.1 review complete and discussed with Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Field Operators:

No feedback required for this failure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 85 of 98 SIMULATOR OPERATORS GUIDE Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge instrumentation failure and commence investigations.

Unit 2 Operator:

If Contacted, acknowledge the failure of 1-RC-PT-1445.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 86 of 98 SIMULATOR OPERATORS GUIDE EVENT 3 Steam Pressure Fails High, B SG. 0-AP-53.00.

When cued by examiner, implement Trigger #3.

Operations Supervisor/Management:

  • If contacted, will acknowledge that Failure of 1MS-PT-1485, Channel III, B SG, Steam Pressure. The individual(s) contacted will also acknowledge any TS LCOs.
  • If asked, the Shift Manager will ask SRO for recommendation concerning performance 1-OP-RP-001 at this time. Shift Manager will tell SRO to wait and will call the SRO.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into AP-53.00.

STA:

  • If contacted, will acknowledge the Failure of 1MS-PT-1485, Channel III, B SG, Steam Pressure. The individual(s) contacted will also acknowledge any TS LCOs. The STA will not confirm or deny any TS decisions.
  • When asked, STA reports the failed channel is a RG 1.97 variable.
  • When asked, SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
  • When contacted, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Field Operators:

No feedback required.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 87 of 98 SIMULATOR OPERATORS GUIDE Maintenance/ Work Week Coordinator:

  • If contacted, will have I&C brief on placing the failed channel in trip.

Unit 2:

  • If contacted, will acknowledge Failure of 1-MS-PT-1485, Channel III, B SG, Steam Pressure.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 88 of 98 SIMULATOR OPERATORS GUIDE EVENT 4 Failure of VCT Level Channel LT-1115 High. 0-AP-53.00.

When Evaluator ready: Implement Trigger #5.

Operations Supervisor/Management:

  • If contacted, will acknowledge the failure of 1-CH-LT-1115 high.

STA:

  • If contacted, will acknowledge the failure of 1-CH-LT-1115 high.
  • If asked, SRO directs STA to review CEP 99-0029. The STA will report that CEP 99-0029 review has been completed and discussed with the Shift Manager.
  • After directed, SRO directs STA to review VPAP-2802 and TRM Section 3.3. The STA will report that review is complete; VPAP-2802 and TRM requirements have been discussed with the Shift Manager.
  • If contacted, will take responsibility for writing the CR.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.

Maintenance/ Work Week Coordinator:

  • If contacted, will acknowledge the failure and commence investigations.

Field Operators: (Wait 4 minutes from time of direction to report).

  • If contacted, to check the status of 1-CH-LT-1115 locally, report no obvious abnormal condition with the transmitter.

Unit 2:

  • If contacted, will acknowledge the failure of 1-CVH-LT-1115 high.

Role-play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 89 of 98 SIMULATOR OPERATORS GUIDE EVENT 5 Overcurrent trip 1-CC-P-1B with breaker stuck Shut, 15J9 trip open.

When cued by examiner, implement Trigger #7. If the Team decides to trip the reactor on this event, consult the examiner and actuate Trigger #11 when first Reactor Trip button pressed.

Operations Supervisor/Management:

  • If contacted, will acknowledge the fault on of 1-CC-P-1B, the failure of the breaker to open, and the trip of breaker 15J9. Will also acknowledge any TS information (time permitting) and information related to radiation monitors alarming.
  • If contacted, will take responsibility for writing the CR.
  • If contacted, will acknowledge entry into ARP.

Unit 2 Operator:

  • If asked: 1-CC-P-1C is running, and CC cross-ties are open.

STA:

  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, will acknowledge any TS information.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
  • If asked, The STA will report that TRM review is complete and TRM requirements have been discussed with the Shift Manager.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 90 of 98 SIMULATOR OPERATORS GUIDE Field Operator:

  • When contacted, report that 15J10 breaker for 1-CC-P-1B has a timed overcurrent drop on A phase. 1-CC-P-1A breaker, 15H10, has no abnormalities.
  • When contacted, report that 15J9 breaker has a timed overcurrent drop on all three phases.
  • If contacted, report as Aux Bldg Operator that there are no abnormalities locally with 1-CC-P-1A and 1-CC-P-1B.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 91 of 98 SIMULATOR OPERATORS GUIDE EVENT 6 Dropped Rod C Bank Group 1. 1-AP-1.00, 0-AP-23.00.

When Examiner ready, Actuate Trigger #9.

Operations Supervisor/Management:

  • If contacted, will acknowledge the dropped rod and the need to ramp at 1%/minute to 70 - 74%

power.

  • If asked for a recommended ramp rate, ask what the Unit Supervisor recommends. When authorized by the NRC, the Shift Manager will direct a 1%/minute ramp rate.
  • If contacted, will take responsibility for writing the WR and CR.

STA:

  • If asked, the STA will perform a QPTR. See AP-1.00, Attachment 6, attached.
  • If the team has a transient brief: The STA will state that primary integrity is as the RO reported and that secondary integrity is as the BOP reported. The STA will state that radiological conditions are normal. He will also state that containment conditions and the electrical conditions are as you see them.
  • If asked, the STA will acknowledge the need to borate and use rods (will acknowledge the team review of pre-planned reactivity plans and OP-RX-010, if performed). If asked to perform the OP-RX-010 review, the STA will state that he is not able to at this time.
  • When contacted, SRO directs STA to review VPAP-2802. The STA reports that review is complete and has been discussed with the Shift Manager.

Unit Two:

  • If contacted, all conditions on U2 are normal.

Field Operators:

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 92 of 98 SIMULATOR OPERATORS GUIDE

  • If contacted, Will perform actions as directed (i.e., may be asked to read bank overlap counter-RD 2).

I&C:

  • If requested by MCR to reset the bank overlap - use RD2 drawing to set as requested.

Maintenance/Work Week Coordinator:

  • If contacted, will acknowledge the failure and commence investigations.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 93 of 98 SIMULATOR OPERATORS GUIDE EVENT 7 RC Loop C disc falls, Valid First-Out, FR-S.1 When Evaluator has seen a sufficient change in power, Actuate Trigger #11.

Operations Supervisor/Management:

  • If contacted, will acknowledge the reactor trip failure and entry into FR-S.1, E-0, and ES-0.1.
  • If contacted, will acknowledge direction for local opening of reactor trip breakers. After two (2) minutes, use Trigger 16 (A RT breaker) and Trigger 17 (B RT breaker).
  • If contacted, will take responsibility for writing the WR and CR.
  • If contacted, SRO requests that tags be cleared and breakers closed for 1-SI-MOV-1890A / B /

C, use Triggers 21, 22, and 23 to perform close the breakers for the MOVs.

Field Operators:

  • If directed, field operators will acknowledge direction for local opening of reactor trip breakers.

After two (2) minutes, use Trigger 16 (A RT breaker) and Trigger 17 (B RT breaker).

  • If contacted, SRO requests that tags be cleared and breakers closed for 1-SI-MOV-1890A / B /

C, use Triggers 21, 22, and 23 to perform close the breakers for the MOVs.

Role play as other individuals as needed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 94 of 98 SIMULATOR OPERATORS GUIDE EVENT 8 LOCA Outside Containment Upstream 1-SI-MOV-1890C.

When Evaluator is ready, implement Trigger # 13.

When RCS Subcooling reaches 35°F and lowering, notify the Lead Examiner, for monitoring CT-2.

1-SI-MOV-1890A / B/ C can be energized when directed using Triggers 21, 22, and 23. 2 minutes to transit to valve, when directed; wait 1 minute between Triggers to energize MOV.

Operations Supervisor/Management:

  • If contacted, will acknowledge the reactor trip failure, completion of FR-S.1, completion of E-0 Immediate Actions, and transition to ES-0.1.
  • If contacted, will take responsibility for writing the WR and CR.

Unit 2 Operator:

  • If directed to respond to radiation alarms on the radiation alarm panel, silence the alarms when and report the alarm to the Unit 1 SRO.
  • When FP alarms occur, acknowledge alarms.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
  • When contacted by BOP, Chilled Water has been throttled IAW the Caution prior to Step 10 of Attachment 3. MCR boundary D/P indicates the same value as Unit 2 ventilation panel D/P gauges. Unit 2 will assume responsibility for Attachment 3 when last page is reached (SFP monitoring).
  • When directed, to read Unit 1 A/E, Blowdown, Main Steam and TDAFW radiation, report as pre-event, no trend.

Field Operators: Perform with a two minute delay to transit to the valve breaker; 1 minute between Triggers to energize MOVs.

  • If directed, field operators will remove tags and close breakers for 1-SI-MOV-1890A / B / C.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Surry 2014-1 Scenario No.: 4 Page 95 of 98 SIMULATOR OPERATORS GUIDE Role play as other individuals as needed.

EVENT 9 BOP Failures.

Operations Supervisor/Management:

  • If contacted, will take responsibility for writing the WR and CR.

Unit 2 Operator:

  • When radiation alarms sound on the radiation alarm panel, silence the alarms when directed and report the alarm to the Unit 1 SRO.
  • If directed perform the associated RM ARP without leaving the confines of the Unit 2 control area. If actions or verifications are required on the Unit 1 side, inform the Unit 1 SRO of the need for an operator to complete the ARP.
  • When directed, to read Unit 1 A/E, Blowdown, Main Steam and TDAFW radiation, report as pre-event, no trend.

Field Operators: Role play as necessary to support the Teams actions.

The scenario will end upon entering 1-E-1 or at the lead examiners discretion

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