ML15224B410

Initial Exam 2011-301 Final Simulator Scenarios

ML15224B410
Person / Time
Site:	Robinson
Issue date:	05/21/2015
From:	NRC/RGN-II
To:	Progress Energy Carolinas
References
Download: ML15224B410 (126)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 1 Op Test No.:

Examiners: Operators: SRO -

RO BOP Initial Conditions:

• 100% RTP MOL, 9000 MWD/MTU, 745 ppm Boron.

. A CCW pump inoperable with the breaker racked out

• 5 GPD primary to secondary leakage into SIG C

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

Turnover:

• Reduce power to 85% to support maintenance on A Heater Drain Pump excessive packing leakage.

Critical Tasks:

• Start one SI Pump to provide injection to the RCS.

• Close valve CVC-303A to isolate RCP seal return.

• Isolate SIG B due to tube rupture lAW Supplement G and PATH-2.

Event MaIf. Event Type* Event No. No. Description 1 (R)RO Reduce turbine load lAW OP-i 05 to 85%.

(N) BOP, SRO 2 (I) BOP, SRO Feedwater Flow Transmitter FT-477 fails HIGH (TS) SRO 3 (I) RO, SRO PZR Pressure Transmitter PT-444 fails HIGH (TS) SRO 4 (C) RO, SRO RCP A #1 Seal Failure 5 (M)ALL S/G B tube rupture following the manual Reactor Trip 6 (C) RO Both Safety Injection Pumps do not Auto Start 7 (C) BOP Isolate Seal Return from RCP A lAW AOP-018 8 (C) BOP Isolate S/G B using Supplement G (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-i 021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 I ILC-11-1 NRC SCENARIO I

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 100% steady state power. The previous shift had identified seal leakage on CCW Pump A. The motor breaker has been racked out and the pump has been isolated and cleared for maintenance. 5 GPD primary to secondary leakage has been identified into S/G C with elevated readings on the applicable radiation monitors. Shift instructions are to reduce reactor power and turbine load to support maintenance on Heater Drain Pump A packing leakage.

The crew will reduce reactor power and turbine load lAW OP-i 05 to 85% to support maintenance on A Heater Drain Pump.

Feedwater flow channel FT-477 fails LOW, affecting the automatic operation of Feedwater Regulating Valve FCV-478 for SIG A. The operator will have to take manual control of the FRV and restore the S/G to program level. The crew will perform the immediate actions for FT-477 failure lAW AOP-025, RTGB Instrument Failure, Section E. The crew will perform the necessary transfer to the controlling channel and restore the FRV to automatic operation. The failed feedwater flow transmitter will be removed from service lAW OWP-026, FWF-2. The SRO will implement ITS Table 3.3.1-i Item 14 which requires 2 S/G Level channels (not affected by the failure) and 2 Steam Flow / Feedwater Flow mismatch channels with Condition E Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Once the feedwater flow transmitter has been removed from service, the FRV returned to automatic and the Chief Examiner is satisfied with the Tech Specs compliance, the Chief Examiner will cue the next event.

PZR Pressure Transmitter PT-444 will fail HIGH, causing the PZR PORV PCV-455C to open and both PZR Spray valves to open. Immediate actions of AOP-025, RTGB Instrument Failure, Section C will be performed by the crew. PCV-455C will not respond to the closure signal from the RTGB control switch and will require the operator to manually close the PZR PORV Block valve RC-536. The PZR Spray valves will have to be manually closed by manual control of the PZR Pressure Controller PC-444J or manual control of each of the PZR Spray Valves PCV 455A and PCV-455B. Due to the PZR PORV PCV-455C being failed open, the SRO will be required to implement ITS 3.4.11, Condition B One PORV inoperable and not capable of being manually cycled. Actions include the following: B.1 Close associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.2 Remove power from the associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.3 Restore PORV to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The actions include opening the power supply breaker to the block valve RC-536, which was closed to isolate the failed open PZR PORV. The Chief Examiner will cue the next event when the necessary ITS requirements have been implemented.

On cue from the Chief Examiner, the #1 seal on RCP A will fail. This will require entry into AOP-018, Reactor Coolant Pump Abnormal Conditions, to identify and determine that a manual reactor trip will be required due to the plant conditions. A manual reactor trip will be initiated along with the securing of the affected RCP from actions directed from AOP-Oi 8. Within 3 to 5 minutes following the securing of the RCP, the seal return isolation valve must be closed to isolate the excessive seal leakage. These actions are performed along with the actions of PATH-i due to AOP-01 8 being a concurrent AOP.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 During the actions of PATH-i, the Chief Examiner will cue the tube rupture in SIG B. The crew may note the lowering PZR level and pressure, along with the rising SIG level to determine that a S/G tube rupture has occurred. There will not be any radiation monitor response from the tube rupture due to the radiation monitor response being disabled. Once the safety injection is initiated, the operator will observe that the SI Pumps do not automatically start and manually start them as required.

PATH-i and PATH-2, along with Supplement G will be used by the crew to isolate the ruptured SIG and equalize the RCS and ruptured SIG pressures to stop the excessive primary to secondary leakage.

The Chief Examiner may terminate the scenario at any time after the SI Pumps are secured in PATH-2 for the termination of the primary to secondary leakage.

Appendix D NUREG-iO2i, Rev. 9, Supp. i

Appendix D Operator Action Form ES-D-2 ILC-II-1 NRC SCENARIO I SIMULATOR SETUP IC!SETUP:

• IC-801, SON: 008_NRC_i

• A 00W Pump inoperable with the breaker racked out

• 5 GPD primary to secondary leakage into SIG C

• R-15 at 24 cpm, R-19C at 232 cpm, R-31C at 0.450 mR/hr

• R-19B, R-31B and R-14C overridden AS IS

• Status board updated to reflect 10-13.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 6: Both Safety Injection Pumps do not Auto Start EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Reduce turbine load lAW OP-lOS to 85%.

Event 2: Feedwater Flow Transmitter FT-477 fails LOW Event 3: PZR Pressure Transmitter PT-444 fails HIGH Event 4: RCP A #1 Seal Failure Event 5: S/G B tube rupture following the manual Reactor Trip EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• OP-I 05

• AOP-025 Main Body and Section E

• OWP-026, FWF-2

• AOP-025 Main Body and Section C

• AOP-018 Main Body and Section A

• PATH-I

• Foldout A

• Supplement G

• PATH-2

• Foldout C Appendix D NUREG-l 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 1 Page 5 of 32 Event

Description:

Reduce turbine load lAW OP-i 05 to 85%.

Time Position Aplicants Actions or Behavior NOTE: The crew will use OP-105, MANEUVERING THE PLANT WHEN GREATER THAN 25% POWER, to perform the plant down power.

Only the applicable steps have been listed.

SRO Notify the Load Dispatcher that unit load will be reduced.

Notify RC that increased radiation levels are expected in the CV Pump SRO Bays and in Pipe Alley due to normal shutdown crud bursts.

Monitor the highest operable Power Range Channel and the highest RO olDerable Intermediate Rancie Channel on NR-45.

IF Reactor Engineering has not provided technical guidance, THEN SRO/RO determine the reactivity change required.

IF additional letdown flow is desired, THEN:

RO . Start additional Charging Pumps as necessary,

. Place additional letdown orifice in service.

IF a significant change in RCS Boron concentration occurs, THEN RO enerqize additional PZR heaters as needed.

NOTE: OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, but may be used following the commencement of the plant down power.

DETERMINE the amount of Boric Acid to add to the RCS and RO OBTAIN an independent check of the volume required.

NOTE: 51 gallons of Boric Acid will be added based on rods stepping to 191 steps. (The crew will add Boric Acid in 1-2 batches.)

RO OBTAIN permission from the CRSS OR the SSO to borate.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 1 Page 6 of 32 Event

Description:

Reduce turbine load lAW OP-I 05 to 85%.

Time Position Applicants Actions or Behavior RO PLACE the RCS MAKEUP MODE selector switch to BORATE RO SET YIC-1 13, BORIC ACID TOTALIZER to desired quantity.

IF desired, THEN PLACE FCV-.113A, BORIC ACID FLOW, in MAN RO AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.

IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RO

• Rod Motion is blocked or in the wrong direction

• TAVG increases

• Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

• FCV-1 13A, BORIC ACID FLOW, closes.

RO

• FCV-113B, BLENDED MU TO CHG SUCT, closes.

• IF in Auto, THEN the operating Boric Acid Pump stops.

• __The_RCS_MAKEUP_SYSTEM_is_OFF.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 1 Page 7 of 32 Event

Description:

Reduce turbine load lAW OP-i 05 to 85%.

Time Position 1 Applicants Actions or Behavior IF desired, THEN FLUSH the Boric Acid flow path as follows

. PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.

. SET YIC-1 14, PRIMARY WTR TOTALIZER to 1 5-20 gallons.

. PLACE FCV-1 14B, BLENDED MU TO VCT to CLOSE.

. Momentarily PLACE RCS MAKEUP SYSTEM switch to START.

. IF any of the below conditions occur, THEN momentarily place RD the RCS MAKEUP SYSTEM switch in the STOP position:

o Unanticipated Rod Motion o Primary Water addition reaches the desired value

. WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

o FCV-1 14A closes.

o FCV-113B closes.

o IF in Auto, THEN the operating Primary Water Pump stops.

o The RCS MAKEUP SYSTEM is OFF.

RETURN the RCS Makeup System to automatic as follows:

. VERIFY FCV-1 14A is in AUTO.

. PLACE FCV-1 14B to the AUTO position.

RO

• PLACE the RCS MAKEUP MODE switch in AUTO

• VERIFY FCV-113A is in AUTO.

• Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER RD TOTALIZER, YIC-1 14 AND Boric Acid TOTALIZER, YIC-1 13 the total amount of Primary Water AND Boric Acid added during the boration.

MONITOR parameters for the expected change in reactivity AND RD inform the CRSS OR the SSO of the results of the boration.

IF EH Turbine Control is in OPER AUTO, THEN reduce turbine load as follows:

• Place the EH Turbine Control in the desired position: IMP IN.

BOP

• Set the desired load in the SETTER.

• Select the desired Load Rate.

• Depress_the_GO_pushbutton.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # I Event # 1 Page 8 of 32 Event

Description:

Reduce turbine load lAW OP-i 05 to 85%.

Time 1 Position Applicants Actions or Behavior Maintain Gland Seal Steam Header Pressure in the normal operating BOP band (3 to 6 psig) (P1-4004, P1-I 382 or ERFIS Pt GSP2O95A)

WHEN Reactor Power is <90% as indicated on NR-45, THEN CHECK RO that APP-005-D6 is received. (YES)

BOOTH OPERATOR: As soon as the power reduction is> 5% or at the discretion of the Chief Examiner, insert the next event.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 2 Page 9 of 32 Event

Description:

FT-477 fails LOW Time J Position Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 2, Feedwater Flow Transmitter FT-477 fails LOW EVENT INDICATIONS:

APP-006-A2; SIG A STM> FW FLOW APP-006-A3; SIG A LVL DEV APP-006-D2; SIG A NAR RANGE HI LEVEL FR-478 Green Pen goes low and FCV-478 opens Recognizes FT-477 has failed and performs Immediate Actions for BOP AOP-025, RTGB INSTRUMENT FAILURE.

Immediate Action Step:

BOP Place the affected FRV (FCV-478 for S/G A) in MAN.

Immediate Action Step:

BOP Restore Affected S/G Level To Between 39% And 52%.

Enters AOP-025, RTGB INSTRUMENT FAILURE, Section E, and SRO verifies Immediate Actions.

RO/BOP Make PA announcement for entry into AOP-025.

Place the affected SIG Feed Flow Selector Switch to the alternate BOP channel. (CH-476, FR-478 recorder pen will return to normal status)

Continuous Action Step:

Restore Affected Controller To Automatic:

BOP

• Check SIG level within +/- 1% of programmed level. (If YES, place in Auto and Go To Step 6)

WHEN S/G level is within +/- 1 % of programmed level, THEN place the affected Controller in AUTO.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 2 Page 10 of 32 Event

Description:

FT-477 fails LOW Time Position Applicants Actions or Behavior Reviews, briefs and directs taking FT-477 instrument out of service SRO using OWP-026, FWF-2.

Remove the affected transmitter from service using OWP-026, FWF-2.

. FR-478 selector switch selected to CH-476.

BOP . Remove FT-477 input to the CALO program.

(APP-036-L1 will be received when Hagan Rack door is opened)

. Trip bistable FC-478B-1. (APP-006-A2 will be received)

SRO Go To Procedure Main Body, Step 2.

SRO Implement the EALs.

Review ITS for applicable LCO.

. ITS Table 3.3.1-1 Item 14 which requires 2 S/G Level channels SRO (not affected by the failure) and 2 Steam Flow I Feedwater Flow mismatch channels with Condition E Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SRO Return to procedure and step in effect.

Booth Operator Initiate Event #3 (PT-444 Fails High) on cue from the Chief Examiner.

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: I Scenario # 1 Event # 3 Page 11 of 32 Event

Description:

PT-444 Fails High Time U Position Applicants Actions or Behavior BOOTH OPERATOR: When directed, initiate Event 3, PT-444 fails HIGH EVENT INDICATIONS:

APP-003-C3, PRT HIGH PRESS APP-003-C7, PZR PRESS CONTROLLER HI OUTPUT APP-003-D6, PZR PORV/SAFETY VLV OPEN APP-003-D8, PZR CONTROL HIILO PRESS APP-003-E6, PZR PORV LN HI TEMP APP-003-F6, PZR SAFETY LINE HI TEMP APP-003-A2, PCV-455C LP PROT ACTITROUB (Received once RC-536 is closed.)

Recognizes that PT-444 is failed high and performs Immediate Actions RO of AOP-025.

Immediate Action Step:

Determine if PZR PORVs should be closed.

RO

• Check Pressurizer pressure less than 2335 psig (YES).

. Verify both PZR PORVs CLOSED (NO, PCV-455C OPEN).

. Manually close RC-536, PORV BLOCK NOTE: May use PC-444J OR Spray Valve Controller in Manual to close spray valves.

Immediate Action Step:

RO Control Pressurizer Spray Valves and Pressurizer Heaters to restore RCS pressure to the desired control band.

Enters AOP-025, RTGB INSTRUMENT FAILURE, Section C and SRO verifies Immediate Actions.

NOTE: Crew will enter LCO 3.4.tA if pressure lowers < 2205 PSIG.

Pressure must be restored > 2205 psig within 2 hrs.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 3 Page 12 of 32 Event

Description:

PT-444 Fails High Time I Position Applicants Actions or Behavior Crew Make PA announcement for entry into AOP-025.

SROIRO Check PT-444 is the failed transmitter. (YES)

Control pressurizer pressure controller PC-444J:

. Place PC.-444J in MAN.

RO . Verify PZR SPRAY VALVES IN AUTO.

. Verify PZR Heaters energized as desired.

. Restore PZR Pressure to the desired control band.

Verify PCV-455C in AUTO. (Crew may decide to leave PCV-455C in RO the CLOSE position since it failed to close.)

Verify Selector Switch PM-444 is selected to operable channel:

RO

. REC-445.

SRO Informs SSO to implement EALs.

Enters LCO 3.4.1, Condition A for RCS pressure less than 2205 psig.

ITS 3.4.11, Condition B One PORV inoperable and not capable of SRO being manually cycled. Actions include the following: B.1 Close associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.2 Remove power from the associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.3 Restore PORV to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Verbally acknowledge that RC-536 must be closed and breaker open SRO within one hour. SRO may direct WCC SRO to dispatch operator to open the breaker to RC-536.

NOTE: Crew should notify WCC SRO andlor l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager.

At Chief Examiners discretion after ITS is addressed, proceed to Event 4 (RCP A #1 Seal Failure).

Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # 4 Page 13 of 32 Event

Description:

RCP A #1 Seal Failure Time 1 Position I Applicants Actions or Behavior BOOTH OPERATOR: When directed, insert Event 4, RCP A #1 seal failure.

EVENT INDICATIONS:

RCP A Seal Leakoff rising (Pen #1 on FR-I 54A)

APP-OOI-D2, RCP #1 SEAL LEAKOFF HIGH FLOW RO Refer to APP-DO 1 -D2.

Enters AOP-018, REACTOR COOLANT PUMP ABNORMAL SRO CONDITIONS.

SRO Evaluate plant conditions and Go to Section A.

Continuous Action Step:

RO Check any RCP #1 seal leakoff flow> 5.7 GPM. (YES)

Check RCP #1 seal leakoff flow on unaffected RCPs decreased (YES)

OR RO RCP Thermal Barrier DP on affected RCP decreased.

(YES)

CAUTION: To prevent damage to the RCP seal stack, the RO should close seal leakoff valve CVC-303A between 3 and 5 minutes of stopping the RCP.

Check Plant status in Mode 1, and direct tripping the Reactor, tripping SRO RCP A and then going to PATH-i.

RO Trips the reactor and trips RCP A.

Appendix D NUREG-i 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 4 Page 14 of 32 Event

Description:

RCP A #1 Seal Failure Time I Position Applicants Actions or Behavior Immediate Action Step:

RO Reactor Tripped. (YES)

Immediate Action Step:

BOP Turbine Tripped. (YES)

Immediate Action Step:

BOP E-1 AND E-2 energized (YES)

Immediate Action Step:

RO SI initiated. (NO)

Immediate Action Step:

RO SI initiation required. (NO)

Immediate Action Step:

RO Verify Two Charqinci PumiDs Runninci. (YES)

SRO Enters PATH-i and verifies PATH-i Immediate Actions.

SRO Transition to EPP-4, Reactor Trip Response.

NOTE: Following the performance and verification of PATH-I Immediate Actions, the crew will continue with AOP-018. These steps may be handed off to the ROIBOP to perform independently. The remaining steps of AOP-018 are listed here. EPP-4 actions will begin on Page 15 Critical WHEN at least 3 minutes have elapsed since tripping the affected RCP, RO/BOP Task THEN Close Seal leakoff valve for RCP A. (CVC-303A)

RO/BOP Check SI Actuated. (NO)

Appendix D NUREG-i 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # 4 Page 15 of 32 Event

Description:

RCP A #1 Seal Failure Time fl Position 1 Applicants Actions or Behavior RO/BOP Check RCP B or C running. (YES)

RO/BOP Check RCP B running (YES)

RO/BOP Check RCP C running (YES)

RO/BOP Check RCP seal injection flow between 8 and 13 GPM. (YES)

RO/BOP Check FCV-626, THERM BAR FLOW CONT Valve CLOSED. (NO)

Inform SRO to Implement EALs and Refer to Technical Specifications ROIBOP 3.4.17, 3.4.13, 3.4.4, 3.4.5, 3.4.6, 3.6.3.

BOOTH OPERATOR: When directed, Event 5, SIG B Tube Rupture will be inserted.

EPP-4 actions.

Continuous Action Steps Determine if Procedure Exit is Warranted due to attack in progress that SRO has resulted in a total loss of SW or loss of Lake Robinson Dam integrity. (NO)

Continuous Action Steps RO Check SI Signal initiated (NO) (IF SI initiation occurs the SRO will direct entry to Path-i, Entry Point A)

RO Reset SPDS and initiate monitoring of CSFST.

SRO Open Foldout A Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 4 Page 16 of 32 Event

Description:

RCP A #1 Seal Failure Time Position Aoolicants Actions or Behavior SI ACTUATION CRITERIA. (Criteria may not be met during the initial Foldout A entry depending on time Event #5 initiated.)

IF EITHER condition below occurs, THEN Actuate SI and Go To PATH RO 1, Entry Point A:

RCS Subcooling - LESS THAN 35°F [55°F]

PZR Level - CAN NOT BE MAINTAINED GREATER THAN 10% [32%]

BOP MSR Isolation Closes all Purge and Shutoff Valves RUPTURED S/G ISOLATION CRITERIA (BOP may not recognize the ruptured S/G during initial Foldout A entry depending on time Event #5 initiated and/or plant conditions.)

IF the conditions below are met, THEN perform the following:

The Ruptured S/G is identified by observing an uncontrolled level increase OR abnormal radiation level on the R-19s or R-31s.

AND The Ruptured S/G Level is Greater than 8% [18%]

BOP a. Reset SI.

b. CLOSE the appropriate Auxiliary Feedwater isolation valves to the Ruptured S/Gs.

S/G B

. V2-14B. SDAFW PUMP DISCH

. V2-16B. AFW HDR DISCH

c. WHEN desired, THEN Perform Supplement G, Steam Generator Isolation Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # I Event # 5 and 6 Page 17 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time Position 1 Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 5, S!G B Tube Rupture following the manual Reactor Trip.

Indications Available:

B SIG level trending up at a faster rate than A and C SIGs.

B SIG level continues to trend up when feed secured to B SIG.

PZR level continues to decrease.

PZR Pressure continues to decrease.

Recognizes tube rupture in B SIG and/or inability to maintain PZR RO / BOP Level greater than 10%.

RO Initiates Safety Injection.

SRO Directs entry into Path-I, Entry Point A NOTE: RO may recognize that neither SI Pump started and take early action to start both SI pumps.

NOTE: Candidate may direct that Supplement G be performed to isolate SIG B. Supplement G steps begin on Page 28.

SRO Foldout A is in effect.

RO Verify Phase A Isolation valves closed (YES)

BOP Verify FW isolation valves closed (YES)

BOP Verify both FW pumps tripped (YES)

BOP Verify both MDAFW pumps running (YES)

If Additional Feedwater is required, THEN Start SDAFW Pump BOP (Running)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 18 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time Position Applicants Actions or Behavior Verify two SI pumps running (NO) (RO will have to manually start Critical RD both SI pumps. May have been previously started after the SI was Task initiated.)

RD Verify both RHR pumps running (YES)

RD Verify SI valves properly aligned (YES)

RD At least one CCW pump running (YES)

BDP All SW & SW booster pumps running (YES)

RD Verify CV Fans HVH-1,2,3 & 4 running (YES)

RD Verify IVSW initiated (YES)

RD Verify CV ventilation isolation (YES)

BDP Verify control room ventilation aligned for pressurization mode (YES)

BDP Verify both EDGs running (YES)

Continuous Action Step BDP Restart Battery Chargers within 30 minutes of Power Loss using OR-601 (Not Required)

Continuous Action Step RD CV pressure remained below 10 psig (YES)

BDP Automatic steam line isolation initiated (ND)

BDP Automatic Steam Line Isolation Required (ND)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 19 of 32 Event

Description:

S/G B Tube Rupture and Both SI Pumps do not Auto Start Time 1 Position 1 Applicants Actions or Behavior Locally open the breaker for HVS-1 at MCC-5 within 60 minutes of SI BOP Initiation Booth Operator Open breaker for HVS-1 on MCC-5 compartment 7-J 3 minutes after being contacted by the crew.

RO RCS pressure greater than 1350 psig [1250 psig] (NO)

RO SI flow verified (YES)

RO RCS pressure >125 psig (YES)

BOP At least 300 GPM AFW flow available (YES)

BOP Verify AFW valves properly aligned (YES)

BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50%

RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (NO)

BOP Place Steam Dump Mode switch to Steam Pressure RO RCS temperature stable at or trending to 547°F (NO)

RO RCS Temperature Greater than 547°F (YES)

Dump Steam using Condenser Dumps or Steam Line PORVs to BOP attain 547°F.

RO PZR PORVs Closed (NO)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ESD-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 20 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time 1 Position Applicants Actions or Behavior RO RCS PRESS Greater Than 2335 psig (NO)

RO Close PZR PORVs RO PZR PORVs Closed (NO)

RO Close PORV Blocks RO PORV Blocks Closed (YES)

RO PZR Spray & Aux Spray valves closed (YES)

RO At least one RCP running (YES)

At least one SI Pump Running (YES) (Both SI pumps had to be RO manually_started.)

RO RCS Subcooling Less Than 35°F [55°F] (NO)

BOP Any SIG with uncontrolled depressurization (NO)

BOP Any SIG Completely Depressurized (NO)

BOP R-19s, R-31s, R-15 rad levels normal (YES)

BOP R-2, R-32A, R-32B Rad Levels Normal (YES)

RO CV Pressure Normal (YES)

RO CV Sump Level Normal (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 21 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time Position 1 Applicants Actions or Behavior RO RCS Subcooling greater than 35°F. (YES)

BOP Level in at least one SIG Greater than 8%. (YES)

RO RCS Pressure greater than 1650 psig. (NO)

RO Reset SPDS and monitor CSFSTs.

BOP Control AFW Flow to Maintain S/G Levels between 8% and 50%.

BOP Any S/G with uncontrolled level increase. (YES B S/G)

SRO Transition to Path-2, Entry Point J Reset SPDS AND Initiate Monitoring of Critical Safety Function Status RO Trees Open Foldout C CREW (No_steps_apply)

When Below 1 Q10 AMPS, THEN Energize Source Range Detectors RO AND Transfer Recorder BOP Request Periodic Activity Samples of All S/Gs BOP Place Steam Dump Mode Switch to Steam Pressure BOP Open QCV-1 0426 to bypass Condensate Polishers Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 22 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time Position 1 Applicants Actions or Behavior BOP Close C-48A AND C-48B to isolated Hotwell return to CST RO At Least One RCP Running (YES)

RO At Least One SI Pump Running (YES)

RO RCS Subcooling Less than 35°F [55°F] (NO)

BOP Ruptured S/G Identified (YES)

BOP Maintain at Least One SIG Available for RCS Cooldown Verify Ruptured Steam Line PORV Setpoint at 1035 PSIG using BOP Status Board BOP Verify RCS Temperature Less Than 547°F Prior to MSIV Closure BOP Close Ruptured S/G MSIV and MSIV Bypass BOP Ruptured S/G MSIV and MSIV Bypass Closed (YES)

Continuous Action Step BOP When Ruptured S/G Pressure decreases Below 1035 PSIG THEN Verify Ruptured Steam Line PORV Closed IF MDAFW Pump is not Available, THEN Maintain at least One S/G BOP supply to SDAFW Pump BOP Close Ruptured S/G Steam Shutoff to SDAFW Pump BOP Verify S/G Blowdown Isolation and Sample Valves Closed Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 23 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time I Position I AIicants Actions or Behavior Locally Close Warmup Steam Supply From Ruptured S/G to SDAFW BOP Pump Booth Operator Close Warmup Steam Supply Valve (MS-29) and Report action 3 Minutes after requested BOP Locally Close MSIV Above and Below Seat Drains from Ruptured S/G Booth Operator Report Above and Below Seat Drains are closed 3 Minutes after requested Isolate Feed Flow to Any Ruptured S/G that is Faulted Unless Needed BOP for RCS Cooldown Continuous Action Step BOP When Ruptured S/G Level Greater Than 8% [18%] THEN Isolate Feed Flow Continuous Action Step BOP Open Breakers for any V1-8, V2-14 AND V2-16 Valve Closed to Isolate Ruptured S/G Booth Operator Wait 3 minutes to Open Breakers as requested and report action complete.

Control Feed Flow to Maintain Intact S/G Level Between 8% [18%]

BOP and 50%

BOP Any Other S/G with Uncontrolled Level Increase (NO)

RO PZR PORVs Closed (NO)

RO RCS PRESS Greater than 2335 PSIG (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 24 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time Position I AioIicants Actions or Behavior RO CLOSE PZR PORVs RD PZR PORVs CLOSED (ND)

RO CLOSE PORV BLOCKS.

RO PORV BLOCKS CLOSED (YES)

Open At Least One PORV Block Unless Closed to Isolate an Open RD PZR PORV Continuous Action Step RD IF PZR PORV Opens on High Pressure, THEN Verify Reclosure at or Below 2335 PSIG. Close PDRV Blocks as Necessary RD Reset SI Continuous Action Step RO/BOP IF Dffsite Power is Lost, THEN Restart Emergency Safeguard Eouioment RO Reset CV Spray RD Reset Phase A and Phase B Establish Instrument Air to CV. IF Compressor not Running, THEN RD Start Compressor BOP All AC Busses Energized by Offsite Power (YES)

RO RCS Pressure Greater Than 275 PSIG [400 PSIG] (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 25 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time 1 Position 1 Applicants Actions or Behavior RO Stop RHR Pumps Continuous Action Step RO IF RCS Pressure Decreases Below 275 PSIG [400 PSIG], THEN Restart RHR Pumps Critical BOP Ruptured S/G Isolated (YES)

Task BOP Ruptured SIG Pressure Greater Than 220 PSIG (YES)

BOP At Least One Intact S/G Available for RCS Cooldown (YES)

NOTE: After the Low Steam Line Pressure SI Signal is Blocked, Main RO/BOP Steam Line Isolation will occur if Hi Steam Line Flow Rate Setpoint is Exceeded Determine Required Core Exit Temperature From Table-3 Table 3 -

Ruptured S/G Pressure (PSIG) Required Core Exit Temperature

(°F)

RO/BOP Greater than 1000 490 [4701 900-1000 480 [4601 800-900 465 [445]

700-800 450 [430]

600-700 435 [395]

Continuous Action Step RO When PZR Pressure Decreases to Less Than 2000 PSIG, THEN Block PZR Pressure/High Steam Line DP Signals RO IF RCPs are NOT Running, THEN Do Not Monitor CSF-4 BOP Condenser Available For Steam Dump (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # 5 and 6 Page 26 of 32 Event

Description:

SIG B Tube Rupture and Both SI Pumps do not Auto Start Time I Position I Applicants Actions or Behavior Verify T-AVG less Than 543°F AND Block T-AVG SI Signal Prior to RO Maximum Steam Dump BOP Place Steam Dump Control Switch to Bypass T-avg Interlock BOP Dump Steam From Intact SIG to Condenser at Maximum Rate RO At Least One Charging Pump Running (YES)

RO Align Charging Pump Suction To RWST RO Establish Charging Flow to Maintain PZR Level Core Exit Temperature Less Than Required Temperature (NO)

RO (PATH-2 begins a loop until CET is less than Required Temperature)

WHEN CET is less than Required the steps begin again.

RO Core Exit Temperature Less Than Required Temperature (YES)

BOP Reduce Steam Flow to Stabilize RCS Temperature CREW Allow RCS Temperature to Stabilize from cooldown prior to continuing BOP Ruptured S/G pressure stable or increasing (YES)

RO RCS Subcooling Greater Than 55°F [75°F] (YES)

RO Normal Spray Available (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 27 of 32 Event

Description:

S/G B Tube Rupture and Both SI Pumps do not Auto Start Time Position Applicants Actions or Behavior RO Close Spray valve associated with the idle RCP(s) using Table 1 (N/A)

RO PZR Level Greater Than 71% [60%] (NO)

RO/BOP Ruptured S/G pressure greater than RCS pressure (NO)

Continuous Action Step RO When PZR level greater than 10% [32%], Then reduce charging flow to minimum RO RCS Subcooling Less Than 35°F [55°F] (NO)

Open PZR Spray Valves to Depressurize RCS, IF Spray valves will RO not open, THEN go to Entry Point L (PATH-2 begins a loop until the PZR level is greater than 71%)

RO PZR Level Greater Than 71% [60%] (YES)

RO Verify PZR Spray and Aux Spray valves closed.

IF PZR Spray Valves fail to close, THEN Stop RCP supplying failed RO valve.

IF Aux Spray Valve Fails to close, THEN Close CVC-460A and B AND RO HCV-1 21 RO/BOP Maintain RCS and Ruptured S/G Pressures Less than 1035 PSIG RO RCS Subcooling Greater Than 35°F [55°F] (YES)

BOP Level in at least one intact S/G greater than 8% [18%] (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 and 6 Page 28 of 32 Event

Description:

S/G B Tube Rupture and Both SI Pumps do not Auto Start Time I Position Applicants Actions or Behavior RO RCS Pressure Stable or Increasing (YES)

RO PZR Level Greater Than 10% [32%] (YES)

RO Stop SI Pumps The Chief Examiner may terminate the scenario anytime after the RCS cooldown has been commenced or at his discretion.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: I Scenario # 1 Event # 5 Page 29 of 32 Event

Description:

SIG B Tube Rupture (Supplement G)

Time I Position I Aoolicants Actions or Behavior SUPPLEMENT G Steps SRO Directs the BOP to perform Supplement G to isolate SIG B Go To Appropriate Step From Following Table:

BOP S/G TO BE ISOLATED I STEP IS/GB 118 BOP Check S/G B FAULTED (NO).

Continuous Action Step BOP When Tavg less than 547°F THEN Close V1-3B and MS-353B.

Continuous Action Step BOP When S/G B level is greater than 8% THEN perform the following steps:

BOP Verify FRV B Closed (YES)

BOP Verify FRV B BYP Closed (YES)

BOP Verify V2-6B, FW HDR SECTION Valve CLOSED. (YES)

BOP Verify V214B, SDAFW PUMP DISCH Valve CLOSED. (YES)

BOP Verify V2-16B, AFW HDR DISCH Valve CLOSED. (YES)

Continuous Action Step BOP Verify B Steam Line PORV setpoint at 1035 psig using Status Board.

(YES)

BOP Verify V1-8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

Verify S/G B Blowdown AND Blowdown Sample Valve Status Light BOP indication CLOSED. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: I Scenario # 1 Event # 5 Page 30 of 32 Event

Description:

SIG B Tube Rupture (Supplement G)

Time Position 1 Applicants Actions or Behavior Dispatch Operator To The Pipe Jungle To Close MS-29, SG B BOP BYPASS DRN & WARM-UP LINE TO AFW PUMP (located above/right of VI -8 B).

Booth Operator Close Warmup Steam Supply Valve (MS-29) and Report action 3 Minutes after asked BOP Check S/G A MSIV Above And Below Seat Drain Valves CLOSED.

Booth Operator Report Above and Below Seat Drains are closed 3 Minutes after requested.

Dispatch Operator To The Aux. Bldg / Ei-E2 Room To Perform The BOP Following:

At MCC-9, verify V2-14B closed AND open breaker V2-14B, SDAFW PUMP TO S/G B (CMPT- IC)

At MCC-6, verify Vi -8B closed AND open breaker Vi -8B, SDAFW PUMP STEAM ISOLATION (CMPT-16M)

At MCC-i0, verify V2-16B closed AND open breaker V2-16B, MDAFW PUMP HEADER DISCHARGE TO S/G B (CMPT-4F)

Booth Operator Wait 3 minutes to Open Breakers as requested and report action complete BOP Go to Step 49 BOP Check All Faulted AND Ruptured S/Gs ISOLATED (YES)

BOP Check any S/G Ruptured (YES)

BOP Perform the following to minimize Secondary system contamination:

. Direct AO to start Auxiliary Boilers.

. IF Condensate Polishers are in service:

Appendix D NUREG-i 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 5 Page 31 of 32 Event

Description:

SIG B Tube Rupture (Supplement G)

Time Position Applicants Actions or Behavior

. Verify QCV-1 0426, SECONDARY BYPASS OPEN. (YES)

. Locally depress the OFF Pushbutton on Condensate Polisher Vessels A, B, C, D, E and F.

. Secure ANY evolution that passes water through the beds, such as a low volume rinse.

BOP Verify Hotwell return to CST isolated as follows:

. Locally verify C-48A, LCV-1417B INLET CLOSED.

. Locally verify C-48B, LCV-1417B DISCHARGE LOCKED -

CLOSED.

Dispatch An Operator To Close GS-36, MANUAL GLAND STEAM BOP DUMP.

End of Supplement G Steps Appendix D NUREG-1 021, Rev. 9, Supp. 1

ILC-11-1 NRC SCENARIO I TURNOVER SHEET POWER LEVEL: 100% RTP Core Burnup: 9000 MWD/MTU EFPD: 257 EFPD Boron: 745 PPM Xenon: EQ Xenon Tavg: 575.9°F Bank D Rods 218 Steps EQUIPMENT UNDER CLEARANCE:

• A COW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:

• 5 GPD Primary to Secondary Leakage identified into C S/G

• R-24C in Alarm (APP-036-C7)

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

INSTRUCTIONS FOR THE WATCH:

• Reduce Reactor Power and Turbine Load to 85% to support Maintenance on A Heater Drain Pump. A Heater Drain Pump has severe packing leakage.

Appendix D NUREG-1 021, Rev. 9, Supp. I

Unit 2 Status Board bate: Today ITime: 6:00:00AMICycle: 27 IMWD/MT: 9000 IDesign: 16590 IEFPD 257 IDesian 473.5 I Tank Level% Status HUT ]Level% Status Monitor A 10 Standby DVCS-A 20 Filling Monitor B 38 Standby CVCS-B 10 Standby WCT A 37 Standby CVCS-C 86 Standby WCT B 7 Standby NHUT #NAME? Filling WCTC 9 Standby WCTD 10 Standby inked to P1 WCTE 9 Standby VGDTS Pressure PSIG Status

1. NAME? PSIG On cover DEMINERALIZERS

. Resin B #NAME? PSIG In Service PPM In Service Date Replaced PSIG Isolated MB A 2194 YES 711712010 51412010 D [#NAME? PSIG Standby MB B 2265 NO 711712010 312912010 CATION 1021 NO 911712010 1219/2009 Shutdown Requirement Temp Boron DEB A 0 NO New 21312010 1.77% =AK1K 547 F Hot 795 DEB B 0 NO 312812010 1.77% =LK/K >350 F 1053 SFP 1963 NO 9/23/2008 412212008 2.6% LKIK 100 F Cold 1182 6%AK/K [N/A 1950 SGBD Con Jenser Air Inleakage Target Value GPM Status PORV Settings 13 CFM A 50 Flash Tank Setting Date POT [GP-3 Psig B 0 CFM B 50 With Heat f 7/18/2010 3.21 1000 Known 8 CFM C 50 Recovery B 7/18/2010 3.12 1040 Total 5 CFM N2 Flow 8 SCFM C 711 8/2010 3.44 1000 Effluent Radiation Monitor Setpoints Rad Current NUE Value RCS Leakage OOO Unidentified Monitor Setpoint Alert Value 200X 2X Total 0.03 GPM R-14C 1.OIE+04 N/A 2.020E+04 PRT 0.02 GPM R-20 7.40E+03 N/A 1.480E+04 RCDT Leakage 0.01 GPM R-18 1.OOE+06 2.000E+08 2.000E+06 Charging Leakoff 0 GPM R-19A 1.05E+04 2.IOOE+06 2.IOOE+04 Misc Identified 0 GPM R-19B 9.72E+03 1.944E+06 1.944E+04 Primary/Secondary 0 GPD R-1 9C 9.58E+03 1.91 6E+06 I .916E+04 Secondary Loss 17.3 GPM R-37 8.53E+03 1.706E+06 1.706E+04 Manuaf V Entered Data Linked to Chem data base Hi Flux At Shutdown Boron PPM Date PPM Date PPM Previous ARI Counts Setpoint RCS Today 745 Nl-31 50 150 BAST-A 9/16/2010 21,535 #NAME? #NAME?

Nl-32 60 180 BAST-B 9/16/2010 21,032 #NAME? #NAME?

SFP 9/15/2010 2246 #NAME? #NAME?

Normal Currents RWST 9/16/2010 2219 #NAME? #NAME?

UPPER LOWER TARGET %BAND Accum-A 8/30/2010 2211 #NAME? #NAME?

N-41 125 119 -1.5 5 +1- Accum-B 8/30/2010 2206 #NAME? #NAME?

N-42 110 109 -1.5 5+1- Accum-C 8/30/2010 2230 #NAME? #NAME?

N-43 105 99 -1.5 5 +/- RHR 7/6/2010 2221 N-44 98 94 -1.5 5 +1- Refuel Canal POWERTRAX Rev# 2.1.0 RNP  % APL 112.55 Refuel Cavity SFP Canal FANS Test/Hrs Date/Tst HVE-IA/B 35640.6 3/8/10 Notes/Additional Data HVE-15A 18643.5 3/18/10 lC-13, 42 HVE-19A/B 6928.3 5/3/10 MOL SR 3.7.11.2 Last Completed 5/27/2010 19:45 I

Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 2 Op Test No.:

Examiners: Operators: SRO -

RO BOP Initial Conditions:

• 50% RTP BOL, 150 MWD/MTU, 1277 ppm Boron.

. A CCW pump inoperable with the breaker racked out

• B MFP breaker racked out for maintenance.

• 5 GPD primary to secondary leakage into SIG C

. Currently thunderstorm watch is in effect for Darlington and Chesterfield counties Turnover:

• Holding reactor power at 50% for maintenance on Main Feedwater Pump B motor.

Critical Tasks:

• Isolate feedwater to S/G B

• Open at least 1 of the CV Spray Pump Discharge valves to provide CV Spray flow.

• Throttle AFW flow to the S/Gs at 80-90 GPM.

Event MaIf. Event Type* Event No. No. Description 1 (I) RO, SRO VCT Level Transmitter LT-112 fails HIGH 2 (I) RO, BOP, SRO First Stage Pressure Transmitter PT-446 fails LOW (TS) SRO 3 (C)RO,SRO CCW Pump B trips and CCW Pump C fails to auto start (TS) SRO 4 (C) BOP, SRO Condenser Vacuum leakage 5 (R)RO Load Reduction due to Condenser Vacuum lowering (N) BOP, SRO 6 (M) ALL Steam Line Break inside the CV 7 (C) ALL All S/Gs Faulted inside the CV on the Reactor Trip 8 (C) BOP Isolate feedwater to S/G B 9 (C) RO Open one of the S 1-880 valves to provide CV Spray flow 10 (C) BOP Throttle AFW flow to the S/Gs at 80-90 GPM Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 V *

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor AppendixD NUREG-1021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 ILC-11-1 NRC SCENARIO 2

SUMMARY

DESCRIPTION The crew will assume the watch with the unit being maintained at 50% RTP while maintenance is performed on Main Feedwater Pump B motor. The previous shift had identified seal leakage on CCW Pump A. The motor breaker has been racked out and the pump has been isolated and cleared for maintenance. 5 GPD primary to secondary leakage has been identified in SIG C with elevated readings on the applicable radiation monitors. Shift instructions are to maintain current reactor power until MEW Pump B is returned to service.

On cue from the Chief Examiner, VCT Level Transmitter LT-112 will fail HIGH. This will cause LCV-1 ISA to divert all letdown flow to the CVCS HUTs and will cause LC-1 12, VCT Level Controller, to go to full output. This failure will result in an automatic makeup to the VCT, which will alert the operators to determine the cause of the makeup operation. AOP-003, Malfunction of Reactor Makeup Control, will be implemented and LCV-115A will be overridden to the VCT until the VCT level control can be restored on the alternate channel. This will require that the alternate channel (LT-1 15) be selected for all control functions of VCT level. Once AOP-003 actions are completed and on cue from the Chief Examiner, First Stage Pressure Transmitter PT-446 will fail LOW.

The crew will perform the immediate actions for PT-446 failure lAW AOP-025, RTGB Instrument Failure, Section H. The immediate actions include checking that a turbine load reduction is not in progress, checking that S/G levels are being controlled in auto to 39% and placing the control rods in manual to maintain reactor power at less than 100%. The crew will perform the necessary transfer of the controlling channel and restore the S/Gs to their programmed level for the present reactor power level. The failed pressure transmitter will be removed from service lAW OWP-033, FSP-1. ITS Table 3.3.1-1 Item 17e, Turbine Impulse Pressure, P-7 input Condition T requires to verify interlock is in required state for existing unit conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Mode 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (Current plant conditions requires that the REACTOR TRIP BLOCK P-7 status light is illuminated). ITS Table 3.3.2-1 Items if, ig, 4d, and 4e for Safety Injection and Steam Line Isolation High Steam Line Flow with Low Tave or Low Steam Line Pressure Condition D: Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. ITS Table 3.3.6-1 Item 4 Safety Injection for Containment Ventilation Isolation Instrumentation refers to LCO 3.3.2 Functions l.a-f (which have already been addressed). Once the pressure transmitter has been removed from service and the Chief Examiner is satisfied with the Tech Specs compliance, the Chief Examiner will cue the next event.

CCW Pump B will trip on overcurrent and CCW Pump C will fail to auto start on CCW System low pressure. The crew will manually start the standby CCW Pump by following the actions in APP-001-F4 for motor overload, APP-001-F5 for system low pressure or enter AOP-014, Component Cooling Water System Malfunction, Section C for System Low Pressure. The SRO will implement ITS 3.7.6, Condition A due to CCW Pump B is powered from an emergency power source. Once the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event.

On cue from the Chief Examiner, Condenser vacuum leak will be initiated and vacuum will start to lower. This will be noted by rising Condenser backpressure and lowering net MWe. AOP-012, Partial Loss of Condenser Vacuum or Circulating Water Pump Trip, will be implemented. The Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Scenario Outline Form ES-D-1 standby Condenser Vacuum Pump will be started and a search for the vacuum leak will be initiated. Unit load will have to be reduced to ensure that operation within the Condenser Backpressure Limits is maintained in the allowable region of the curve. Once the Chief Examiner is satisfied with the crew response to the unit load reduction, he can cue the next event.

The steam line from S/G B will fault inside the CV. The crew will diagnose the event and make the determination that the reactor needs to be manually tripped. Upon the reactor trip, all S/Gs will be faulted inside the CV. PATH-I will be implemented with Safety Injection initiated.

The discharge valves for the CV Spray Pumps will not automatically open and will require that at least one of the valves be manually opened to provide CV Spray flow.

Feedwater Regulating Valve FCV-488 and its respective Feedwater Block valve V2-6B will fail to close on the SI signal, resulting in excessive feedwater flow into SIG B and will have to be manually closed from the RTGB control switches to terminate the flow.

The crew will transition through PATH-l and will transition to FRP-P.I, Response to Imminent Pressurized Thermal Shock, to throttle AFW flow to all of the S/Gs at a reduced rate of 80-90 GPM to each SIG. After throttling AFWthe crew will transition to FRP-H.I, Response to Loss of Secondary Heat Sink, and immediately reset SPDS and return to procedure and step in effect since entry was due to operator actions.

The Chief Examiner may terminate the scenario at any time after AFW flow has been established to all of the S/Gs at a reduced flow rate.

Appendix D NUREG-I 021, Rev. 9, Supp. I

Appendix D Operator Action Form ES-D-2 ILC-II-1 NRC SCENARIO 2 SIMULATOR SETUP IC!SETUP:

• IC-802, SCN:008_NRC_2

• A CCW Pump inoperable with the breaker racked out

• B Main Feed Pump breaker racked out for maintenance.

• 5 GPD primary to secondary leakage into SIG C

• R-15 at 24 cpm, R-19C at 232 cpm, R-31C at 0.450 mR/hr

• Status board updated to reflect lC-4.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 7: All S/Gs Faulted inside the CV Event 8: FCV-488 and V2-6B fail to Close on SI Event 9: CV Spray Pump Discharge Valves Sl-880s fail to Open EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 1: VCT Level Transmitter LT-112 fails HIGH Event 2: First Stage Pressure Transmitter PT-446 fails LOW Event 3: CCW Pump B Trips on Overcurrent and CCW Pump C fails to auto start Event 4: Condenser Vacuum Leakage Event 5: Load Reduction due to Condenser Vacuum lowering Event 6: Steam Line Break on S/G B inside the CV EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• AOP-003

• OWP-005, CVC-19

• AOP-025 Main Body and Section H

• OWP-033, FSP-I

• AOP-014 Main Body and Section C

• AOP-012

• PATH-I

• Foldout A

• FRP-P.I

• FRP-H.I Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 1 Page 6 of 27 Event

Description:

VCT Level Transmitter LT-112 fails HIGH Time Position Applicants Actions or Behavior BOOTH OPERATOR: When directed, insert Event 1, VCT Level Transmitter LT-112 fails HIGH EVENT INDICATIONS:

VCTIHLDP TK DIV LCV-1 15A aligns to the Holdup Tank LI-115 lowering Auto makeup occurs at 20 inches VCT Level LC-112 fails to full scale APP-003-E3, VCT HIILO LVL, illuminated if level decreases to 17 inches RO Diagnoses high failure of VCT level transmitter LT-1 12.

SRO Enters AOP-003, Malfunction of Reactor Makeup Control.

RO Check for failure of a level transmitter as follows:

. Obtain VCT level for LT-1 15 from ERFIS.

. Obtain VCT level for LT-1 12 from ERRS.

. Check VCT Level Indicators Oscillating Level Deviation Observed (NO)

. Check deviation between LT-1 12 and LT-1 15 greater than 8 (13%) (YES)

RO Check LT-115 failed. (NO)

RO Check LT-1 12 failed. (YES)

RO Check LT-1 12 Failed High (YES)

CAUTION: With NO operator action, LT-1 12 failing high with makeup flow less than charging suction flow will result in a loss of Charging Pump suction.

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # I Page 7 of 27 Event

Description:

VCT Level Transmitter LT-112 fails HIGH Time Position I Applicants Actions or Behavior RO Place LCV-1 1 5A, VCT I HLDP TK Dlv, to VCT position.

BOP Obtain Hagan Rack Key number 10.

BOP Implement OWP-005, CVC-19

. (OWP-005, CVC-19) Place the selector switch in the bottom of Hagan Rack 19 to LT1 15 position.

BOOTH OPERATOR: Place selector to LT-115 by inserting IRE CVCO67 LT-115 and report back that OWP-005, CVC-19 has been completed.

SRO Check OWP-005, CVC-19 COMPLETED (YES)

RO Place LCV-1 1 5A in AUTO position.

SRO Contact l&C to repair failed channel.

CREW Make PA Announcement for Procedure Entry Continuous Action Step RO Check VCT level decreases to less than 12.5 (21%) (NO)

RO Check VCT level less than 20 (33%) (NO).

RO Check VCT level less than 51.5 (86%) (YES)

Verify Charging and Letdown flows are normal for plant conditions RO (YES).

RO Check APP-003-D5, BA FLOW DEV, illuminated (NO).

Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # 1 Page 8 of 27 Event

Description:

VCT Level Transmitter LT-1 12 fails HIGH Time Position Applicants Actions or Behavior RO Check APP-003-E5, MAKEUP WATER DEV, illuminated (NO).

RO/SRO Check boration required (NO).

RO/SRO Check dilution required. (NO)

SRO Check ITS for applicable LCO. (NONE apply.)

SRO Implement the EALs (NONE apply.)

Booth Operator Insert Event #2 (PT-446 fails low) on cue from the Chief Examiner.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 2 Page 9 of 27 Event

Description:

PT-446 fails LOW Time I Position D Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 2 First Stage Pressure Transmifter PT-446 fails LOW EVENT INDICATIONS:

PT-446 pressure indication fail to 0 PSIG APP-003-D4, TAVGITREF DEV APP-005-F5, AMSAC TROUBIBYPD APP-006-D4, E4, F4, SIG A, B, C STM LINE HI FLOW TR-408 Pen #2 defaults to 547°F Determines PT-446 failed low and performs Immediate Actions of Crew AOP-025.

Immediate Action Step:

BOP Check Turbine Load Reduction in progress or has occurred.

(NO, Go TO Step 3)

Immediate Action Step:

BOP Check S/G Level trend controlling in AUTO to 39% (YES)

Immediate Action Step:

Manually control Reactor power and TAVG:

RO

• Place the Rod Control Selector Switch in Manual.

• Operate rods to maintain reactor power less than 100%.

Determines AOP-025, RTGB INSTRUMENT FAILURE and enters SRO Section H and verifies Immediate Actions.

Crew Make PA announcement for entry into AOP-025.

BOP Check SIG levels stabilized at between 39% and 52%. (YES)

Place all FRV Controllers in MANUAL:

BOP

• FCV-478, FCV-488, and FCV-498.

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 2 Page 10 of 27 Event

Description:

PT-446 fails LOW Time H Position I Aoolicants Actions or Behavior Place the First Stage Pressure Selector Switch to the alternate BOP channel (PT-447).

EXPECTEI) ALARMS:

APP-OO6-3. B3, C3 ( IG A, B, C LEVEL DEVI BOP Restore each SIG level to program level using FRVs or Bypass Valves Continuous Action Step:

Restore each FRV to AUTOMATIC as follows:

BOP

. Check S/G level within +1- 1% of program level.

. Place the affected controller in AUTO.

Continuous Action Step:

Restore Rod Control to AUTOMATIC as follows:

. Check TAvG within 0.5 to +0.5°F of TREF AND Axial Offset within RO the target band. (NO) o Restore TAVG using manual rod control prior to placing rods in auto.

. Place the Rod Control Selector Switch n AUTO.

SRO Remove PT-446 from service using OWP-033, FSP-1.

BOOTH O ERATOR: When requested, perform steps of OWP-033 to remove PT-446 from service. Actions should include AMSAC portion of OWP-033.

If requested to check PT-446, there is no visible damage or leakage noted.

SRO Go to procedure Main Body, Step 2.

SRO Inform SSO to implement EALs.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 2 Page 11 of 27 Event

Description:

PT-446 fails LOW Time Position I Applicants Actions or Behavior Check Tech Specs for applicable LCOs:

. ITS Table 3.3.1-1 Item 17e, Turbine Impulse Pressure, P-7 input Condition T requires to verify interlock is in required state for existing unit conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Mode 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (Current plant conditions requires that the REACTOR TRIP BLOCK P-7 status light is illuminated).

SRO

• ITS Table 3.3.2-1 Items If, Ig, 4d, and 4e for Safety Injection and Steam Line Isolation High Steam Line Flow with Low Tave or Low Steam Line Pressure Condition D: Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

• ITS Table 3.3.6-1 Item 4 Safety Injection for Containment Ventilation Isolation Instrumentation refers to LCO 3.3.2 Functions 1 .a-f (which have already been addressed).

SRO Return to Procedure and Step in effect.

When Tech Specs are identified and at Chief Examiners discretion, proceed to Event #3.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 3 Page 12 of 27 Event

Description:

CCW Pump 8 Trips and CCW Pump C fails to auto start Time Position Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 3, CCW Pump B Trips and CCW Pump C fails to auto start EVENT INDICATIONS:

Dual Indication on B CCW Pump FI-613 indicates 0 GPM APP-0O1-F4, CCW PMP MOTOR OVLDITRIP APP-001-F5, CCW PMP LO PRESS APP-001-B1, RCP BRG COOL WTR LO FLOW APP-001-D1, RCP THERM BAR COOL WTR LO FLOW APP-001-B7, RHR PMP A COOL WTR LO FLO APP-001-C7, RHR PMP B COOL WTR LO FLO APP-001-A8, CCW TO CRDM LOW FLOW APP-002-E1, CV SRY PMP COOL WTR LO FLOW APP-002-E5, SI PMP COOL WTR LO FLOW APP-001-A6, LTDN FLOW HI TEMP DEMIN BYPD (Delayed)

Note: Candidates may enter APP-001-F4 andlor APP-001-F5 and start the standby CCW Pump. The following steps are from the APPs.

IF the running CCW Pump has tripped, THEN VERIFY Standby CCW RO Pump STARTED ( RO manually starts C CCW Pump)

Dispatches an operator to check breaker and Current Limiter Fuses.

RO (APP-OO1 -F4)

Note: Dandidates may enter AOP-014 to address the CCW Low Pressure. The following steps if AOP-014 is entered.

SRO Directs entry to AOP-014.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 3 Page 13 of 27 Event

Description:

CCW Pump B Trips and COW Pump C fails to auto start Time JPosition Applicants Actions or Behavior SRO Implement EALs (NONE Applicable.)

Go to the appropriate section for indicated Malfunction:

SRO/RO CCW Pump Discharge Pressure Low Go to Section C RO Check Spray AND Blackout Signal Actuated (NO)

BOP Check El AND E2 Busses Energized by Offsite Power (YES)

RO Start one CCW Pump (C CCW Pump Manually started.)

RO Check CCW Pump Status At least one running (YES)

RO Check APP-00l-F5, CCW PMP LO PRESS Extinguished (YES)

RO Check FCV-626 Closed due to starting Pump (NO)

SRO Go to Main Body, Step 4, of AOP-014 RO Check RCS temperature less than 350°F (NO)

F CCW HX outlet temperature is greater than 105°F, then goto step 3 (NO)

RO OR IF CCW HX outlet temperature is less than 105°F, then go to step 4.c.

(YES)

RO Check CCW HX outlet temperature Stable OR Decreasing (YES)

RO Check APP-001-F5, CCW PMP LO PRESS Extinguished (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 3 Page 14 of 27 Event

Description:

CCW Pump B Trips and CCW Pump C fails to auto start Time Position Applicants Actions or Behavior Refer to Technical Specifications for Applicable LCOs SRO Enter LCO 3.7.6, Condition A, One required CCW train inoperable Restore required CCW train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, due to CCW Pump B OOS and is powered from an emergency power source.

SRO Return to Procedure and Step in Effect.

Booth Operator Initiate Event #4 (Condenser Vacuum leakage) after ITS entry and on cue from the Chief Examiner.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4 and 5 Page 15 of 27 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time 1 Position Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 4, Condenser Vacuum Leakage.

EVENT INDICATIONS:

Rising condenser backpressure as indicated on P1-1310, 1311, 1312 and 1313.

Lowering net MWe BOP Diagnosis the lowering condenser vacuum Immediate Action BOP Check Circulating Water Pump Any Tripped (NO)

SRO Enters AOP-012 and verifies immediate actions.

BOP Check Condenser Vacuum previously established. (YES)

Verify all available Vacuum Pumps Running. (YES)

BOP Manually start A Vacuum Pump BOP Verify Vacuum breakers MS-70A and MS-70B closed. (YES)

RO/BOP Make PA announcement for entry into AOP-012.

SRO Check plant conditions in Mode 1 or Mode 2. (YES)

Continuous Action Step:

BOP Check Condenser Backpressure approaches restricted region of Attachment 3, Condenser Backpressure Limit Curve. (NO)

Continuous Action Step BOP INCREASING (YES)

Check P1-1310 AND P1-1311 Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4 and 5 Page 16 of 27 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time Position 1 Applicants Actions or Behavior Reduce Turbine Load using Attachment 2, as necessary, to maintain CREW Condenser back pressure in the allowed region of Attachment 3.

SRO Notify Load Dispatcher of the load reduction.

Attachment 2 Turbine Load Reduction BOP Check Turbine Control Mode Automatic (YES)

BOP Depress the IMP IN Pushbutton BOP Set the Desired Load in the setter Set the Desired Load Rate (1 %/min) (Higher load rate may be chosen BOP but is not necessary)

BOP/RO Depress the GO and HOLD Pushbuttons as necessary to reduce load.

NOTE: The RO will need to add boric acid to maintain AFD within band while reducing power with Rod Control in Automatic. The following steps are for the addition of boric acid from OP-301, Section 8.2.8, Quick Boration Checklist. Boric Acid additions will most likely be added in multiple batches. Steps only listed once.

DETERMINE the amount of Boric Acid to add to the RCS and RO OBTAIN an independent check of the volume required.

RD OBTAIN permission from the CRSS OR the SSO to borate.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4 and 5 Page 17 of 27 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time Position Applicants Actions or Behavior RD PLACE the RCS MAKEUP MODE selector switch to BORATE.

RD SET YIC-1 13, BORIC ACID TOTALIZER to desired quantity.

IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN RD AND ADJUST using the UP and DOWN pushbuttons.

RD Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.

IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RD

• Rod Motion is blocked or in the wrong direction

• increases

. Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

. FCV-113A, BORIC ACID FLOW, closes.

• FCV-113B, BLENDED MU TO CHG SUCT, closes.

• IF in Auto, THEN the operating Boric Acid Pump stops.

.__The_RCS_MAKEUP_SYSTEM_is_OFF.

IF desired, THEN FLUSH the Boric Acid flow path as follows:

. PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.

. SET YIC-1 14, PRIMARY WTR TOTALIZER to 15-20 gallons.

• PLACE FCV-114B, BLENDED MU TO VCTto CLOSE.

• Momentarily PLACE RCS MAKEUP SYSTEM switch to START.

• IF any of the below conditions occur, THEN momentarily place the RD RCS MAKEUP SYSTEM switch in the STOP position:

o Unanticipated Rod Motion o Primary Water addition reaches the desired value

• WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

o FCV-ll4Acloses.

o FCV-113B closes.

o IF in Auto, THEN the operating Primary Water Pump stops.

o__The_RCS_MAKEUP_SYSTEM_is_OFF.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4 and 5 Page 18 of 27 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time I Position Aoolicants Actions or Behavior RETURN the RCS Makeup System to automatic as follows:

. VERIFY FCV-114A is in AUTO.

. PLACE FCV-1 14B to the AUTO position.

RO . PLACE the RCS MAKEUP MODE switch in AUTO.

. VERIFY FCV-1 1 3A is in AUTO.

• Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START Dosition.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER TOTALIZER, RD YIC-1 14 AND Boric Acid TOTALIZER, YIC-1 13 the total amount of Primary Water AND Boric Acid added during the boration.

MONITOR parameters for the expected change in reactivity AND RD inform the CRSS OR the SSO of the results of the boration.

END OF BORATION STEPS BOP Check Condenser Nitrogen Addition in service (YES)

Dispatch an Operator to Close NS-143, N2 Injection to Condenser BOP isolation BOP Verify all available Circ. Water Pumps running (YES)

BOP Check APP-008-F3, EXH HOOD HI TEMP Alarm Illuminated (NO)

Continuous Action Step BOP Check TURBINE GENERATOR SUPERVISORY RECORDER - ANY VIBRATION GREATER THAN 14.0 MILS (NO)

BOP Check status of Auxiliary Boilers In Service (NO)

BOP Check Blowdown status Split between flash tank and condenser (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4 and 5 Page 19 of 27 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time I Position Aoolicants Actions or Behavior BOP Check Cause of Vacuum Loss Identified (NO)

SRO/BOP Dispatch personnel to locally perform Attachment 1, Local Actions.

CREW Monitor Condenser Backpressure during performance of Attachment 1.

SRO/BOP Notify Chemistry Personnel to Monitor Secondary Chemistry.

Direct measurement of condenser Inleakage using OP-504, Condenser SRO/BOP Air Removal BOP Check Cause of Vacuum Loss Found (NO)

BOOTH OPERATOR: As soon as the power reduction is > 5% or at the discretion of the Chief Examiner, insert Event 6, Steam Line Break on SIG B inside the CV.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8, 9, 10 Page 20 of 27 Event

Description:

Steam Line Break on SIG B inside the CV, All S/Gs Faulted inside the CV on the Reactor Trip, Isolate feedwater to S/G B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the S/Gs at 80 90 GPM.

Time I Position 1 Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 6, Steam Line Break on SIG B inside the CV.

EVENT INDICATIONS:

APP-002-B7 CV Narrow Range HiILo Pressure APP-006-E4 SIG B Steam Line Hi Flow B S!G Pressure Dropping CV Pressure Rising CREW Crew will determine that a Reactor Trip is required.

SRO Directs RO to Manually trip the reactor.

Note: Upon manually tripping the Reactor All SIGs become faulted inside the CV.

PATH-I Actions RO Immediate Action Step Reactor tripped (YES)

Immediate Action Step BOP Turbine tripped (YES)

Immediate Action Step BOP El & E2 energized (YES)

Immediate Action Step RO SI initiated (YES)

Open Foldout A RCP TRIP CRITERIA IF the PHASE B Isolation Valves are Closed, THEN stop all RCPs.

(YES)

Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8, 9, 10 Page 21 of 27 Event

Description:

Steam Line Break on S/G B inside the CV, All SJGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to S/G B, Open one of the SI-880 to provide CV Spray Flow, Throttle AFW flow to the S/Gs at 80 90 GPM.

Time Position Aølicants Actions or Behavior MSR Isolation Criteria BOP IF ANY Purge OR Shutoff Valve does not indicated fully closed. THEN place the associated RTGB Switch to CLOSE FAULTED SIG ISOLATION CRITERIA IF both the conditions below are met, THEN perform the following:

. Any SIG pressure is decreasing in an uncontrolled manner OR Any SIG has completely depressurized.

AND BOP . At least ONE S/G is intact (NO, all faulted)

a. Reset SI.

b. CLOSE the appropriate Auxiliary Feedwater isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed.

RO Verify Phase A Isolation valves closed (YES)

Verify FW isolation valves closed (NO)

Critical . Manually closes FCV-488 1

Task BOP . Manually closes V2-6B 1

(Candidate must close at least one of the above valves to isolate FW Flow to SIG B to meet the Critical Task.)

BOP Verify both FW pumps tripped (YES)

BOP Verify both MDAFW pumps running (YES)

If Additional Feedwater is required, THEN Start SDAFW Pump BOP (Tripped on Low Pressure)

RO Verify two SI pumps running (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8, 9, 10 Page 22 of 27 Event

Description:

Steam Line Break on SIG B inside the CV, All S/Gs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the S/Gs at 80 90 GPM.

Time 1 Position I Applicants Actions or Behavior RO Verify both RHR pumps running (YES)

RO Verify SI valves properly aligned (YES)

RO At least one CCW pump running (YES)

BOP All SW & SW booster pumps running (YES)

RO Verify CV Fans HVH-1 ,2,3 & 4 running (YES)

RO Verify IVSW System initiated (YES)

RO Verify CV ventilation isolation (YES)

BOP Verify control room ventilation aligned for pressurization mode (YES)

BOP Verify both EDGs running (YES)

Continuous Action Step BOP Restart Battery Chargers within 30 minutes of Power Loss using OP 601 (Not Required)

Continuous Action Step RO CV pressure remained below 10 psig (NO)

NOTE: Crew should identify and announce that Adverse Numbers are in effect.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8, 9, 10 Page 23 of 27 Event

Description:

Steam Line Break on SIG B inside the CV, All S/Gs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 90 GPM.

Time 1 Position Applicants Actions or Behavior RD Verify CV Spray Initiated (YES)

Critical Verify All CV Spray Pumps Running With Valves Properly Aligned 1

Task (NO)

RO

• Manually Opens Sl-880A,B,C and D (Candidate must open at least one of the Sl-880 Valves to meet the Critical Task.)

Verify Approximately 12 GPM Spray Additive Tank Flow (RD will RD throttle flow using SI-845C)

RD Verify Phase B Isolation Valves Closed (YES)

RD Stop All RCPs BOP Verify All MSIVs AND MSIV Bypasses Closed Locally Open Breaker for HVS-1, At MCC-5 Compartment 7J within 60 BOP minutes of SI Initiation Booth Operator_After 3 mm delay open the breaker for HVS-1, MCC-5, Compartment 7J RD RCS pressure greater than 1350 psig [1250 psig] (YES)

BDP At least 300 gpm AFW flow available (YES)

BDP Verify AFW valves properly aligned (YES)

BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50%

Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8, 9, 10 Page 24 of 27 Event

Description:

Steam Line Break on SIG B inside the CV, All S/Gs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the S/Gs at 80 90 GPM.

Time Position 1 Applicants Actions or Behavior RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (YES)

RO At Least one Charging Pump Running (YES)

RO Greater than 5 inches Thermal Barrier AP on all Running RCPs (YES)

BOP Place Steam Dump Mode switch to Steam Pressure RO RCS temperature stable at or trending to 547°F (NO)

RO RCS Temperature greater than 547°F (NO)

RO Attempt to limit cooldown If RCS cooldown continues and is not due to SI flow, then close all BOP MSIVs and MSIV bypasses RO PZR PORVs Closed (YES)

RO PZR Spray & Aux Spray valves closed (YES)

RO At Least One RCP Running (NO)

BOP Any S/G with Uncontrolled Depressurization (YES)

Reset SPDS AND Initiate Monitoring of Critical Safety Function Status RO Trees Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8, 9, 10 Page 25 of 27 Event

Description:

Steam Line Break on S/G B inside the CV, All S/Gs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the SI880 to provide CV Spray Flow, Throttle AFW flow to the S/Gs at 80 90 GPM.

Time I Position I Aoolicants Actions or Behavior Transition to FRP-P.1, Response to Imminent Pressurized Thermal SRO Shock, due to an ORANGE on CSF-4.

Continuous Action Step Check CST Level Less than 10% (NO)

BOP If becomes less than 10% align Service Water to the suction of AFW Pumps using OP-402.

Determine if RCS Cooldown is due to a Large Break LOCA (NO)

Check both of the following conditions exist:

RO RCS pressure LESS THAN 275 PSIG [400 PSIG] (NO)

AND RHR flow on FI-605 GREATER THAN 1200 GPM (NO)

RO Check RCS Cold Leg Temperature Decreasing (YES)

BOP Verify Steam Line PORVs Closed (YES)

BOP Verify Steam Dumps Closed (YES)

RO Check RHR System Aligned for core cooling (NO)

BOP Check S/G Status Any Intact (NO)

BOP Verify closed all MSIVs and MSIV BYPs. (YES)

Verify closed all Steam Shutoffs to the SDAFW Pump.

BOP Close V1-8A, -8B, -8C Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8, 9, 10 Page 26 of 27 Event

Description:

Steam Line Break on SIG B inside the CV, All S/Gs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the S/Gs at 8090 GPM.

Time Position Applicants Actions or Behavior Critical Maintain feed flow to each SIG between 80 gpm and 90 gpm Task BOP BOP will coordinate with AOs to open the breakers to the AFW Discharge Valves and manually throttle them to achieve 80 to 90 gpm.

Identifies RED on Heat Sink Critical Safety Function Status Tree and C REW enters FRP-H.1, Response to Loss of Secondary Heat Sink.

Check Total Feed Flow LESS THAN 300 GPM DUE TO BOP OPERATOR ACTION (YES)

SRO Reset SPDS and Return to Procedure and Step in Effect The Chief Examiner may terminate the scenario anytime after reduced AFW flow has been established to all of the SIGs.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

ILC-11-1 NRC SCENARIO 2 TURNOVER SHEET POWER LEVEL: 50% RTP Core Burnup: 150 MWD/MTU EFPD: 4.3 EFPD Boron: 1277 PPM Xenon: EQ Xenon Tavg: 560°F Bank D Rods 153 Steps EQUIPMENT UNDER CLEARANCE:

• A CCW Pump QOS and Breaker Racked Out

• B Main Feed Pump OOS and Breaker Racked Out EQUIPMENT STATUS:

• 5 GPD Primary to Secondary Leakage identified on C S/G.

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

INSTRUCTIONS FOR THE WATCH:

Holding reactor power at 50% for maintenance on Main Feedwater Pump B motor.

AppendixD NUREG-1021, Rev. 9, Supp. 1

Unit 2 Status Board IDate: Today ITime: 6:0O:0OAMlCycle: 127 IMWDIMT: 1150 IDesign: 16590 IEFPD 4.3 IDesign 473.5 I Tank [Level% Status HUT Level % I Status MonitorA 10 Standby CVCS-A 20 Filling Monitor B 38 Standby CVCS-B 10 Standby WCT A [37 Standby CVCSC 86 Standby WCT B [7 Standby WHUT #NAME? Filling WCT C [9 Standby WCT D [10 Standby ked to P1 WCT E [9 Standby WGDTS Pressure PSIG Status A #NAME? PSIG Ion cover ,JCIv,,i.crnL.iLtRS

. Resin B #NAME? PSIG In Service PPM In Service Date Replaced C #NAME? PSIG Isolated MB A 2194 YES 7117/2010 5/412010 D [#NAME? PSIG Standby MB B 2265 NO 7/17/2010 3/29I2010 CATION 1021 NO ó1i2I9I2i Shutdown Requirement I Temp 547 Boron DEBA 0 NO New 2/3/2010 1.77%=tKiK F Hot 1051 DEB B 0 NO [3/28/2010 1.77%=zM(/K >350F 1281 SFP 1963 NO 9123/2008 [412212008 2.6% KIK 100 F Cold 1430 6%=AKIK [N/A 1950 SGBD Con ienser Air Inleakage Target Value GPM [Status PORV Settings A 13 CFM A 50 Flash Tank Setting Date POT______ GP-3 Psig B 0 CFM B 50 With Heat A jii/201O 3.21 1000 Known 8 CFM C 50 Recovery BJ2010 3.12 1040 Total 5 CFM N2 Flow 8 SCFM C 7/18,2010 3.44 1000 Effluent Radiation Monitor Setpoints Rad Current [NUE Value RCS Leakage 0.00 Unidentified Monitor Setpoint Alert Value 200X 2X Total 0.03 GPM R-14C 1.OIE+04 N/A 2.020E+04 PRT 0.02 GPM R-20 7.40E+03 N/A 1 .480E+04 RCDT Leakage 0.01 GPM R-18 1.OOE+06 2.000E+08 2.000E+06 Charging Leakoff 0 GPM R-19A 1.05E+04 2.IOOE+06 2.IOOE+04 Misc Identified 0 GPM R-19B 9.72E+03 1.944E+06 1.944E+04 Primary/Secondary 0 GPD R-19C 9.58E+03 1.916E+06 1.916E+04 Secondary Loss 17.3 GPM R-37 8.53E+03 1.706E+06 1.706E+04 Manually nterecl Uata Linked to C em data base Hi Flux At Shutdown Boron PPM Date [PPM Date LPPM Previous ARI Counts Setpoint RCS Today 1277 NI-31 50 150 BAST-A 9116/2010 21,535 #NAME? #NAME?

NI-32 60 180 BAST-B 9116/2010 21,032 #NAME? #NAME?

SFP 9/15/2010 2246 #NAME? #NAME?

Normal Currents RWST 9/16/2010 2219 #NAME? #NAME?

UPPER LOWER TARGET %BAND Accum-A 8/30/2010 2211 #NAME? #NAME?

N-41 ioi 2.3 5 +1- Accum-B 8/30/2010 2206 #NAME? #NAME?

N-42 101 100 2.3 5 +1- Accum-C 8/30/2010 2230 #NAME? [#NAME?

N-43 96 89 2.3 5 +1- RHR 7/6/2010 2221 N-44 [91 87 2.3 5 +1- Refuel Canal POWERTRAX Rev# 2.1.0 RNP 1% APL 112.55 Refuel Cavity SFP Canal FANS TestiHrs DatelTst HVE-IAIB 35640.6 318110 Notes/Additional Data HVE-15A 18643.5 3118110 IC-4 HVE-19A/B 31 5

ij 6928 0

i BOL SR 3.7.11.2 Last Completed 5/27/2010 [19:45 I

Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 3 Op Test No.:

Examiners: Operators: SRO -

RO BOP Initial Conditions:

• 1E-8 amps BOL, 150 MWD/MTU, 1531 ppm Boron.

• A CCW pump inoperable with the breaker racked out.

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

Turnover:

• Maintain current reactor power until the RCP C oil leak issue is resolved.

Critical Tasks:

• Align low head injection by starting RHR Pump A and opening RHR 744A or 744B valves.

. Start HVE-19A or 19B for Control Room Pressurization

. (Conditional) Restore seal injection by starting one charging pump.

• Identify that Emergency Coolant Recirculation capability has been lost and implement EPP-15.

Event Maif. Event Type* Event No. No. Description 1 (C) BOP, SRO HVE-3 (CV Iodine Removal Fan) Trips 2 (I) RO, SRO PT-145 Letdown Pressure Transmitter Fails LOW 3 (N) RO, SRO Place Excess Letdown in Service 4 (C) BOP, SRO Service Water Booster Pump B Trips (TS) SRO 5 (C)ALL Degraded Voltage on System Grid (TS) SRO 6 (M) ALL LOCA occurs when the reactor trips 7 (C) ALL Safeguards sequencers fail to start loads 8 (C) RO Restoration of Charging Pump I Seal Cooling 9 (C) RO RHR Pump A trips 10 (C) RO Loss of Emergency Coolant Recirculation capability requires entry into EPP-15 Appendix D NUREG-1 021, Rev. 9, Supp. 1

I Appendix D Scenario Outline Form ES-D-1 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor ILC-11-1 NRC SCENARIO 3

SUMMARY

DESCRIPTION The crew will assume the watch with the reactor at 1 E-8 amps and the turbine on the turning gear with GP-005 in effect. The unit is being maintained in the present configuration while Engineering personnel resolve the RCP C oil leak issue. The previous shift had identified seal leakage on CCW Pump A. The motor breaker has been racked out and the pump has been isolated and cleared for maintenance. Shift instructions are to maintain current reactor power until the RCP oil leak issue is resolved.

On cue from the Chief Examiner, HVE-3 (CV Iodine Removal Fan) will trip. APP-010-C6 is received and HVE-3 has lost indication on the RTGB. The crew will investigate and proceed to start HVE-4 to restore the cooling function for the CV Dome Vent. Once APP-01 0 actions are completed, the Chief Examiner can cue the next event.

Pressure Transmitter PT-i 45 for Letdown Line Pressure will fail LOW, causing PCV-145 to close and isolate letdown flow. AOP-025, RTGB Instrument Failure, Section A will be implemented to isolate the letdown line, reduce charging flow and place Excess Letdown in service. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.

Service Water Booster Pump B will trip on overcurrent. APP-002-A8, B8, C8 and D8 will be received when the pump trips and will direct the crew to start the standby SWBP and restore normal flow to the CV HVH units. ITS 3.7.7, Condition A, one Service Water System (SWS) train inoperable Restore SWS train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, will be entered for the SWBP failure and ITS 3.6.6, Condition D, Two Containment Cooling Trains inoperable Restore one containment cooling train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, will be entered due to the failure to meet SR 3.6.6.3 (Verify cooling water flow rate to each cooling unit is > 750 gpm) for the CV HVH units. Once the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event.

On cue from the Chief Examiner, the system load dispatcher will notify the control room that system grid voltage is unstable and LOCA voltage cannot be maintained for offsite power. ITS 3.8.1, Condition A, The qualified offsite circuit inoperable Declare required features(s) with no offsite power available inoperable when its redundant required feature(s) is inoperable within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Restore offsite circuit to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be entered due to the offsite power source being inoperable. APP-036-E3 will be received and the crew will monitor 115kV and 230kV voltages. AOP-026, Grid Instability, will be entered. Grid voltage will continue to lower until 480V Busses E-1 and E-2 separate from the grid due to the actuation of the Degraded Grid Voltage relays for the Emergency Busses, the Emergency Diesel Generators start and re-energize the busses. When 480V Bus E-1 separates from the grid, a reactor trip signal will be generated due to de-energizing Intermediate Range N-35. The crew will have to manually trip the reactor from the RTGB once it is identified that the reactor did not automatically trip.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

• Appendix D Scenario Outline Form ES-D-i The reactor trip will trigger a LOCA and an SI will be generated. The crew will enter PATH-i and continue through the actions of the PATH. The SDAFW pump trips while attempting to start. No loads will start on the safeguards sequencers. The operators must manually start safeguards loads.

Valves RHR-744A and 744B will not automatically open when the SI signal is generated. The RO will open at least one of the valves to ensure that low head core injection is available. This will be identified during the initial phase of the Safety Injection signal as PATH-i determines that the SI valves are properly aligned.

The crew will manually start a Charging Pump within the 15 minutes to restore seal injection to the RCPs or determine that the 15 minute criteria has been exceeded and choose to allow the pump to remain idle. Charging Pumps B and C will be available once the SI signal has been reset. Charging Pump A will be available if the crew directs that the Dedicated Shutdown Diesel Generator be started in accordance with EPP-25, Energizing Supplemental Plant Equipment using the DSDG, to re-energize the 480V Bus DS.

Once FRP-P.i has been exited, RHR Pump A will trip and meet the conditions that Supplement D components cannot be met. This will lead to the entry of EPP-1 5 due to loss of emergency recirculation capability. EPP-i 5 will be entered with the subsequent restoration of RHR Pump B.

This will allow EPP-i5 to be exited based on the first continuous action step that emergency recirculation capability has been restored.

The Chief Examiner may terminate the scenario when the crew has made the determination that EPP-15, Loss of Emergency Coolant Recirculation, can be exited.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 ILC-II-I NRC SCENARIO 3 SIMULATOR SETUP ICISETUP:

• IC-803, SCN: 008_NRC_3

• A CCW Pump inoperable with the breaker racked out

• Status board updated to reflect IC-i.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 6: LOCA occurs when the reactor trips Event 7: Safeguards sequencers fail to start loads EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

Event 1: HVE-3 (CV Iodine Removal Fan) Trips Event 2: Low Pressure Letdown PT-145 fails LOW Event 3: Place Excess Letdown in Service Event 4: Service Water Booster Pump B Trips Event 5: Degraded Voltage on System Grid Event 8: Restoration of Charging Pump I Seal Cooling Event 9: RHR Pump A trips Event 10: Loss of Emergency Coolant Recirculation capability requires entry into EPP-15 EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• APP-OIO-C6

• OP-921, Section 8.12

• AOP-025 Main Body and Section A

• AOP-025 Attachment 2

• APP-002-A8, B8, C8, D8

• APP-036-E3

• AOP-026

• PATH-I

• Foldout A

• Foldout B

• FRP-P.I

• EPP-15 Appendix D NUREG-l 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 OpTestNo.: Scenario # 3 Event # 1 Page 5 of 23 Event

Description:

HVE-3 (CV Iodine Removal Fan) Trips Time .

Position I Applicants Actions or Behavior BOOTH OPERATOR: When directed, insert Event I, HVE-3 Trip EVENT INDICATIONS:

APP-OIO-C6 HVE-3 AIR TROUB I MOTOR OVLD HVE-3 has no RTGB indication.

Announce APP-010-C6, HVE-3 AIR TROUB I MOTOR OVLD, BOP ill urn mated.

BOP Check Breaker at MCC-5, CMPT 8B, for tripped condition. (YES)

BOP Check damper positions. (YES DOME VENT)

IF the breaker has tripped, THEN ATTEMPT Reclosure once (YES BOP the breaker would not close.)

BOP Start HVE-4, CV IODINE RMVL FAN. (OP-921 Section 8.1.2)

Booth Operator Insert Event #2 (PT-I 45 fails LOW) on cue from the Chief Examiner.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 and 3 Page 6 of 23 Event

Description:

PT-i 45 fails LOW Time I Position I Applicants Actions or Behavior BOOTH OPERATOR: Event 2 PT-I 45 fails LOW EVENT INDICATIONS:

APP-OOI-E6, LP LTDN RELIEF HI TEMP Letdown flow will lower to zero gpm.

Per APP-OO1-E6, IF PCV-145 is malfunctioning, THEN REFER to RO AOP-025.

SRO Enters AOP-O25 for PT-145 Malfunction.

RO Place LCV-460A & B in the CLOSE Position.

RO Verify ONLY ONE Charging Pump Running Place Excess Letdown In Service Using Attachment 2, Placing Excess RO Letdown in Service NOTE: The following steps will place Excess Letdown in Service using ttachment 2. Actions of AOP-025 will continue on Page 7.

Verify Closed the following valves:

. LCV-460A & B, LTDN LINE STOP

. CVC-200A, LETDOWN ORIFICE ISOLATION RO/BOP

• CVC-200B, LETDOWN ORIFICE ISOLATION

. CVC-200C, LETDOWN ORIFICE ISOLATION

. CVC-204A. LETDOWN LINE ISO

.__CVC-204B,_LETDOWN_LINE_ISO RO/BOP Verify Open CC-739, CCW FROM EXCESS LTDN HX. (YES)

RO/BOP Position CVC-389, EXCESS LTDN DIV, to the RCDT Position Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 and 3 Page 7 of 23 Event

Description:

PT-i 45 fails LOW Time Position Applicants Actions or Behavior RO/BOP Open CVC-387, EXCESS LTDN STOP SLOWLY OPEN HCV-1 37, EXCESS LTDN FLOW not to exceed RO/BOP 195°F as indicated on TI-I 39, EXCESS LTDN HX OUTLET TEMP ROBOP Notify the CRS that Excess Letdown is in service Update the ERFIS Calorimetric program to reflect Excess Letdown is RO/BOP in service.

IF required to control Pressurizer level, THEN CONTACT Chemistry RO/BOP to perform the alignment for purging the Pressurizer Liquid sample line with full flow to the VCT lAW CP-003 RO/BOP Position CVC-389 EXCESS LTDN Dlv, to the VCT Notify Radiation Control that Excess Letdown is in service through the RO/BOP Seal Water Return Filters and Heat Exchanger, which will result in INCREASED radiation levels in these areas.

Note End of Attachment 2, Placrng Excess Letdown In Service Crew Make PA Announcement for procedure entry.

RD Check RCP Seal Injection Flow Between 8 GPM and 13 GPM (YES)

SRO Contact Plant Operations Staff to Expedite Repair of PT-145.

SRO Implement the EALs Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 and 3 Page 8 of 23 Event

Description:

PT-i 45 fails LOW Time I , Position I Applicants Actions or Behavior Check Technical Specifications for applicable LCOs SRO ITS LCO, 3.3.1, 3.3.2, 3.3.3, 3.3.4, 3.4.1, 3.4.9, 3.4.17.

SRO Return to Procedure and Step In Effect.

Booth Operator Insert Event #4 (Service Water Booster Pump B Trips) on cue from the Chief Examiner.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 4 Page 9 of 23 Event

Description:

Service Water Booster Pump B Trips Time I Position Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 4, Service Water Booster Pump B Trips.

EVENT INDICATIONS:

APP-002-A8, HVH-1 WTR OUTLET LO FLOW APP-002-B8, HVH-2 WTR OUTLET LO FLOW APP-002-C8, HVH-3 WTR OUTLET LO FLOW APP-002-D8, HVH-4 WTR OUTLET LO FLOW Service Water Booster Pump B Lost Indication Enters APP-002-A8, B8, C8 and D8. Recommends starting Standby RO Service Water Booster PumiD BOP Starts Service Water Booster Pump A Dispatches AO to check local indication of A SWBP and breaker for BOP B SWBP Declares B SWBP out of service and enters ITS 3.7.7, Condition A, one Service Water System (SWS) train inoperable Restore SWS train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, will be entered for the SWBP failure and ITS 3.6.6, Condition D, Two Containment Cooling Trains SRO inoperable Restore one containment cooling train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, will be entered due to the failure to meet SR 3.6.6.3 (Verify cooling water flow rate to each cooling unit is > 750 gpm) for the CV HVH units.

Booth Operator Prior to Event #5 (Degraded Voltage on System Grid) initiation, notify the Control Room as the Load Dispatcher that problems on the system grid has caused voltage instability and that LOCA voltage support cannot be maintained (The crew needs enough time to implement ITS 3.8.1 for the off-site power circuit prior to initiating Event #5).

Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5 Page 10 of 23 Event

Description:

Degraded Voltage on System Grid Time 1 Position 1 Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 5, Degraded Voltage on System Grid.

EVENT INDICATIONS:

APP-036-E3, SUT PRI OVER/UNDER VOLTAGE 115 kVvoltage lowering 230 kV voltage lowering SRO will enter the ITS requirement due to the notification from the load dispatcher.

ITS 3.8.1, Condition A, The qualified offsite circuit inoperable Declare SRO required features(s) with no offsite power available inoperable when its redundant required feature(s) is inoperable within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Restore offsite circuit to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be entered due to the offsite power source being inoperable.

CREW Enter AOP-026, Grid Instability.

RO Check Plant Status Mode 1 or 2 (YES)

Continuous Action Step RO/BOP Check system frequency Less than 58.4 Hz (NO)

Crew Make PA Announcement for AOP-026 Entry Check ANY of the following Diesel Generators Paralleled to the Grid.

BOP (NO)

BOP Check Turbine Status On Line (NO)

Check with Load Dispatcher Adequate Voltage Support is Presently BOP Available For a LOCA Event (NO)

Declare off-site power Inoperable and implement the required actions SRO of ITS 3.8.1 and Notify personnel and Evaluate plant risk.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5 Page 11 of 23 Event

Description:

Degraded Voltage on System Grid Time 0 Position Applicants Actions or Behavior BOP Monitor ERFIS Points for BOTH Emergency Bus Voltages Continuous Action Step BOP Check Emergency Bus E-1 AND E-2 Voltage Decreased to Less than 430 Volts for greater than 10 seconds. (YES)

Verify the following for the affected Emergency Bus:

. Normal supply breaker opens (YES)

BOP

. EDG starts (YES)

. EDG output breaker closes. (YES)

NOTE: When 480V Bus E-I separates from the grid, a reactor trip signal will be generated due to de-energizing Intermediate Range N-35.

The crew will identify that the reactor did not automatically trip and manually trip the reactor and enter PATH-I.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: I Scenario # 3 Event # 6 Page 12 of 23 Event

Description:

LOCA when Reactor Trips.

Time I Position Applicants Actions or Behavior BOOTH OPERATOR: The reactor trip will automatically trigger a LOCA. Safeguards sequencers will fail to start loads.

EVENT INDICATIONS:

RCS Pressure Lowering Rapidly PZR Level Lowering Rapidly Containment Sump Level and Pressure Rising Rapidly Safety Injection has automatically initiated.

PATH-I Actions RO Immediate Action Step Reactor tripped (YES)

Immediate Action Step BOP Turbine tripped (YES)

Immediate Action Step BOP El & E2 energized (YES)

Immediate Action Step RO SI initiated (YES)

Open Foldout A RCP TRIP CRITERIA IF BOTH conditions below are met, THEN stop all RCPs: (YES)

RO

. SI Pumps AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE

. RCS Subcooling LESS THAN 35°F [55°F]

EXCESS LETDOWN ISOLATION CRITERIA IF a Phase A Isolation signals occurs, THEN verify:

RO

. CVC-387, EXCESS LTDN STOP CLOSED

.__HIC-137,_EXCESS_LTDN_FLOW -_CONTROLLER AT 0%

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6 Page 13 of 23 Event

Description:

LOCA when Reactor Trips.

Time 1 Position 0 Applicants Actions or Behavior MSR ISOLATION CRITERIA IF ANY Purge OR Shutoff Valve does not indicate fully closed, THEN BOP place the associated RTGB Switch to CLOSE.

END Foldout A RO Verify Phase A Isolation valves closed (YES)

BOP Verify FW isolation valves closed (YES)

BOP Verify both FW pumps tripped (YES)

BOP Verify both MDAFW pumps running (YES)

If Additional Feedwater is required, THEN Start SDAFW Pump (NO)

BOP (SDAFW Pump tripped on overspeed. Unable to restart.)

Verify two SI pumps running (NO)

RO

.__Starts_SI_Pumps_(May_have_been_previously_done.)

Verify both RHR pumps running (NO)

RO

.__Starts_A_RHR_pump_(May_have_been_previously_done.)

Critical Verify SI valves properly aligned (NO RHR-744A and RHR-744B did Task not open automatically.)

RO

. Opens RHR-744A and RHR-744B with RTGB Control Switch.

(May_have_been_previously_done.)

RO At least one CCW pump running (YES)

BOP All SW & SW booster pumps running (NO)

BOP Attempt to start all SW and SWBPs Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6 Page 14 of 23 Event

Description:

LOCA when Reactor Trips.

Time Position Applicants Actions or Behavior BOP North OR South SW HDR low pressure alarms illuminated. (NO)

Verify CV Air Recirc Coolers HVH-1 ,2,3 & 4 running (NO)

RO

. StartsHVH-1,2,3&4.

RO Verify IVSW System initiated (YES)

RO Verify CV ventilation isolation (YES)

Critical Verify control room ventilation aligned for pressurization mode (NO)

BOP Task

• Manually start HVE-19A BOP Verify both EDGs running (YES)

Continuous Action Step BOP Restart Battery Chargers within 30 minutes of Power Loss using OP 601 (Not Required Battery Chargers Automatically restart.)

Continuous Action Step RO CV pressure remained below 10 psig (NO)

RO Verify CV Spray Initiated. (YES)

Verify ALL CV Spray Pumps Running with Valves Properly Aligned RO (YES)

Verify Approximately 12 GPM Spray Additive Tank Flow. (Manually RO throttles Sl-845C from RTGB.)

RO Verify Phase B Isolation Valves Closed. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # 6 Page 15 of 23 Event

Description:

LOCA when Reactor Trips.

Time I Position J Applicants Actions or Behavior RO Stop all RCPs (All previously secured.)

BOP Verify All MSIVs AND MSIV Bypasses closed. (YES)

Locally open the breaker for HVS-1 at MCC-5 within 60 minutes of SI BOP Initiation Booth Operator Open breaker for HVS-1 on MCC-5 compartment 7-J approximately 3 minutes after being contacted by the crew RO RCS pressure greater than 1350 psig [1250 psig] (NO)

RO SI flow verified (YES)

RO RCS pressure >125 psig (NO)

RO RHR flow verified (YES)

BOP At least 300 gpm AFW flow available (YES)

BOP Verify AFW Valves Properly Aligned (YES)

BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50%

RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (YES)

RO At least one charging pump running (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6 Page 16 of 23 Event

Description:

LOCA when Reactor Trips.

Time 1 Position 1 Applicants Actions or Behavior RD Stop all RCPs IF adequate diesel capacity not available to run charging pumps THEN RD shed non-critical loads using Supplement F RD Reset SI Continuous Action Step CREW IF offsite power is lost, THEN restart emergency safeguards equipment.

Critical IF seal injection has been lost for less than 15 mm then start one Task charging pump. (YES)

RD

• Start B or C Charging Pump.(or do not start a charging pump, dependent on the time elapsed since the loss of charging)

BDP Place Steam Dump Mode switch to Steam Pressure RO RCS temperature stable at or trending to 547°F (ND)

RD RCS temperature greater than 547° F (ND)

RD Attempt to limit cooldown IF RCS Cooldown continues and is not due to SI flow, THEN CLOSE RO MSIVs and MSIV Bypasses.

• MSIV and MSIV Bypasses are closed.

RD PZR PDRVs Closed (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6 Page 17 of 23 Event

Description:

LOCA when Reactor Trips.

Time Position Applicants Actions or Behavior RO PZR Spray & Aux Spray valves closed (YES)

RO At least one RCP running (NO)

BOP Any SIG with uncontrolled depressurization (NO)

BOP Any S/G Completely Depressurized (NO)

BOP R-19s, R-31s, R-15 rad levels normal (YES)

BOP R-2, R-32A, R-32B Rad Levels Normal (YES)

CV Pressure Normal (NO)

RO

. GO TO PATH-i Entry Point C RO Reset SPDS, initiate monitoring CSFSTs NOTE: Crew will transition to FRP-P.1 once recognized that RED condition exists on Integrity Critical Safety Function Status Tree Continuous Action Step Check CST Level Less than 10% (NO)

BOP If becomes less than 10% align Service Water to the suction of AFW Pumps_using OP-402.

Determine if RCS Cooldown is due to a Large Break LOCA (YES)

Check both of the following conditions exist:

RO RCS pressure is less than 275 psig [400 psig]. (YES)

AND RHR flow on Fl-605 Greater than 1200 GPM (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: I Scenario # 3 Event # 6 Page 18 of 23 Event

Description:

LOCA when Reactor Trips.

Time I Position Aoolicants Actions or Behavior RO Reset SPDS AND return to procedure and step in effect.

NOTE: Crew will transition back to PATH-I, Entry Point C.

Open Foldout B.

CREW (No actions needed from this Foldout.)

BOP Request Periodic Activity Samples of All S/Gs RO At Least One RCP Running (NO)

BOP Any SIG with Uncontrolled Depressurization (NO)

BOP Any SIG Completely Depressurized (NO)

Control AFW Flow to Maintain SIG Levels between 8% [18%] and BOP 50%

BOP Any SIG with Uncontrolled Level Increase (NO)

BOP R-19s, R-31s, AND R-15 Rad Levels Normal (YES)

RO PZR PORVs Closed (YES)

Open at least one PORV Block unless Closed to Isolate an Open PZR RO PORV Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6 Page 19 of 23 Event

Description:

LOCA when Reactor Trips.

Time I Position I Aoolicants Actions or Behavior Continuous Action Step RO IF PZR PORV Opens on High Pressure, THEN Verify Reclosure at or Below 2335 PS 1G. Close PORV Blocks as Necessary.

RO Reset SI Continuous Action Step CREW IFOffsite Power is Lost, THEN Restart Emergency Safeguard Equipment RO Reset CV Spray RO Reset Phase A AND Phase B Booth Operator Insert trip of A RHR Pump.

Establish Instrument Air to CV. IF Compressor Not Running, THEN RO Start Compressor.

Booth Operator Start A andlor B Instrument Air Compressor 3 minutes after the crew asks.

BOP Offsite Power Available to Charging Pumps (NO)

IF Adequate diesel capacity not available to run charging pumps BOP THEN shed non-essential loads using Supplement F.

RO At Least One Charging Pump Running (YES)

RO Establish Charging Flow as Necessary Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6 Page 20 of 23 Event

Description:

LOCA when Reactor Trips.

Time 1 Position L Applicants Actions or Behavior RO CV Spray Pumps Running (YES)

Continuous Action Step RO When CV Press decreases below 4 psig then stop CV Spray pumps and close Sl-880 valves RO RCS Subcooling Greater Than 35°F [55°F] (NO)

Continuous Action Step RO WHEN Below 1010 Amps THEN EnergIze Source Range detectors and monitor recorder.

RO RCS Pressure Greater Than 275 PSIG [400 PSIG] (NO)

BOP E-1 AND E-2 Energized by Offsite Power (NO)

BOP Attempt to restore offsite power to E-1 AND E-2 BOP Restart Battery Chargers within 30 mm of power loss using OP-601.

BOP Verify EDGs Properly Loaded (YES)

BOP Locally verify Air Side Seal Oil Backup Pump running. (YES)

IF Diesel Capacity is not adequate to run lnstr Air Compressors AND BOP Battery Chargers, THEN shed non-essential loads using Supplement F.

BOP Locally Load lnstr Air Compressors AND Battery Chargers BOP E-1 OR E-2 Energized by Offsite Power (NO)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6 Page 21 of 23 Event

Description:

LOCA when Reactor Trips.

Time Position Applicants Actions or Behavior Critical RO Supplement D components capable of recirc (NO)

Task NOTE Crew will transition to EPP-15, Loss of Emergency Coolant Recirculation Continuous Action Step Check Emergency Coolant Recirculation Capability Restored (NO)

RO If Emergency Coolant Recirculation is restored, THEN perform Step

2. Go to Step 3.

Foldout pages are not applicable during performance of this CREW procedure.

Continuous Action Step Check suction source to any of the following pumps LOST (NO)

RO SI Pumps, RHR Pumps, CV Spray Pumps If suction source lost to pump(s), THEN perform Step 5. Go to Step 6.

Check Emergency Recirculation Equipment AVAILABLE USING RO SUPPLEMENT D (NO)

RNO Try to restore at least one train while continuing with this RO procedure.

Verify the following CV RECIRC FANs RUNNING (YES)

RO HVH-1, HVH-2, HVH-3, HVH-4 Booth Operator Notify the Control Room that I&C personnel has corrected the problem with RHR Pump B breaker and can be started if needed.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6 Page 22 of 23 Event

Description:

LOCA when Reactor Trips.

Time 1 Position 1 Applicants Actions or Behavior RHR Pump B can be started. The crew should return to Step 2 of RO EPP-1 5 which will reset SPDS and return to procedure and step in effect.

The Chief Examiner may terminate the scenario at his discretion or once it has been identified that transition out of EPP-15 is allowed.

Appendix D NUREG1 021, Rev. 9, Supp. 1

ILC-11-1 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL: 1 E-8 amps Core Burnup: 150 MWD/MTU EFPD: 4.3 EFPD Boron: 1531 PPM Xenon: EQ Xenon Tavg: 548°F Bank 0 Rods 100 Steps EQUIPMENT UNDER CLEARANCE:

• A CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:

• Reactor is at 1 E-8 amps and the turbine is on the turning gear with GP-005 in effect.

• RCP C has an oil leak issue.

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

INSTRUCTIONS FOR THE WATCH:

• Maintain current reactor power until the RCP C oil leak issue is resolved.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Unit 2 Status Board IDate: iToday ITime:...... 6:00:00 AMjCycle: [27 IMWD/MT: [150 IDesian: [16590 IEFPD 4.3 IDesicin [473.5 I Tank [Level% Status HUT Level % Status Monitor A 10 Standby CVCS-A 20 Filling Monitor B 38 Standby CVCS-B [10 Standby WCTA 37 Standby CVCS-C 86 Standby Tf Standby WHUT #NAME? Filling WCT C Standby WCTD 10 Standby Data Linked to P1 WCT E 9 Standby WGDTS Pressure PSIG Status A #NAME? PSIG On cover DEMINERALIZERS

. Resin B #NAME? :I)S [In Service PPM In Service Date

[ Replaced C #NAME? [PSIG Isolated MB A 2194 [YES 7/17/2010 [514/2010 D #NAME? PSIG andby MB B 2265 -* NO 7/17J/29/201 CATION 1021 NO 9117 12/9/2009 Shutdown Requirement Temp Boron DEBA 0 NO New 2/3/2010 1.77% =L.KIK 547 F Hot 1051 DEBB 0 [NO 1.77% =LKiK jio 1281 SEP [1963 [NO [i2i122I2oi 2.6% zK1K 100 F Cold 1430 6%=AKIK [N/A [1950 SGBD Condenser Air Inleakage Target Value GPM [Status PORV Settings A 13 CFM A 50 Flash Tank Setting Date POT GP-3 Psig B 0 CEM B 50 With Heat A [7/18/2010:3.21 1000 Known [8 CFM C Recovery B 711812010 3.12 1040 Total 5 [CFM N2 Flow 8 SCFM C 711812010 3.44 1000 Effluent Radiation Monitor Setpoints Rad Current NUE Value RCS Leakage 0.00 Unidentified . Alert Value 200X 2X Monitor Setpoint Total 0.03 R-14C [1.o1E+o4 N/A [2.o2oE+o4 PRT 0.02 R-20 7.40E+03 N/A 1.480E+04 RCDT Leakage 0.01 GPM R-18 1.OOE+06 2.000E+08 .000E+06 Charging Leakoff 0 GPM R-19A 1.05E+04 2.IOOE+06 2.IOOE+04 R-19B 9.72E+03 1.944E+06 I .944E+04 Misc Identified 0 j GPM Primary/Secondary 0 R-1 9C 9.58E+03 1.91 6E+06 1.91 6E+04 Secondary Loss [17.3 [ GPM R-37 8.53E+03 1.706E+06 1.706E+04 Manually Entered Data Linked to Chem data base Hi Flux At Shutdown Boron PPM [ Date [PPM Date PPM Previous ARI Counts Setpoint RCS [Today [1531 Nl-31 :50 150 BAST-A 9/16/2010 21,535 #NAME? #NAME?

NI-32 [60 [180 BAST-B [9/16/2010 [21,032 #NAME? [#NAME?

SEP [9/15/2010 [.2246 #NAME? [#NAME?

Normal Currents RWST 9/16/2010 2219 #NAME? #NAME?

UPPER [LOWER [TARGET %BAND Accum-A 30/2010 2211 #NAME? #NAME?

Accum-B [8/30/2010 2206 #NAME? #NAME?

Accum-C 8/30/2010 2230 #NAME? #NAME?

RHR [7/6/2010 2221 Refuel Canal POWERTRAX Rev# 2.1.0 RNP 1% APL 112.55 Refuel Cavity SEP Canal FANS TestlHrs [Date/Tst HVE-IA/B 35640.6 3/8/10 Notes/Additional Data HVE.15A 18643.5 3/18110 IC-I, 2,40 HVE-19A/B 6928.3 :513110 BOL -

SR 3.7.11.2 Last Completed 15/27/2010 :19:45 I

I Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 4 Op Test No.:

Examiners: Operators: SRO -

RO BOP Initial Conditions:

• 75% RTP EOL, 15697 MWD/MTU, 132 ppm Boron.

• A COW pump inoperable with the breaker racked out

. 5 GPD primary to secondary leakage into S/G C

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

Turnover:

• Awaiting Engineering personnel to install vibration monitoring equipment to allow starting Heater Drain Pump A.

Critical Tasks:

• Manually runback the turbine to stop the steam flow

• Provide heat removal by RCS Bleed and Feed Event MaIf. Event Type* Event No. No. Description 1 (C) RO, BOP, SRO Loss of Instrument Bus #1 (TS) SRO 2 (l)RO,SRO PZR Pressure Controller PC-444J Range Shifts (TS) SRO 3 (I) BOP, SRO Steam Pressure Channel PT-485 fails LOW (TS) SRO 4 (C) BOP, SRO Loss of Cooling to the Auxiliary Transformer 5 (R)RO Load Reduction to 50%

(N) BOP, SRO 6 (M) ALL Feedwater Header Rupture 7 (C) BOP Turbine Trip Does Not Occur 8 (C) BOP MDAFW and SDAFW Pumps Trip when Start Signal Received 9 (C) BOP Steam Dump Valves fail Open on Reactor Trip 10 (C) BOP MSIV5 fail to Close when Demanded Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Scenario Outline Form ES-D-1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ILC-11-1 NRC SCENARIO 4

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 75% RTP and waiting on Engineering personnel to install vibration monitoring equipment on Heater Drain Pump A to support pump startup. The previous shift had identified seal leakage on CCW Pump A. The motor breaker has been racked out and the pump has been isolated and cleared for maintenance. 5 GPD primary to secondary leakage has been identified in SIG C with elevated readings on the applicable radiation monitors.

On cue from the Chief Examiner, Instrument Bus #1 will de-energize due to the tripping of the normal supply breaker on MCC-5. AOP-024, Loss of Instrument Bus, immediate actions will be taken by the crew and the procedure will proceed to energize the instrument bus from its alternate power supply. The crew will ensure that all of the controllers have been returned to auto. ITS 3.8.7, Condition A, One AC Instrument Bus power source inoperable Restore AC Instrument Bus Power Source to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and ITS 3.8.9 Condition B, One AC instrument bus subsystem inoperable Restore AC instrument bus subsystem to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, will be implemented by the SRO. Once AOP-024 and ITS actions are completed, the Chief Examiner can cue the next event.

PZR Pressure Controller PC-444J control range will shift causing the PZR Spray valves to open and lower PZR pressure. AOP-019, Malfunction of RCS Pressure Control, immediate actions will be taken and the procedure will take actions to restore pressure to the normal control band with PC-444J operated in manual control. ITS 3.4.1, Condition A, One or more RCS DNB parameters not within limits Restore RCS DNB parameters to within limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, will be entered due to PZR Pressure being less than 2205 psig. Once the Chief Examiner is satisfied with the crews actions, the Chief Examiner will cue the next event.

Steam Pressure Transmitter PT-485 will fail LOW, causing the controlling steam flow channel on S/G B to fail low and causing a transient on the Feedwater Regulating valve FCV-488. AOP 025, RTGB Instrument Failure, Section G immediate actions will be taken by the crew to stabilize the SIG level transient. The procedure will place an alternate control channel in service and direct the removal of the channel from service. ITS Table 3.3.1-1 Item 14 which requires 2 SIG Level channels (not affected by the failure) and 2 Steam Flow I Feedwater Flow mismatch channels with Condition E Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ITS Table 3.3.2-1 Items le, ig, and 4e for Safety Injection and Steam Line Isolation High Steam Line Flow with Low Tave or Low Steam Line Pressure Condition D: Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. ITS Table 3.3.3-1 Item 20 Post Accident Monitoring Instrumentation for Steam Generator pressure required channels is 2 per SIG which is currently met. ITS Table 3.3.6-1 Item 4 Safety Injection for Containment Ventilation Isolation Instrumentation refers to LCO 3.3.2 Functions l.a-f (which have already been addressed) requirements will be reviewed by the SRO to ensure that all of the ITS specs are satisfied. Once the SIG level control has been stabilized and the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event.

Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Scenario Outline Form ES-D-1 Auxiliary Transformer Trouble alarm (APP-009-C6) will be received on the RTGB. The report from the field is that all cooling fans and oil pumps on the transformer have been lost. AOP-037, Large Transformer Malfunctions, will be implemented by the crew with the requirement to reduce load to less than 50% within 30 minutes and unload the transformer. Power reduction will commence and will continue until the Chief Examiner cues the next event.

Feedwater header rupture will occur at the discharge of the Main Feedwater Pumps. This will cause an immediate reduction in the SIG levels and the crew will manually trip the reactor. Once the reactor is tripped, the crew will enter PATH-i.

The turbine will not trip automatically or manually from the RTGB and the operator will have to manually runback the turbine with the EH controls until the governor valves are closed.

Both MDAFW Pumps and the SDAFW Pump will trip when the start signal is received.

Steam dump valves will fail open on the trip and the MSIVs will fail to close when demanded from the RTGB control switches. If requested to locally fail close the MSIVs, the task will be successful to close the valves.

The crew will transition to FRP-H. 1, Response to Loss of Secondary Heat Sink, due to the inability to feed the SIGs. During the procedure, following the initiation of RCS bleed and feed through the PZR PORVs, one MDAFW Pump will be restored to allow feedwater flow to be initiated to the SIGs.

The Chief Examiner may terminate the scenario after the crew has restored AFW flow to at least one SIG.

Appendix D NUREG-i 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 ILC-I1-I NRC SCENARIO 4 SIMULATOR SETUP I C!SETU P:

• IC-804, SCN: 008_NRC_4

• A COW Pump inoperable with the breaker racked out

• 5 GPD primary to secondary leakage into SIG C

• R-15 at 24 cpm, R-19C at 232 cpm, R-31C at 0.450 mR/hr

• Status board updated to reflect 10-22.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 7: Turbine Trip does not occur Event 8: MDAFW and SDAFW Pumps Trip when Start Signal Received Event 9: Steam Dump Valves fail Open on Reactor Trip Event 10: MSIVs fail to Close when Demanded EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Loss of Instrument Bus #1 Event 2: PZR Pressure Controller PO-444J Range Shifts Event 3: Steam Pressure Channel PT-485 fails LOW Event 4: Loss of Cooling to the Auxiliary Transformer Event 5: Load Reduction to 50%

Event 6: Feedwater Header Rupture EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• AOP-024

• AOP-019

• AOP-025 Main Body and Section G

• OWP-025, SGP-8

• APP-046

• AOP-037

• PATH-I

• Foldout A

• FRP-HI Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 1 Page 5 of 40 Event

Description:

Loss of Instrument Bus #1 Time 0 Position Applicants Actions or Behavior BOOTH OPERATOR: When directed, insert Event 1, Loss of Instrument Bus #1 EVENT INDICATIONS:

Rack #1 Nuclear Instruments Lost (N-31, N-35, N-41)

Bistable Status Panel B Extinguished FR-478 Extinguished AOP-024 LOSS OF INSTRUMENT BUS BOP Immediate Action Step Place The Main Turbine in Manual Immediate Action Step BOP Verify SIG(s) Maintained At Program Level Immediate Action Step RO Place Rods in M (Manual)

SRO Enters AOP-024 and verifies Immediate Actions.

RO Maintain Reactor Power 100%

Continuous Action Step Determine if RCS Makeup needs to be stopped:

RO Check Auto Makeup, Boration OR Dilution In Progress (YES)

OR Check Instrument Bus 2 AND Instrument Bus 7 De-energized (NO)

RO Place the RCS Makeup System Switch to STOP.

Control PZR Heaters and Sprays to restore RCS Pressure to the RO desired control band.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 1 Page 6 of 40 Event

Description:

Loss of Instrument Bus #1 Time Position Applicants Actions or Behavior RO Control Charging and Letdown Flow to Maintain PZR Level.

RO Verify RCP Seal Injection Flow Between 6 GPM and 20 GPM.

CREW Make PA Announcement For Procedure Entry Determine Failed Instrument Bus (IB) From Any Of The Following:

. Available indications OR BOP

• Table Below Instrument Bus Indication to Check I FR-478, A S/G Level Continuous Action Step BOP Check Emergency Busses E-1 AND E-2 - ENERGIZED FROM THE 4160V BUSSES (YES)

Continuous Action Step RO/BOP Check Affected Instrument Bus Energized (NO)

RO Check CVC-460A & B, LTDN LINE STOP CLOSED (YES)

RO Place The Selector Switch For CVC-460A & B In The Closed Position RO Verify only ONE Charging Pump running at minimum speed RO Verify RCP Seal Injection Flow between 6 GPM and 20 GPM Appendix D NUREG-l 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # I Page 7 of 40 Event

Description:

Loss of Instrument Bus #1 Time ft Position (I Applicants Actions or Behavior Check Affected Instrument Bus ENERGIZED (NO)

Locally perform the applicable step below:

. lB-i through lB-4 BOP

• IF MCC-8 is supplying an Instrument Bus, THEN Go To Step

58. (NO)

• Transfer the affected Instrument Bus to the alternate (MCC-8) power supply.

Booth OpErator Transfer Instrument Bus I to Alternate Power Supply SRO Stop All Radioactive Batch Releases Check Status Of Local Actions:

BOP a. Check Local Actions Of Step 12 RNO REQUIRED (YES)

b. Check Local Actions Of Step 12 RNO ATTEMPTED (YES)

Continuous Action Step BOP Check Affected Instrument Bus ENERGIZED (YES)

Restore Affected Controllers On The RTGB To AUTO Mode RO/BOP (All Controllers go to Auto EXCEPT FC-605 which has no instrument air_aligned_to_it_normally)

Verify RCS Makeup Control IN AUTO

• Place the RCS MAKEUP SYSTEM Switch in STOP RO

• Verify the RCS MAKEUP MODE Switch in AUTO

• __Momentarily_place the_RCS_MAKEUP_SYSTEM_Switch_to_START Continuous Action Step Restore Rod Control To Automatic As Follows:

RO a. Check Power GREATER THAN 15%

b. Check Automatic Rod Control AVAILABLE

c. Check Tavg WITHIN -1.5 TO +1.5°F OF TREF d.__Place_the_Rod_Control_Selector_Switch_to_A_(Automatic)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 1 Page 8 of 40 Event

Description:

Loss of Instrument Bus #1 Time Position Applicants Actions or Behavior BOP Check Emergency Busses E-1 AND E-2 ENERGIZED (YES)

Check Emergency Busses E-1 AND E-2 - ENERGIZED FROM THEIR BOP 4160V BUSSES (YES)

SRO Implement The EALs Note Possible ITS LCO 3.4.9 entry for PZR Level greater than 63.3%.

Continuous Action Step Check Status Of Turbine:

BOP

. Check Instrument Bus 4 ENERGIZED (YES)

. Place Turbine Controls in Automatic RO Check CCW Pumps More than one running (NO)

BOP Check RMS-1, RMS-2, RMS-3 AND RMS-4 ALL OPEN (YES)

Continuous Action Step BOP Check Affected Instrument Bus ENERGIZED (YES)

RO Check PZR Heater Status DEENERGIZED (YES)

Reset PZR Heaters As Follows:

a. Place PZR HTR CONTROL GROUP Control Switch to OFF position AND return to ON position RO b. Place PZR HTR BACK-UP GROUP A Control Switch to OFF position AND return to AUTO OR ON position as desired

c. Place PZR HTR BACK-UP GROUP B Control Switch to OFF position_AND_return_to_AUTO_OR_ON_position_as_desired Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 1 Page 9 of 40 Event

Description:

Loss of instrument Bus #1 Time N Position I Applicants Actions or Behavior RO Check Normal Letdown ISOLATED (YES)

Restore Normal Letdown Using Attachment 15, Restoration of Normal RO Letdown.

NOTE: Th following are the steps to restore normal letdown using Attachment 15 of AOP-024 Normal charging flow through the Regenerative Heat Exchanger is in RO/BOP service.

RO/BOP A Phase A Containment Isolation signal is NOT present RO/BOP The Residual Heat Removal System is NOT in service.

VERIFY the following valves are CLOSED:

. CVC-204A, LETDOWN LINE ISO

. CVC-204B, LETDOWN LINE ISO

• LCV-460A, LTDN LINE STOP RO / BOP

• LCV-460B, LTDN LINE STOP

• CVC-200A, LETDOWN ORIFICE ISOLATION

• CVC-200B, LETDOWN ORIFICE ISOLATION

• CVC-200C, LETDOWN ORIFICE ISOLATION RO I BOP VERIFY FULL OPEN HIC-121, CHARGING FLOW (CR 95-01 752)

Check Pressurizer level is greater than OR equal to program level.

RO BOP (YES)

IF desired, THEN PLACE TCV-143, VCT/DEMIN. DIVERSION, in the RO I BOP VCT_position.

RO I BOP PLACE PC-145, PRESSURE, in MANUAL.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # I Page 10 of 40 Event

Description:

Loss of Instrument Bus #1 Time N Position 1 Applicants Actions or Behavior SET PC-I 45 to throttle PCV-145 to 45% to 55% open to ensure the RO/BOP Letdown line is NOT overpressurized.

RO/BOP OPEN CVC-204A, LETDOWN LINE ISO.

RO/BOP OPEN CVC-204B, LETDOWN LINE ISO.

PERFORM the following:

. OPEN LCV-460A&B by placing switch CVC-460A&B LTDN RO/BOP LINE STOP to OPEN.

. PLACE LTDN LINE STOP CVC-460 A&B switch to AUTO.

PLACE TC-144, NON-REGEN HX OUTLET TEMP, in MANUAL AND RO I BOP adjust as necessary to ensure Letdown temperature does NOT increase above 127°F when letdown is reestablished.

While MAINTAINING Charging Pump discharge pressure as indicated on RTGB instrument P1-121 LESS THAN 2500 psig, ADJUST RO BOP charging pump speed to the expected letdown flow to be established in_the_next_step.

OPEN one LTDN ORIFICE valve.

RO I BO CVC-200A, CVC-200B or CVC-200C PLACE PC-i 45 in AUTO AND CHECK letdown pressure as indicated RO I BOP on P1-145, LOW PRESS LTDN PRESS, is being maintained between 300 psig_and_320_psig.

RO I BOP PLACE TC-144, NON-REGEN HX OUTLET TEMP, in AUTO IF TCV-143 was selected to the VCT, THEN Position TCV-143 as RO BOP directed by the CRS/SM.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # I Page 11 of 40 Event

Description:

Loss of Instrument Bus #1 Time I Position I Applicants Actions or Behavior IF Charging flow is changed, THEN establish RCP Seal Injection Flow between 8 GPM and 13 GPM by throttling the following RO/BOP . CVC-297A, RCP A SEAL WATER FLOW CONTROL VALVE

. CVC-297B, RCP B SEAL WATER FLOW CONTROL VALVE

. CVC-297C, RCP C SEAL WATER FLOW CONTROL VALVE IF increased letdown flow is desired, THEN place additional letdown orifices in service as follows:

. Verify HIC-121, Charging Flow is Full Open.

. Verify Charging Pump discharge pressure as indicated on RTGB instrument P1-121 less than 2500 psig.

. IF required, THEN start the second Charging Pump on MINIMUM SPEED.

. IF required, THEN while maintaining Charging Pump discharge pressure as indicated on RTGB instrument P1-121 LESS THAN 2500 psig, ADJUST charging pump speed to meet flow RO / BOP requirement.

. Place PC-I 45, PRESSURE, in MANUAL

. Slowly Throttle Open PC-145 to achieve 180-200 psig on P1 145 to ensure the Letdown Line is NOT overpressurized.

. OPEN one additional LTDN ORIFICE valve.

. Place PC-145 in AUTO and Check letdown pressure as indicated on P1-145, LOW PRESS LTDN PRESS, is being maintained between 300 psig and 320 psig.

. Verify Seal Injection Flow between 8 GPM and 13 GPM by throttling the following_CVC-297A,_B, C.

NOTE: Decision on additional letdown flow may be dependent on PZR Level. PZR Level at> 63.3% is ITS LCO 3.4.9, Condition A.

Notify RC that letdown flow has been restored and the affected areas RO BOP should be monitored for changing radiological conditions.

BOP Check All Radiation Monitor Alarms - EXTINGUISHED (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 1 Page 12 of 40 Event

Description:

Loss of Instrument Bus #1 Time Position Aoplicants Actions or Behavior Check R-1 I OR R-12 IN SERVICE (YES)

BOP RMS-l,2,3,4OPEN (YES)

R-1 I and R-12 Vacuum Pump Operating (YES)

Check Control Room Ventilation ALIGNED FOR PRESSURIZATION BOP MODE (NO)

GoToStep4l.

Check PZR PRV Safety Acoustic Monitor Lights ILLUMINATED -

RO (YES)

Locally Reset PZR Safety Acoustic Monitors At INSTRUMENT CABINET A In The Computer Room By Performing The Following:

BOP

• Depress RESET RC-551A Pushbutton.

• Depress RESET RC-551 B Pushbutton.

• DeiDress RESET RC-551C Pushbutton.

Booth Operator Reset PZR Safety Valve Acoustic Monitors NOTE: The crew may choose to unsaturate PZR Pressure Controller PC-444J.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 1 Page 13 of 40 Event

Description:

Loss of Instrument Bus #1 Time 0 Position fi Applicants Actions or Behavior Continuous Action Step Check Instrument Busses 1, 2, 3, AND 4- ENERGIZED FROM THEIR NORMAL SOURCE (As Indicated Below):

• lB-I: MCC-5 (Via E-1) (On Alternate)

• IB-2: INVERTERA

• IB-3: INVERTERB

• IB-4: MCC-6 WHEN the Instrument Bus normal source becomes available, THEN transfer the affected Instrument Bus back to its normal supply using BOP the appropriate attachment below:

Bus Attachment lB-I Attachment 9 I B-2 Attachment 10 I B-3 Attachment 1 1 I B-4 Attachment 12

• Restore the Instrument Bus to the normal power supply within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• IF the normal power supply can NOT be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, THEN_be_in_Mode_3_within_6_hours_AND_Mode_5_within_36_hours.

Check Status of EDGs START SIGNAL RECEIVED (NO)

BOP

• Observe the NOTE prior to Step 63 and Go To Step 63.

BOP Check ALL Safety Related Electrical Buses ENERGIZED (YES)

Check Technical Specifications For Applicable LCOs

• ITS LCD 3.8.1, AC Sources Operating (None)

• ITS 3.8.7, Condition A, One AC Instrument Bus power source inoperable Restore AC Instrument Bus Power Source to SRO operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

• ITS 3.8.9 Condition B, One AC instrument bus subsystem inoperable Restore AC instrument bus subsystem to operable status_within_2_hours Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 1 Page 14 of 40 Event

Description:

Loss of Instrument Bus #1 Time I Position Aoolicants Actions or Behavior Check Annunciator APP-005-A3, PR DROP ROD ILLUMINATED -

RO (YES)

Reset Dropped Rod Alarm By Momentarily Placing DROPPED ROD RO MODE Selector Switch For The Affected Power Range Drawer To RESET Position and then back to NORMAL (N-41 Only)

BOP Check APP-006-F5, Steam Dump Armed - Illuminated (NO)

RO Check APP-005-F5, AMSAC TROUB/BYP- Illuminated (YES)

Reset AMSAC TROUB/BYP Alarm by depressing the System Reset RO Pushbutton on AMSAC Front Panel. (Key 52 is required.)

Booth Operator Reset AMSAC Trouble Alarm.

SRO Return to Procedure and Step in Effect.

Appendix D NUREG-1 021, Rev. 9, Supp. I

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 2 Page 15 of 40 Event

Description:

PZR Pressure Controller PC-444J Range Shifts Time Position 1 Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 2, PC-444J Range Shifts EVENT INDICATIONS:

PZR Spray Valves open at pressure lower than normal.

PZR Pressure lowering.

APP-003-D8, PZR Control HIILO Pressure AOP-019 MALFUNCTION OF RCS PRESSURE CONTROL Immediate Action Step RO Determine If PZR PORVs Should Be Closed:

. Check PZR pressure LESS THAN 2335 PSIG (YES)

. Verify Both PZR PORVs CLOSED (YES)

Immediate Action Step RO Control The PZR SPRAY VALVES AND PZR Heaters To Restore RCS Pressure To The Desired Control Band

. Place PC-444J in Manual to Control Pressure Crew Make PA Announcement for Procedure Entry Continuous Action Step RO Check PZR Pressure UNDER OPERATOR CONTROL (YES)

Continuous Action Step RO Check Pressurizer Pressure Transmitter PT-444 OR PT-445 Failed.

(NO Check PC-444J, PZR PRESS OPERATING PROPERLY IN AUTO (NO)

RO

. Place PC-444J in Manual.

. IF PC-444J is operable in manual, THEN go to Step 9. (YES)

RO Check PZR SPRAY VALVE Controllers In Auto (YES)

RO Check PZR Heaters In Normal Conficwration (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 2 Page 16 of 40 Event

Description:

PZR Pressure Controller PC-444J Range Shifts Time N Position 1 Applicants Actions or Behavior RO Manually adjust PC-444J to maintain PZR pressure.

RO Check PZR pressure Under control (YES)

SRO Go to step 29 SRO Implement the EALs SRO Contact I&C to make repairs to the PZR Pressure Control System Refer To ITS For Applicable LCOs

. LCO3.4.11, PZRPORV

. TRM 3.4, PZR Spray AT

. LCO 3.4.4 AND 3.4.5, RCS Loops SRO

• ITS 3.4.1, Condition A, One or more RCS DNB parameters not within limits Restore RCS DNB parameters to within limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, will be entered due to PZR Pressure being less than 2205 psig

• LCO 3.4.9, PZR Level SRO Return To Procedure And Step In Effect Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 3 Page 17 of 40 Event

Description:

Steam Pressure Transmitter PT-485 fails LOW Time I Position 1 Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 3, Steam Pressure Transmitter PT-485 fails LOW EVENT INDICATIONS:

APP-006-A4 Steam Line High iP APP-006-B1 SIG B FW>STM Flow APP-006-B2 SIG B STM>FW Flow (When bistables are tripped.)

APP-006-B3 SIG B Level Dev APP-006-E3 SIG B Wide Range HiILo Level APP-006-E5 Steam Line Low Pressure FR-488, Pen #1 Lowering and Pen #3 Lowering AOP-025 RTGB INSTRUMENT FAILURE SRO Go To The Appropriate Section For The Failed Transmitter:

SIG Steam Pressure Section G Page 21 SECTION G SIG Steam Pressure Transmitter Failure Immediate Action Step Place The Affected FRV In MAN BOP FCV-478 (FRV A) (NO)

FCV-488 (FRV B) (YES)

FCV-498 (FRV C) (NO)

Immediate Action Step BOP Restore Affected S/G Level To Between 39% And 52%

RO Make PA Announcement For Procedure Entry Place The Affected S/G Steam Flow Selector Switch To The Alternate Channel Below:

BOP Selected Position Failed Channel Affected Channel PT-485 FI-484 CH_485 Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 3 Page 18 of 40 Event

Description:

Steam Pressure Transmitter PT-485 fails LOW Time I Position 1 Aoolicants Actions or Behavior Continuous Action Step Restore Affected Controller To Automatic As Follows:

BOP a. Check S/G level WITHIN +/-1% OF PROGRAMMED LEVEL b Place the affected Controller in AUTO Remove The Affected Transmitter From Service Using OWP-025:

BOP I Channel I OWP I PT-485 I SGP-8 OWP-025 SGP-8 STEAM GENERATOR PRESSURE Main Steam Line B Pressure Transmitter PT-485 BOP FR-488 (STM) Selected To 485 BOP DELETE INPUT PT-485 FROM CALO PROCESSING (MSPO421A)

Trip the Bistables for PT-485 BOP (END OWP-025)

Booth Operator Trip the bistables for PT-485 in accordance with OWP-025, SGP-8, after the operator requests and report completed actions SRO Implement The EALs Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 3 Page 19 of 40 Event

Description:

Steam Pressure Transmitter PT-485 fails LOW Time Position I Applicants Actions or Behavior Check Technical Specifications (ITS) For Applicable LCOs

. ITS Table 3.3.1-1 Item 14 which requires 2 SIG Level channels (not affected by the failure) and 2 Steam Flow I Feedwater Flow mismatch channels with Condition E Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

. ITS Table 3.3.2-1 Items le, ig, and 4e for Safety Injection and Steam Line Isolation High Steam Line Flow with Low Tave or Low Steam Line Pressure Condition D: Place channel in trip within 6 SRO hours OR Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

. ITS Table 3.3.3-1 Item 20 Post Accident Monitoring Instrumentation for Steam Generator pressure required channels is 2 per SIG which is currently met.

. ITS Table 3.3.6-1 Item 4 Safety Injection for Containment Ventilation Isolation Instrumentation refers to LCO 3.3.2 Functions 1 .a-f (which have already been addressed)

SRO Return To Procedure And Step In Effect Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 4 and 5 Page 20 of 40 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.

Time 1 Position Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 4, Loss of Cooling to the Auxiliary Transformer.

EVENT INDICATIONS:

APP-009-C6 AUX TRANSF TROUBLE Crew Make PA Announcement for Procedure Entry SRO Go to Section B for Auxiliary Transformer Dispatch an Operator to the Auxiliary Transformer to determine BOP the alarming function, acknowledge the alarm and attempt to reset the alarm.

BOP Check Alarm Function Remains Illuminated. (YES)

NOTE: The APP-046 alarms in the table below are prioritized by SRO importance.

Observe the NOTE CAUTION prior to the step and go to the SRO appropriate step based on the listed alarm function that is illuminated.

Alarm 46-11, Loss of Normal 48OVac Power Source (18G) (Step BOP 4)

Caution: JE the Auxiliary Transformer is operated for more than SRO 30 minutes with no fans or pumps, THEN damage to the Transformer could occur.

Dispatch an Operator to Observe the Status of the Fans and BOP Pumps Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 4 and 5 Page 21 of 40 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.

Time 1 Position I Applicants Actions or Behavior NOTE: IF APP-046-11 orAPP-046-12 are valid alarms, THEN SRO there will be no fans OR pumps running and APP-046-3, APP 046-4, APP-046-7, and APP-46-8 will also be illuminated.

BOP Check Status of the Fans and Pumps ALL LOST (YES)

Check Status of 480 Volt Bus 3 POWER LOST (NO)

BOP Go to Step 11 Check Status of MCC-4 POWER LOST (NO)

BOP Go to Step 17 BOP Check Status of MCC-4, Breaker 4BR TRIPPED (YES)

Attempt to Reset and Close MCC-4, Breaker 4BR One Time.

BOP (YES)

BOP Check Status of MCC-4, Breaker 4BR Closed (NO)

SRO Initiate action to repair problem causing the tripped breaker.

IF breaker MCC-4 (4BR) can NOT be reclosed promptly, THEN SRO qo to Step 28.

Continuous Action Step Determine If Trip Required As Follows:

BOP

- Check time elapsed since loss of all cooling Greater than 30 mm. (NO)

IF the Auxiliary Transformer is NOT unloaded within 30 minutes, SRO THEN perform Step 28.b.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 4 and 5 Page 22 of 40 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.

Time Position Aoolicants Actions or Behavior SRO Observe the Caution prior to Step 29 and Go to Step 29.

Reduce power to less than 50% using Attachment 4, Turbine Crew Load Reduction Check ANY of the following Diesel Generators Paralleled to the Grid BOP - EDG A (NO)

- EDG B (NO)

- DS Diesel (NO)

RO Check Power Less than 50% (NO) (Go to Power Reduction.)

NOTE: 1 Fhe crew is currently in a loop until power is less than 50% RTP nd the Auxiliary Transformer Unloaded. The following steps are ror the Power Reduction.

BOP/SRO Notify Load Dispatcher of Load Decrease to less than 50% power.

BOP Check Turbine Control Mode Automatic (YES)

BOP Depress the IMP IN Pushbutton BOP Set the Desired Load in the SETTER BOP Set the Desired Load Rate BOP/RO Depress the GO Pushbutton Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 4 and 5 Page 23 of 40 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.

Time 1 Position Applicants Actions or Behavior NOTE: OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, as it will be needed for the rapid downpower.

DETERMINE the amount of Boric Acid to add to the RCS and RO OBTAIN an independent check of the volume required.

NOTE: -100 gallons of Boric Acid. (The crew will add Boric Acid in 2-4 batches.) (Values based on 3%!min.)

RO OBTAIN permission from the CRSS OR the SSO to borate.

RO PLACE the RCS MAKEUP MODE selector switch to BORATE.

RO SET YIC-1 13, BORIC ACID TOTALIZER to desired quantity IF desired, THEN PLACE FCV.-113A, BORIC ACID FLOW, in MAN RO AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.

IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RO

• Rod Motion is blocked or in the wrong direction

• TAVG increases

• Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following

• FCV-1 13A, BORIC ACID FLOW, closes.

RO

• FCV-1 13B, BLENDED MU TO CHG SUCT, closes.

• IF in Auto, THEN the operating Boric Acid Pump stops.

• __The_RCS_MAKEUP_SYSTEM_is_OFF.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 4 and 5 Page 24 of 40 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.

Time I Position I Aoolicants Actions or Behavior IF desired, THEN FLUSH the Boric Acid flow path as follows:

. PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.

. SET YIC-1 14, PRIMARY WTR TOTALIZER to 1 5-20 gallons.

. PLACE FCV-1 14B, BLENDED MU TO VCT to CLOSE.

. Momentarily PLACE RCS MAKEUP SYSTEM switch to START.

. IF any of the below conditions occur, THEN momentarily place RO the RCS MAKEUP SYSTEM switch in the STOP position.

o Unanticipated Rod Motion o Primary Water addition reaches the desired value

. WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

o FCV-ll4Acloses.

o FCV-113B closes.

o IF in Auto, THEN the operating Primary Water Pump stops.

o The RCS MAKEUP SYSTEM is OFF.

RETURN the RCS Makeup System to automatic as follows:

. VERIFY FCV-1 14A is in AUTO.

. PLACE FCV-1 14B to the AUTO position.

RO . PLACE the RCS MAKEUP MODE switch in AUTO.

. VERIFY FCV-1 13A is in AUTO.

. Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO TOTALIZER, YIC-114 AND Boric Acid TOTALIZER, YIC-113 the total amount of Primary Water AND Boric Acid added during the boration.

MONITOR parameters tor the expected change in reactivity ANU RO inform the CRSS OR the SSO of the results of the boration.

NOTE: End of Boration and Power Reduction Steps. AOP-037 steps continue below.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 4 and 5 Page 25 of 40 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.

Time 0 Position Applicants Actions or Behavior Stop the following components:

1. Circulating Water Pump A BOP 2. Feedwater Pump A

3. Heater Drain Pump A

4. Condensate Pump B Transfer loads from the Auxiliary Transformer to the Startup BOP Transformer with the Unit at greater than 1 10 Mwe using Attachment

5. Transfer of Electrical Loads to the Startup Transformer.

.L NOTE: The following steps are from Attachment 5, Transfer of Electrical Loads to the Startup Transformer.

BOP Notify the Load Dispatcher of the 4KV switching evolution Insert key into Startup Transf synchroscope switch AND turn switch to BOP STARTUP BUS 2 position WHEN the synchroscope come up to the 12 oclock position, THEN BOP close START-UP TO 4KV BUS 2 BKR 52/12 WHEN breaker 52/12 indicates closed, THEN return switch to the mid-BOP position AND verify UNIT AUX TO 4KV BUS 1 BKR 52/7 has opened.

Insert key into 4KV TIES synchroscope switch AND turn switch to BUS BOP 3 & 4 position.

WHEN synchroscope comes up to 12 oclock position, THEN close BOP 4KV BUS 3-4 TIE BKR 52/19.

WHEN breaker 52/19 indicates closed, THEN return switch to the mid BOP position AND verify UNIT AUX TO 4KV BUS 4 BKER 52/20 opened.

BOP Turn synchroscope key switch to mid position.

BOP Check Auxiliary Transformer Unloaded (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 4 and 5 Page 26 of 40 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.

Time Position Applicants Actions or Behavior Check Auxiliary Transformer Alarm Status as Follows:

BOP a. Press and release the Reset pushbutton.

b. Check all APP-046 Alarms extinguished. (NO)

IF APP-046 Alarms are present than have not been addressed, THEN SRO go to Step 3.

SRO Implement the EAL5.

Check Technical Specifications for Applicable Action Statements.

3.8.1 AC Sources Operating 3.8.2 AC Sources Shutdown SRO 3.8.9 Distribution Systems Operating 3.8.10 Distribution Systems Shutdown SRO Check Status of Condition Causing Alarm Corrected (NO)

BOOTH OPERATOR: As soon as the power reduction is> 5% or at the discretion of the Chief Examiner, insert the next event.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 27 of 40 Event

Description:

Feedwater Header Rupture Time Position L Applicants Actions or Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 6, Feedwater Header Rupture EVENT INDICATIONS:

All SIG Levels lowering.

All FRVs go to full open.

FW Flow towering APP-006-A3 SIG A LVL 0EV APP-006-B3 SIG B LVL DEV APP-006-C3 SIG C LVL 0EV APP-007-D5 FW HDR LO PRESS Operators note the lowering SIG Levels and FRVs full open and RO/BOP recommend tripping the Reactor.

Immediate Action Step:

RO Reactor Tripped. (YES)

Immediate Action Step:

Critical BOP Turbine Tripped.(NO)

Task Trip or Runback the Turbine. (YES, Runback was successful)

Booth Operator: Manually trip the Turbine locally, if requested, after a 3 mm time delay.

Immediate Action Step:

BOP E-1 AND E-2 energized. (YES)

Immediate Action Step:

RO SI Initiated. (YES)

SRO Enters PATH-i and verifies Immediate Actions.

CREW Open Foldout A.

AppendixD NUREG-i021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 28 of 40 Event

Description:

Feedwater Header Rupture Time Position Applicants Actions or Behavior RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO)

RO o SI Pumps AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE o RCS Subcooling - < 35 degrees F [55 degrees F]

. MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does not BOP indicate fully closed, THEN place the associated RTGB Switch to CLOSE.

Faulted SIG isolation criteria.

H both the following conditions are met, THEN perform the following:

. Any SIG pressure is decreasing in an uncontrolled manner (YES)

BOP OR

. Any SIG has completely depressurized.(NO)

AND

. At least ONE SIG is intact. (NO)

NOTE: Operators may identify that steam dumps valves have failed open and cannot be closed and attempt to close the MSIVs. The MSIVs will fail to close from the RTGB.

Booth Operator: If requested to locally close the MSIVs, the task will be successful to close the valves.

RO Verify Phase A Isolation valves are closed. (YES)

BOP Verify FW Isolation valves are closed. (YES)

BOP Verify both FW pumps are tripped. (YES)

Verify both MDAFW pumps are running. (NO) (Unable to start from BOP RTGB.)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ESD-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 29 of 40 Event

Description:

Feedwater Header Rupture Time Position Applicants Actions or Behavior If additional Feedwater is required, start the SDAFW pump. (NO, BOP Pump started but tripped)

RO Verify 2 SI pumps running. (YES)

RO Verify Both RHR pumps running. (YES)

RO Verify SI valves are properly aligned. (YES)

RO At least 1 cow pump is running. (YES)

BOP All sw and SW Booster pumps running. (YES)

RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)

RO Verify IVSW System Initiated. (YES)

RO Verify CV Ventilation isolation. (YES)

BOP Verify Control Room Vent aligned for Pressurization Mode. (YES)

BOP Verify both EDGs running. (YES)

CONTINUOUS ACTION STEP BOP Restart battery chargers within 30 minutes of power loss using OP 601.

CONTINUOUS ACTION STEP:

RO CV Pressure has remained below 10 psig. (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 30 of 40 Event

Description:

Feedwater Header Rupture Time Position Applicants Actions or Behavior RO Automatic Steam Line Isolation Initiated (NO)

RO Automatic Steam Line Isolation Required (NO)

Locally open breaker for HVS-1 at MCC-5 CMPT 7J within 60 mm of SRO Shutdown.

Booth Operator Open the breaker for HVS-1 within approximately 3 minutes of request.

RO RCS pressure> 1350 psig. [1250 psig] (YES)

BOP At least 300 GPM AFW flow available. (NO)

BOP Level in at least one SIG greater than 8% [18%] (NO)

BOP Align AFW valves.

BOP At least 300 GPM AFW flow verified (NO)

Reset SPDS and Initiate monitoring of Critical Safety Function Status RO Trees Transition to FRP-H.1, RESPONSE TO LOSS OF SECONDARY SRO HEAT SINK.

Check Total Feed Flow less than 300 GPM due to operator action.

BOP (NO)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 31 of 40 Event

Description:

Feedwater Header Rupture Time Position I Applicants Actions or Behavior Determine if Secondary Heat Sink is required:

• Check RCS pressure greater than any non-faulted SIG RO pressure. (YES)

. Check RCS temperature greater than 350°F [310°F] (YES)

Continuous Action Step BOP Check Any TWO S/G Wide Range Levels less than 10% [19%] (YES)

RO Stop All RCPs SRO Observe CAUTION prior to Step 31 and Go to Step 31.

Steps 31 through 35 must be performed quickly in order to establish SRO RCS heat removal by RCS bleed and feed.

RO Depress the Initiate Safety Injection Pushbutton RO Verify SI Pumps At least one running (YES)

At the RTGB, verify SI Valves for at least one flow path ALIGNED RO FOR COLD LEG INJECTION (YES)

Verify APP-002-F7, INSTR AIR HDR LO PRESS EXTINGUISHED RO (YES)

Place IA PCV-1716, INSTRUMENT AIR ISO TO CV Control Switch to RO the OVERRIDE position.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 32 of 40 Event

Description:

Feedwater Header Rupture Time Position Applicants Actions or Behavior Establish RCS Bleed Path as follows:

. Verify power to PZR PORV Block Valves Available (YES)

RO

• Place all PZR Heater Control Switches to the OFF position.

. Verify PZR PORV Block Valves BOTH OPEN (YES)

• Open both PZR PORVs Verify Adequate RCS Bleed Path as Follows:

Critical RO

• PZR PORVs BOTH OPEN (YES)

Task

• PZR PORV Block Valves BOTH OPEN (YES)

RO/BOP Verify Auto Start of All SI Equipment Using Supplement L. (YES)

NOTE Supplement L steps included at the end of the scenario starting on Page 34 Maintain RCS Heat Removal As Follows:

RO Maintain Safety Injection Flow (YES)

Maintain PZR PORVs BOTH OPEN (YES)

RO Reset Safety Injection Momentarily place the Containment Spray Key Switch to the RO OVRD/RESET position and return to the NORMAL position.

RO Reset Phase A and Phase B RO Check Status of PCV-1716 IN OVERRIDE POSITION (YES)

Momentarily place IA PCV-1716 Switch to RESET return to RO AUTO.

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 33 of 40 Event

Description:

Feedwater Header Rupture Time Position I Applicants Actions or Behavior BOP Check E-l OR E-2 Energized by EDG (NO)

RO Check Charging Pumps All Stopped. (NO)

Align Charging Pump Suction to RWST as follows:

. Verify LCV-1 I 5B OPEN (YES)

. Verify LCV-1 150 CLOSED (YES)

RO

. Start all available Charging Pumps

• Increase running Charging Pumps speed to maximum

. Verify maximum charging flow on Fl-I 22A. (YES)

Continuous Action Step RO Check RWST Level LESS THAN 27% (NO)

Continuous Action Step RO Check CV Pressure HAS INCREASED TO GREATER THAN 10 PSIG (NO)

Continuous Action Step RO Check CV Pressure LESS THAN 4 PSIG (YES)

RO Stop the operating CV Spray Pump (None running)

Verify CV SPRAY PUMP DISCH Valves CLOSED RO (Sl-880A,B,C,D) (YES)

Verify Spray Additive Tank Discharge Valves CLOSED RO (Sl-845A,B) (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 34 of 40 Event

Description:

Feedwater Header Rupture Time Position Applicants Actions or Behavior Continuous Action Step BOP Check CST level Greater Than 10% (YES)

BOP Check AFW Lines INTACT (YES)

BOP Check AFW Pump Breakers Tripped (YES)

Position the MDAFW Pump Control Switch to the STOP position and BOP to the START position BOP Check MDAFW Pump RUNNING (NO)

Attempt to Start SDAFW Pump:

. Verify STEAM DRIVEN AFW PUMP STM SHUTOFF VALVES OPEN. (V1-8A, V1-8B, V1-8C) (YES)

BOP

• Verify STEAM DRIVEN AFW PUMP DISCH Valves OPEN (V2-14A, V2-14B, V2-14C) (YES)

• Check AFW flow to S/Gs Greater Than 300 GPM (NO)

Locally Investigate AND Attempt To Restore AFW Flow:

BOP

• Verify AFW Pump suction supply is available. (YES)

• Position MDAFW Pump LOCAL/REMOTE Switch to LOCAL.

Attempt to reclose any tripped breakers:

• Depress the MDAFW Pump local STOP pushbutton.

BOP

• Depress the MDAFW Pump local START pushbutton.

• Check MDAFW Pump started. (YES)

BOP Check AFW flow to S/Gs GREATER THAN 300 GPM. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 35 of 40 Event

Description:

Feedwater Header Rupture L Time 1 Position Applicants Actions or Behavior BOP Check Level in at least One SIG Greater than 8% [18%] (NO)

Continuous Action Step BOP Check CST level Greater Than 10% (YES)

BOP Check AFW Lines INTACT (YES)

BOP Check AFW Pump Breakers Tripped (YES) (B MDAFW Tripped.)

BOP Attempt to reclose breaker on B MDAFW Pump (NO)

BOP Check MDAFW Pump RUNNING (NO)

Verify AFW HDR DISCH Valves OPEN BOP (V2-1 6A,B,C) (YES)

BOP Check AFW flow to S/Gs GREATER THAN 300 GPM. (YES)

The Chief Examiner may terminate the scenario anytime after AFW flow has been established to at least one SIG.

NOTE The following are Supplement L steps RO / BOP Verify Containment Isolation Phase A Valves Closed (YES)

Verify Excess Letdown Isolated RO I BOP

• CVC-387, Excess LTDN Stop Closed (YES)

• HIC-1 37, Excess LTDN FLOW Controller at 0% (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 36 of 40 Event

Description:

Feedwater Header Rupture Time Position 1 Applicants Actions or Behavior Verify FW Isolation Valves CLOSED (YES)

. FRVs

. FRV Bypass Valves RO/BOP

. V2-6A, FW HDR SECTION

. V2-6B, FW HDR SECTION

. V2-6C, FW HDR SECTION RO I BOP Verify Both FW Pumps TRIPPED (YES)

RO / BOP Check Both MDAFW Pumps RUNNING (NO)

RO I BOP Start SDAFW Pump (NO Pump tripped.)

RO I BOP Verify Two SI Pumps RUNNING (YES)

RO I BOP Verify Both RHR Pumps RUNNING (YES)

RO I BOP Verify SAFETY INJECTION Valves PROPERLY ALIGNED (YES)

RO I BOP Check CCW Pumps AT LEAST ONE RUNNING (YES)

RO / BOP Verify ALL SW Pumps RUNNING (YES)

RO / BOP Verify BOTH SW Booster Pumps RUNNING (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 37 of 40 Event

Description:

Feedwater Header Rupture Time I Position Applicants Actions or Behavior Verify CV RECIRC FANS RUNNING (YES)

. HVH-1 RO/BOP

• HVH-2

. HVH-3

• HVH-4 Verify IVSW System INITIATED (YES)

RO I BOP

• IVSWS VA PCV-1 922A

• IVSWS VA PCV-1922B Verify CONTAINMENT VENTILATION ISOLATION INITIATED RO I BOP (YES)

Verify Control Room Ventilation System Has Shifted To Emergency Pressurization Mode As Follows:

a. CONT RM AIR EXHAUST Fan, HVE-16 STOPPED (YES)

RO I BOP b. CLEANING Fan HVE-19A OR B RUNNING (YES)

c. CONTROL ROOM AIR EXHAUST FAN DICHARGE DAMPER, CR D1A-SA CLOSED (YES)

d. CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-DIB-SB CLOSED (YES)

RO I BOP Verify Both EDGs RUNNING (YES)

RD I BOP Check CV Pressure EXCEEDED 10 PSIG (NO)

RD I BOP Check Steam Line Isolation INITIATED (NO)

RD / BDP IF Steam Line Isolation required (YES), then perform step 24.

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 6 Page 38 of 40 Event

Description:

Feedwater Header Rupture Time Position Applicants Actions or Behavior Verify All MSIVs AND MSIV BYPs IN CLOSED POSITION (NO) (If RO / BOP only attempted from RTGB).

MSIVs and MSIV Bypasses can be closed locally, if requested.

At MCC-5, open breaker AUX BUILDING SUPPLY FAN, HVS-1 RO / BOP (CMPT 7 J)

Check SW Header Pressure AND Transition To Steps Indicated By The Table Below:

SW PRESStRE CONIi J rrro\ ST1P RO I BOP LESS THAN 4() PS IC 27 GREATER THAN 50 PSIG 28 BETWEEN 40 PSTG AND 0 PSTG 29 RD I BOP Check number of SW Pumps Running Greater than 2 (YES)

RO/BOP Reset SI RD I BOP Stop 1 SW Pump RO I BOP Check SW Header Pressure GREATER THAN 50 PSIG (YES)

RD / BOP Check number of SW Pumps Running Greater than 2 (YES)

RD / BOP Reset SI Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: I Scenario # 4 Event # 6 Page 39 of 40 Event

Description:

Feedwater Header Rupture Time Position Appicants Actions or Behavior RO/BOP Stop 1 SWPump RO I BOP Check SW Header Pressure GREATER THAN 50 PSIG (NO)

RO I BOP Check SW Header pressure GREATER THAN 40 PSIG (YES)

NOTE End of Supplement L steps Appendix D NUREG1 021, Rev. 9, Supp. 1

ILC-11-1 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL: 75% EOL Core Burnup: 15697 MWD/MTU EFPD: 448 EFPD Boron: 132 PPM Xenon: EQ Xenon Tavg: 567.5°F Bank D Rods 169 Steps EQUIPMENT UNDER CLEARANCE:

• A CCW Pump DOS and Breaker Racked Out EQUIPMENT STATUS:

• 5 GPD primary to secondary leakage into SIG C

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

INSTRUCTIONS FOR THE WATCH:

• Awaiting Engineering personnel to install vibration monitoring equipment to allow starting Heater Drain Pump A.

AppendixD NUREG-1021, Rev. 9, Supp. I

Unit 2 Status Board

[Date: TodayITime: IMWDIMT: 15697 IDesign: 16590 IEFPD 448 IDesicin 473.5 I Tank Level % Status HUT *Level % Status MonitorA 10 Standby CVCS-A 20 Filling Monitor B 38 Standby CVCS-B 10 Standby WCT A Standby CVCS-C WCT B 7 Standby WHUT #NAME? Filling WCT C 9 Standby WCT D 10 Standby Data Linked to Fl WCTE 9 Standby WGDTS Pressure IPSIG Status A #NAME? -1IG On cover DEMINERALIZERS

. Resin B #NAME? PSIG In Service PPM In Service Date Replaced C1#NAMET PSIG Isolated MB A 2 9

l 4 YES 711712010 51412010 D #NAME? PSIG Standby MB B 2265 NO 711712010 3/2912010 CATION 1021 NO 911712010 12/9/2009 Shutdown Requirement Temp Boron DEBA 0 NO New 21312010 1.77%=LK1K 547FHot 258 ,

DEB B 0 1.77%=zKIK >350F 611 SFP 1963 NO 9/2312008 4/2212008 2.6% =AKIK 100 F Cold 776 6% =LK/K N/A 1950 Condenser Air Inleakage Target Value GPM Status PORV Settings A 13 CFM A 50 Flash Tank Setting Date POT GP-3 Psig B 0 CFM 5 50 With Heat f

7/18/2010 3.21 1000 C 50 1 Recovery 8 7/18/2010 3.12 1040 Total 5 CR4 N2 Flow 8 SCFM Ci/2010 3.44 1000 Effluent Radiation Monitor Setpoints Rad Current NUE Value RCS Leakage 0.00 Unidentified Alert Value 200X Monitor Setpoint 2X Fotal 0.03 GPM R-14C II OIE+04 N/A 2.020E+04 PRT 0.02 GPM REjiE0 N/A 1.480E+04 RCDT Leakage 0.01 GPM R-18 1.OOE+06 2.000E+08 [2.000E+06 Charging Leakoff 0 GPM R-1 9A I .05E+04 2.IOOE+06 2.IOOE+04 Misc Identified 0  : GPM R-19B 9.72E+03 1.944E+06 1.944E÷04 Primary/Secondary 0 GPD R-19C 9.58E+03 I .916E+06 I .916E+04 Secondary Loss 17.3 GPM R-37 8.53E+03 1.706E+06 1.706E+04 Manually Entered Data Linked to Chem data base Hi Flux At Shutdown Boron PPM I Date PPM Date PPM fevioRlCMnts Setpoint RCS Today 132 BAST-A 9/16/2010 21,535 #NAME?

Nl-32 60 180 BAST-B 9/16/2010 21,032 #NAME? #NAME7 SFP 9/15/2010 2246 #NAiNAME?

Normal Currents RWST 9/16/2010 2219 #iiiAME?

UPPER LOWER j]GEIj% BAND Accum-A 8130/2010 2211 N-41 144 136 0.0212 5 +1- Accum-B 8/30/2010 2206 #NAME? #NAME?

N-42 126 125 0.0212 5 +/- Accum-C 8/30/2010 2230 #NAME? #NAME?

N-43 121 113 0.0212 RHR 7/6/2010 2221 N-44 112 108 0.0212 Refuel Canal POWERTRAXRev#2.1.ORNP I%APL 112.55 Refuel Cavity SFP Canal FANS Test/Hrs Date/Tst HVE-IA/B 35640.6 3/8/10 Notes/Additional Data HVE-15A 18643.5 3118/10 IC-17, 20, 22 HVE-I9AIB 6928.3 5/3/10 EOL SR 3.7.11.2 Last Completed 5/2712010 19:45