Text

Initial Exam 2008-302 Final Simulator Scenarios
	ML091810124
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Issue date:	06/30/2009
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AppendixD Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-2 Op-Test Number: HLT0707 Examiners: Operators:

Initial Conditions:

Unit 3 is at 79% power. 3C RHR Pump is out of service. T.S 3.5.1.A.1, 3.6.2.3, 3.6.2.4, 3.6.2.5 have been entered. Unit 3 is 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months into a seven day LCO. Appendix R LCO addressed and in LCO tracking. Loop II of RHR has been vented within the hour in preparation for placing Torus cooling in service.

Turnover:

Alternate EHC Pumps per section 6.3 of 3-01-47A. Increase reactor power to 85% using Recirc flow (3-GOI-100-12, step 5.0[20]) with no pre-conditioning limitations. Reactor Engineering will evaluate further power changes. Continue with 3-SR-3.5.1.7 which is in progress and is complete up to Step 7.4 [7] (HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure).

Event Malfunction Event Event Number Number Type* Description 1 N/A N-BOP The crew will alternate EHC pumps using 3-01-47A.

N-SRO 2 N/A R-ATC The crew will continue with power ascension using 3-R-SRO GOI-12 and 3-01-68.

3 N/A N-BOP The BOP Operator will continue performance of a HPCI surveillance.

4 imf hp08 C-BOP The crew will recognize and respond to a HPCI steam C-SRO line break. HPCI will fail to auto isolate and must be TS-SRO manually isolated.

The SRO will enter and execute EOI-3.

5 imf ad01g 40 C-BOP The crew will recognize and respond to a stuck open C-SRO SRV using 3-AOI-1-1.

TS-SRO

6. bat RRPAVIB C-ATC The crew will recognize and respond to a recirc pump imf cr02a 75 C-BOP high vibration, dual seal failure, trip, core power 3:00 C-SRO oscillations and scram.

The crew will carry out actions using EOI-1 & 2 and 3-AOI-100-1.

7 imf th22 100 M-AII The crew will recognize and respond to a MSIV 1:30 Closure and LOCA using EOI-1 & 2.

The crew will monitor and control primary containment until reactor water level approaches TAF.

The crew will transition to EOI C-1 and perform Emergency Depressurization to enable level restoration using low pressure systems.

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor

AppendixD Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-5 Op-Test Number: HLT 0707 Examiners: Operators:

Initial Conditions: The unit is at 73% power with the 3A CRD Pump in standby and ready for a PMT this shift. 3B CRD pump is in service. 3B RFP is warming after maintenance to the oil system.

Turnover: The Reactor is at 73% Power because Recirc Pump 3A VFD tripped last night due to a logic card failure. Power was being restored when an oil leak developed on the 3B RFP.

Maintenance has completed repairs and the clearance is picked up. The RFP was placed in warming last shift. Plans are to return 3B RFP to service per 3-01-3 section 5.7 and place in Auto, then return reactor power to 100% with control rod withdrawal and Recirc flow per 3-GOI-100-12 step 5 [20].

Event Malfunction Event Event Number Number Type* Description 1 none N-ATC Place 3B RFP back in service and increase Rx power N-BOP with control rod withdrawal and Recirc flow increase.

R-SRO 2 imf ed09a C-ATC Loss of 4KV Shutdown Board "3EA" (Bus Lockout) Loss C-BOP causes loss of operating CRD pump, a loss of RPS "N ,

C-SRO a loss of RBCCW, a loss of RWCU, FPC, and a loss of TS-SRO SJAE. ATC will swap CRD pumps and restore RPS power. BOP will restore RBCCW, RWCU, FPC and re-start SJAE. The SRO will address Tech Specs due to multiple component failures 3 none TS-SRO Low oil level is reported on 3B Core Spray pump.

4 imf hp01 C-ATC HPCI inadvertently initiates and injects to the RPV C-BOP without a valid initiation signal. ATC will return FWLC C-SRO from 1-element to 3-element control.

TS-SRO 5 imf tc07 100 R-ATC EHC leak. BOP must lock out EHC pumps and trip C-BOP Main Turbine. ATC reduces power and scrams C-SRO Reactor.

6 bat atws95east M-AII ATWS with fuel failure. SRO and crew respond per EOI-1, EOI-2 and C-5 imfth2320

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)aJor

AppendixD Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-6 Op-Test Number: HLT 0707 Examiners: Operators:

Initial Conditions: Unit at 70% power due to 3A Condensate Booster Pump out of seNice for oil leak. CRD Pump 3B tagged out for breaker work. 3-FCV-74-100 tagged out for maintenance on the actuator, valve has a mechanical locking device installed and is closed.

Actuator is removed. HPCI injection valves tagged for replacement of contactors in supply breakers. A 14 day LCO (TS 3.5.1) has been entered. Work has been completed and the clearance has been released.

Turnover: CRD Timer has been replaced, perform CRD Timer Test per 3-01-85 section 8.14, then withdraw rods per RE instructions to establish rod pattern. When 3A CBP is restored, continue to raise power and monitor pump amps. (step 5.0[18.3] of 3-GOI-1 00-12). When HPCI clearance is picked up, perform PMT per WO (copy attached) prior to making HPCI operable. EM connecting MOVAT equipment to Sys 69 valves, should be invisible to control room personnel.

Event Malfunction Event Event Number Number Type* Description 1 None N-ATC ATC performs CRD Timer test per 3-01-85.

2 None R-ATC Raise Reactor Power by control rod withdrawal.

R-SRO 3 imf C-ATC Control Rod 34-19 uncouples during Control Rod rd05r3419 C-SRO movement, ATC responds per AOL Tech Spec call for ITS-SRO SRO.

4 ior zdihs691 C-BOP BOP responds to RWCU inadvertent isolation. Tech close C-SRO Spec call for SRO.

ITS-SRO 5 ior C-ATC ATC responds to loss ofVFD cooling water system.

zdihs682a1 a C-SRO off 6 ior zdihs719a C-BOP BOP responds to RCIC trip and performs HPCI PMT.

trip C-SRO SRO refers to Tech Specs.

ITS-SRO 7 imf ad01b 25 C-BOP BOP responds to stuck open MSRV which results in C-SRO rising Suppression Chamber pressure due to a tailpipe ITS-SRO break. SRO address Tech Specs for ADS valve failure and direct manual scram before DW pressure exceeds 2.45 psig.

8 imf pc14 50 M-AII Crew responds to lowering Suppression Pool level due to an un-isolable leak.

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor

AppendixD Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-7 Op-Test Number: HLT 0707 Examiners: Operators:

Initial Conditions: Unit 3 is at 100% rated power. HPCI was tagged out 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago for repair to the Gland Seal Exhauster. Expected return to service is in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . A 14 day LCO Action has been entered in accordance with TSR 3.S.1.

Turnover: Maintain 100% power. Unit 3 has been operating for 187 days. Unit 1 and Unit 2 are at 100% power. Perform 3-SR-3.3.1.1.8(11) REACTOR PROTECTION SYSTEM MANUAL SCRAM FUNCTIONAL TEST. Severe thunderstorms are expected to pass through the area for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Limestone County is currently under a tornado watch.

Event Malfunction Event Event Number Number Type* Description 1 none N-ATC The ATC will perform 3-SR-3.3.1.1.8(11) REACTOR N-SRO PROTECTION SYSTEM MANUAL SCRAM FUNCTIONAL TEST.

2 mrf R-ATC The operating crew will recognize and respond to a rd10r1839 R-SRO control rod scram in accordance with 3-AOI-8S-S.

scram TS-SRO 3 imf C-ATC The crew will recognize that control rod 22-39 is stuck rd06r2239 C-SRO and difficult to withdraw. The ATC will respond in accordance with 3-01-8S.

4 imf ad01f C-BOP The operating crew will recognize and respond to a stuck C-SRO open SRV in accordance with 3-AOI-1-1.

TS-SRO The SRO will recognize an inoperable ADS valve and HPCI in accordance with Technical Specifications.

S imf ed06b The operating crew will recognize a loss of 161 KV.

6 imf th33a M-ALL The operating crew will recognize and respond to a imf th22 steam line break per the ARPs and EOls.

7 imf ed01 M-ALL The operating crew will recognize and respond to a loss of offsite power per 0-AOI-S7-1A.

8 imf dg01a C-BOP The operating crew will recognize and respond to diesel imf dg03d generator failures per 0-AOI-S7-1A.

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor

AppendixD Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-8 Op-Test Number: HLT 0707 Examiners: Operators:

Initial Conditions: Unit 3 is at -1 % power with a unit startup in progress. Currently at step 5.0[60.3] of3-GOI-100-1A, Rod Group 17, control rod 30-11. 3C RFP is warmed at 600 rpm ready to be started. 3B CRD pump has been tagged for bearing replacement. IRM "G" is bypassed due to periodic noise spikes. System Engineering is monitoring IRM operation.

Turnover: Continue start-up. Commence inerting the Suppression Chamber per 3-01-76 Section 5.1. The potential for icing of power lines due to freezing rain has been reported by Transmission Power Services.

Event Malfunction Event Event Number Number Type* Description 1 none N-ATC Place 3C RFP in service per 3-01-3.

2 none N-BOP The operating crew will commence inerting the suppression chamber per 3-01-76.

3 none R-ATC The operating crew will withdraw control rods in R-SRO accordance with 3-01-85 and 3-GOI-100-1A.

4 imf rd02a C-ATC The operating crew will recognize and respond to a failed C-SRO CRD Flow Control valve per 3-AOI-85-3.

5 imf nm05c C-ATC The operating crew will recognize and respond to a failed C-SRO IRM instrument per 3-01-92 and Tech. Specs.

TS-SRO 6 C-BOP The operating crew will recognize and respond to a failed C-SRO H2/02 analyzer in accordance with ARPs and Tech.

TS-SRO Specs.

7 imf ed07a C-BOP The operating crew will recognize and respond to a trip C-SRO of 480V Unit Board 3A per ARPs.

8 imf nm05b M-ALL The operating crew will recognize and respond to another IRM instrument failure and subsequent Rx.

Scram.

9 imf th33c M-ALL The operating crew will respond to 3-EOI-1 and 3-EOI-2 entry conditions for failure to scram and drywell leak.

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor

Appendix D Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-2 Op-Test Number: HLT0707 Examiners: Operators:

Initial Conditions:

Unit 3 is at 79% power. 3C RHR Pump is out of service. T.S 3.5.1.A.1, 3.6.2.3, 3.6.2.4, 3.6.2.5 have been entered. Unit 3 is 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months into a seven day LCO. Appendix R LCO addressed and in LCO tracking. Loop II of RHR has been vented within the hour in preparation for placing Torus cooling in service.

Turnover:

Alternate EHC Pumps per section 6.3 of 3-01-47A. Increase reactor power to 85% using Recirc flow (3-GOI-1 00-12, step 5.0[20]) with no pre-conditioning limitations. Reactor Engineering will evaluate further power changes. Continue with 3-SR-3.5.1. 7 which is in progress and is complete up to Step 7.4 [7] (HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure).

Event Malfunction Event Event Number Number Type* Description 1 N/A N-BOP The crew will alternate EHC pumps using 3-01-47A.

N-SRO 2 N/A R-ATC The crew will continue with power ascension using 3-R-SRO GOI-12 and 3-01-68.

3 N/A N-BOP The BOP Operator will continue performance of a HPCI surveillance.

4 imf hp08 C-BOP The crew will recognize and respond to a HPCI steam C-SRO line break. HPCI will fail to auto isolate and must be TS-SRO manually isolated.

The SRO will enter and execute EOI-3.

5 imf ad01g 40 C-BOP The crew will recognize and respond to a stuck open C-SRO SRV using 3-AOI-1-1.

TS-SRO

6. bat RRPAVIB C-ATC The crew will recognize and respond to a recirc pump imf cr02a 75 C-BOP high vibration, dual seal failure, trip, core power 3:00 C-SRO oscillations and scram.

The crew will carry out actions using EOI-1 & 2 and 3-AOI-100-1.

7 imf th22 100 M-AII The crew will recognize and respond to a MSIV 1 :30 Closure and LOCA using EOI-1 & 2.

The crew will monitor and control primary containment until reactor water level approaches T AF.

The crew will transition to EOI C-1 and perform Emergency Depressurization to enable level restoration using low pressure systems.

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor

HLTS-3-02 Rev 0 Page 1 of 44 SIMULATOR EVALUATION GUIDE TITLE: HPCI STEAMLINE BREAK, SRV FAILURE, RECIRC PUMP TRIP, DRYWELL LEAK, EMERGENCY DEPRESSURIZATION ON LEVEL (C1)

REVISION: 0 DATE: October 12, 2008 PROGRAM: BFN Operator Training - Hot License Requires copy of 3-SR-3.5.1.7 (current rev.) completed up to step 7.4 [7] to be provided to crew at turnover PREPARED: \

(Operations Instructor) Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HLTS-3-02 Rev 0 Page 2 of 44 Nuclear Training Revision/Usage Log Revision Description of Date Pages Revised Number Changes Affected 0 Initial 10/12/08 All csf

HLTS-3-02 Rev 0 Page 3 of 44 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

HPCI STEAMLINE BREAK, SRV FAILURE, RECIRC PUMP TRIP, DRYWELL LEAK, EMERGENCY DEPRESSURIZATION ON LEVEL (C1)

IV. Length of Scenario - 1 to 1 ~ hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment I unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HL TS-3-02 Rev 0 Page 4 of 44 B. Enabling Objectives:

1. The operating crew will alternate EHC pumps.

2. The operating crew will continue power ascension from::::: 79% power.

3. The operating crew will experience a HPCI steam line break during performance of 3-SR-3.5.1.7 , HPCI Flow Rate, with a failure of HPCI to auto isolate.

4. The operating crew will recognize and respond to a safety-relief valve failed open.

5. The operating crew will recognize and respond to a high vibration and trip of 3A Recirc pump.

6. The operating crew will recognize and respond to a high drywell pressure condition.

7. The operating crew will Emergency Depressurize when in C1 before reactor water level reaches -180".

HLTS-3-02 Rev 0 Page 5 of 44 VI.

References:

The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order I Caution Order tags E. Annunciator window covers F. Steam tables

HLTS-3-02 Rev 0 Page 6 of 44 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat HLTS-3-02 MF/RF/OR# Description

1) trg e1 MOOESW Sets trigger

2) trg e2 adssrv1-22 Sets trigger

3) ior zlohs 7 416a[1] off Tag Out 3C RHR

4) imf rh01c 3C RHR Pump trip

5) ior ypobkrpmpcrh fail power Control power for RHR 3C breaker

6) mrf hw01 fast Advances all charts

7) imf th33b(e1 0) 1 2:00 B MSL break in OW 8t imf th21 (e1 5:00) 0.5 10:00 Recirc. line break

9) imf rd01a (e1 10:00) 3A CROP trip

10) imf rd01 b 3B CROP trip

11) imf hp09 Failure of HPCI to auto isolate

12) ior zlohs 718a[1] on Fails 71-8 green light on

13) ior ypovfcv718 fail now Keeps the 71-8 valve closed

14) imf rp11 (e1 1 :00) MSIV logic fuse failure

2. File: bat RRPAVIB MF/RF/OR# Description

1) imf th12a Inserts Vibration Alarm

2) imf th1 Oa (none 1:00) 25 Fails Recirc Pump A Inboard Seal

3) imf th11 a (none 2:00) 25 Fails Recirc Pump A Outboard Seal)

4) ior zdihs681 open Prevents Recirc Pump A Suction Valve Closure

HLTS-3-02 Rev 0 Page 7 of 44 VIII. Console Operator Instructions ELAPSED TIME PFK DESCRIPTION I ACTION Simulator setup ~ 78 %Power MOC, use mid-power runback push button from IC-28 (snapshot 246) (david)

Simulator setup manual bat HLTS3-02 See Scenario File Summary Simulator setup manual Place suppression pool cooling in service (Loop II)

Simulator setup manual Place HO tags on '3C' RHR pump Simulator setup manual Place TESTING/MAINT frames on Panel 9-3F, Windows 5, 11,26 for HPCI 3-SR-3.5.1.7 complete up to step 7.4 [7]

Simulator setup manual Provide a copy of 3-SR-3.6.2.1.1 ,

Suppression Chamber Water Temperature Checks.

Simulator setup manual Verify lens covers on EHC pumps are correct Simulator setup mrf hp02 Isolate HPCI Fire Protection Valve close ROLE PLAY: When asked for local EHC pressure, (3-PI-047 -0001 (0002>> indicates 1625 psig. (3-01-47 A section 6.3 step [4].

ROLE PLAY: When asked, EHC pump 38 EHC PUMP SUCTION FILTER and EHC AUX PUMP SUCTION FILTERS, indicate CLEAN, (3-01-47 A section 6.3 step [11].

ROLE PLAY: When asked, MANUAL FLOW CONTROL VALVE, 3-047-0588, is set at 2.0 turns clockwise. (3-01-47A section 6.3 step [12].

ROLE PLAY: When asked, personnel are ready to monitor 3-FCV-73-18 for smooth operation.

HLTS-3-02 Rev 0 Page 8 of 44 When HPCI is at rated pressure and (imf hp08) flow Steam leak into HPCI room ROLE PLAY: AUO at HPCI quad. Reports a large steam leak on HPCI and present location is elev. 565 Rx.Bldg.

When directed by Lead Instructor Fails SRV-1-22 open (imf ad01 c 40)

When RO cycles SRV then: SRV-1-22 closes (dmf ad01 c)

When directed by Lead Instructor Recirc Pump A high vibration, seal failure, suction valve fails to close.

(bat RRPAVIB)

ROLE PLAY: When dispatched to check 3A Recirc Vibration, wait 2 minutes and report back 3-XI-68-59 F & G are swinging 10 to 14 mils.

When 'A' Recirc trips Deletes vibration high alarm (dmfth12a) 4 min. after 3A recirc. pump trip then: Bottom head leak (imf th22 (none 1:30) 100)

Terminate the scenario when the following conditions are satisfied or upon request of instructor:

1) Drywell sprayed

2) Emergency Depressurization completed

3) RPV water level +2" to +51"

HL TS-3-02 Rev 0 Page 9 of 44 IX. Scenario Summary:

Given Unit 3 at 79% power, the crew will alternate EHC pumps and resume power ascension to 100%. As 3-SR-3.5.1.7, HPCI Flow Rate, is continued the crew will experience a ruptured HPCI steam line with a failure of HPCI to automatically isolate.

Manual HPCI isolation will be possible. As power ascension is continued, an SRV fails open but can be closed as steps of 3-AOI-1-1 are performed. The crew experiences high vibration with a subsequent trip and seal leakage on the 3A Recirc Pump resulting in high drywell pressure. When the diesel generators automatically start the 3ED diesel generator fails to auto start but can be manually started. Finally, the crew will Emergency Depressurize before reactor water level reaches -200".

HLTS-3-02 Rev 0 Page 10 of 44 X. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. US: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1) Drywell sprayed

(

2) Emergency Depressurization completed

3) RPV water level +2" to +51"

HLTS-3-02 Rev 0 Page 11 of 44 XI. Simulator Event Guide:

Event #1: Alternate EHC Pumps Position Expected Actions Sat/UnsatlComments ATC/BOP Receive crew briefing and walk boards down SRO Directs BOP to alternate EHC pumps per 3-01-47 A section 6.3 BOP Alternates EHC pumps lAW 3-01-47A section 6.3

[1] VERIFY EHC System is in service. REFER TO Section 5.1.

[2] REVIEW Precautions and Limitations listed in Section 3.0.

[3] START the non-operating EHC PUMP 3B(3A) using EHC HYD FLUID PUMP 3B(3A), 3-HS 2A(1A).

Direct AUO to perform steps [4] and [5]

[6] STOP EHC PUMP 3A(3B) using EHC HYD FLUID PUMP 3A(3B), 3-HS-47-1A(2A). (N/A)

[7] CHECK EHC HEADER PRESSURE, 3-PI-47-7, indicates between 1550 pslg and 1650 psig

[8] IF EHC header pressure is NOT between 1550 psig and 1650 psig, THEN ADJUST the pressure compensator for the operating EHC pump to adjust EHC header pressure. REFER TO Step 8.6[2].

[9] IF there are any disagreement flags, THEN RESET disagreement flags by placing the operating pump handswitch, EHC HYD FLUID PUMP 3A(3B), 3-HS-47-1A(2A), to START Direct AUO to perform steps [10] thru [12]

Swaps lens covers for EHC pumps based on new lineup

HL TS-3-02 Rev 0 Page 12 of 44 XI. Simulator Event Guide:

Event #2: Power Ascension Position Expected Actions SatlUnsat/Comments SRO Directs power ascension per 3-GOI-100-12 step 5.0[18] and 3-01-68, section 6.2 ATC Raises reactor power in accordance with 3-GOI-100-12 step 6.2 and 3-01-68

[18] RAISE power to 100%, or as directed by the Unit Supervisor, using control rod withdrawal or core flow changes, as recommended by the Reactor Engineer, while monitoring core thermal limits (Illustration 1). (REFER TO 3-SR-3.1.3.5(A) and 3-01-68).

[1] ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-15A(15B)/LOWER SLOW(MEDIUM) 3-HS-96-17A(17B), push-buttons, to achieve balanced jet pump flows. N/A for Single Loop Operation. ANDIOR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS-96-16A(16B)/LOWER SLOW(MEDIUM) 3-HS-96-18A(18B), push-buttons, to achieve balanced jet pump flows. N/A for Single Loop Operation.

[2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the RECIRC MASTER CONTROL, THEN ADJUST Recirc Pump speed 3A & 3B using the following push buttons as required:

RAISE SLOW, 3-HS-96-31

RAISE MEDIUM, 3-HS-96-32

LOWER SLOW, 3-HS-96-33

LOWER MEDIUM, 3-HS-96-34

LOWER FAST, 3-HS-96-35 BOP Performs as peer checker for recirc flow changes

HLTS-3-02 Rev 0 Page 13 of 44 XI. Simulator Event Guide:

Event #3: HPCI Surveillance Position Expected Actions SatlUnsat/Comments SRO Directs BOP to continue with 3-SR-3.S.1.7 at step 7.4[7]

BOP Continues with HPCI SR - already in progress

[7] ALIGN HPCI System for a manual start by performing the following steps:

[7.1] CHECK HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 is in AUTO and SET to control at 500 (5,000 gpm). IF required, THEN DEPRESS AUTO operation mode transfer switch and ADJUST setpoint using Setpoint up/down keys.

[7.2] PLACE HPCI STEAM PACKING EXHAUSTER by placing 3-HS-73-10A to START.

[7.3] VERIFY 3-FCV-73-36, using HPCI/RCIC CST TEST VLV 3-HS-73-36A, is OPEN.

[7.4] OPEN 3-FCV-73-35, using HPCI PUMP CST TEST VLV, 3-HS-73-35A.

[8] START the HPCI turbine by performing the following:

[8.1] [NER] VERIFY communication is established with Operations personnel in HPCI Room. [IE 93-67]

[8.2] [NER] REQUEST Operations personnel in HPCI Room, to ensure that all unnecessary personnel have exited HPCI Room. [IE 93-67]

[8.3] [NER] ANNOUNCE HPCI turbine startup over plant public address system. [IE 93-67]

HLTS-3-02 Rev 0 Page 14 of 44 XI. Simulator Event Guide:

(

Event #3: HPCI Surveillance Position Expected Actions SatlU nsatlComments BOP [8.4] PLACE HPCI AUXILIARY OIL PUMP 3-HS-73-4 7A to START.

[8.5] OPEN 3-FCV-73-30, using HPCI PUMP MIN FLOW VALVE, 3-HS-73-30A.

[8.6] ENSURE personnel are ready to monitor 3-FCV-73-18 for smooth operation.

AND NOTIFY the personnel monitoring that the next step will open 3-FCV-73-18.

[8.7] OPEN 3-FCV-73-16, using HPCI TURBINE STEAM SUPPLY VLV, 3-HS 16A.

[8.8] OBSERVE that the following actions occurs:

HPCI AUXILIARY OIL PUMP starts.

[NRC/C] HPCI TURBINE STOP VALVE 3-FCV-73-18 opens by observing 3-ZI-73-18 position indicating lights. [Appendix R]

HPCI TURBINE CONTROL VALVE 3-FCV-73-19 partially or fully opens by observing 3-ZI-73-19 position indicating lights.

[NRC/C] HPCI PUMP MIN FLOW VALVE 3-FCV-73-30 closes when HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 indicates approximately ~

125 (~ 1250 gpm) flow. [Appendix R]

HPCI turbine speed rises to greater than 2400 rpm as indicated on HPCI TURBINE SPEED 3-SI-73-51.

HPCI STM LINE CNDS INBD/OUTBD DR VLVS 3-FCV 6A and 3-FCV-73-6B close by observing 3-ZI-73-6A and 3-ZI-73-6B position indicating lights.

HPCI AUXILIARY OIL PUMP stops as turbine speed rises.

HLTS-3-02 Rev 0 Page 15 of 44 XI. Simulator Event Guide:

Event #3: HPCI Surveillance Position Expected Actions SatlU nsat/Comments BOP [8.9] VERIFY Smooth operation of 3-FCV-73-18 and mark results below.

YesDNoDD

IF the Answer above is "NO", THEN NOTIFY System Engineer to initiate a WO and proceed with test.

(Otherwise N/A)

[8.10] VERIFY RESET the following annunciators:

HPCI PUMP DISCH FLOW LOW 3-FA-73-33 (3-XA-55-3F, window 5)

HPCI TURBINE TRIPPED 3-ZA 18 (3-XA-55-3F, window 11 )

HPCI TURBINE GLAND SEAL DRAIN PRESSURE HIGH 3-PA 46 (3-XA-55-3F, window 14)

HPCI TURBINE BEARING OIL PRESSURE LOW 3-PA-73-47 (3-XA-55-3F, window 19)

[8.11] VERIFY system flow, discharge pressure, and turbine speed are stable prior to performing the next step

HLTS-3-02 Rev 0 Page 16 of 44 XI. Simulator Event Guide:

Event #4: HPCI Steam Line Break Position Expected Actions SatlUnsat/Comments BOP Announces Reactor bldg Hi Rad Alarm (3-ARP 3Awin 22)

A. DETERMINE area with high radiation level on Panel 3-9-11. (Alarm on Panel 3-9-11 will automatically reset if radiation level lowers below setpoint.)

Determines HPCI is the source of the Alarm and has personnel locally verify alarm B. IF the alarm is from the HPCI Room while Flow testing is being performed, THEN REQUEST personnel at the HPCI Quad to validate conditions When notified by personnel at HPCI of steam leak, notifies US C. NOTIFY RADCON D. IF the TSC is NOT manned and a "VALID" radiological condition exists., THEN USE public address system to evacuate area where high airborne conditions exist SRO Enters EOI-3 on HPCI area Hi Rad

HLTS-3-02 Rev 0 Page 17 of 44 XI. Simulator Event Guide:

Event #4: HPCI Steam Line Break Position Expected Actions SatlU nsatlComments BOP Notifies US of isolation signal with a failure to isolate.

SRO Directs BOP to manually isolate HPCI BOP Manually isolates HPCI SRO Determines unit in 14 day LCO (TS 3.5.1.C - HPCI inop. Verify RCIC OPERABLE by administrative means Determines unit in 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO (TS 3.5.1.0 - HPCI and C RHR Inop)

Tech. Specs. 3.6.1.3.B.1, on FCV 73-2 or 73-3 (failed to auto isolate) (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to close and de-activate)

HL TS-3-02 Rev 0 Page 18 of 44 XI. Simulator Event Guide:

Event #5: SRV-1-22 Fails Open Position Expected Actions SatlU nsat/Com ments Crew Recognizes SRV open by; Main Steam Relief Valve Open alarm, 3-ARP-9-3C window 25 lowering generator output BOP A. CHECK MSRV DISCHARGE TAILPIPE TEMPERATURE, 3-TR-1-1, on Panel 3-9-47 and SRV Tailpipe Flow Monitor on Panel 3-9-3 for rising temperature and flow indications.

B. REFER TO 3-AOI-1-1.

C. IF alarm is due to sensor malfunction, THEN REFER TO 0-01-55 and OPDP-4.

SRO Directs response per 3-AOI-1-1 BOP Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 3-FMT-1-4, on Panel 3-9-3, OR

MSRV DISCHARGE TAILPIPE TEMPERATURE, 3-TR-1-1 on Panel 3-9-47 Determines open valve is SRV-1-22

HLTS-3-02 Rev 0 Page 19 of 44 XI. Simulator Event Guide:

Event #5: SRV-1-22 Fails Open Position Expected Actions Sat/Unsat/Comments BOP [2] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch several times as required:

CLOSE to OPEN to CLOSE positions Cycles valve from close to open to close and reports to US that the valve went closed

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A)

[1] IF ANY EOI entry condition is met, THEN ENTER the appropriate EOI(s)

[2] REFER TO Technical Specifications Sections 3.5.1 and 3.4.3 for Automatic Depressurization System and relief valve operability requirements

[3] INITIATE suppression pool cooling as necessary to maintain suppression pool temperature less than 95°F.

[4] IF the relief valve can NOT be closed AND suppression pool temperature Can NOT be maintained less than or equal to 95°F, THEN PLACE the reactor Modeo4 in accordance with 3-GOI-100-12A.

[5] DOCUMENT actions taken and INITIATE Work Order for the valve SRO Evaluates Tech Spec operability of ADS valve lAW TS 3.5.1 (H) and 3.4.3(A). Determines valve operable and 3.5.1.H is not applicable, but requests Eng. evaluation. (Functional evaluation)

HL TS-3-02 Rev 0 Page 20 of 44 XI. Simulator Event Guide:

Event #6: Recirc Vibration, Seal Leakage, and Scram Position Expected Actions SatlU nsatlComments ATC Announces Recirc "3A" high vibration alarm 9-4A win 20 SRO Directs entry into 3-ARP-9-4A window 20 ATC A. CHECK temperatures for RECIRC PMP MTR 3A13B WINDING AND BRG TEMP recorder, 3-TR-68-71 on Panel 3-9-21 are below those listed for 3-XA-55-4A, Window 13 B. CHECK for a rise in Drywell equip sump pumpout rate due to seal leakage C. DISPATCH personnel to 3-LPNL-925-0412 (Vibration Mon. System) on EL 565' (S-R17) and REPORT the Vibration Data for Pump A to the Unit Operator and any other alarm indications. The person shall advise the Unit Operator of any changes in the vibration values D. IF alarm seals in, THEN ADJUST pump speed slightly to try reset the alarm.

Adjusts pump speed slightly in an attempt to reset alarm (alarm does not clear)

E. IF unable to reset alarm, THEN CONSULT with Shift Manager, and with his concurrence, SHUTDOWN the Recirc pump and REFER TO 3-AOI-68-1A or 3-AOI-68-1 B

HL TS-3-02 Rev 0 Page 21 of 44 XI. Simulator Event Guide:

Event #6: Recirc Vibration, Seal Leakage, and Scram Position Expected Actions Sat/U nsat/Com ments SRO Contacts Rx Engineer ATC Announces RECIRC PUMP A NO.1 SEAL LEAKAGE ABN Alarm 3*ARP*9*4A win 25 A. DETERMINE initiating cause by comparing No.

1 and 2 seal cavity pressure indicators on Panel 3-9-4 or ICS.

Plugging of No.1 RO - No.2 seal cavity pressure indicator drops toward zero.

Plugging of No.2 RO - No.2 seal pressure approaches no. 1 seal pressure.

Failure of No.1 seal - No.2 seal pressure is greater than 50% of the pressure of No.1.

Failure of No.2 seal - no. 2 seal pressure is less than 50% of the No. 1 seal

(

HLTS-3-02 Rev 0 Page 22 of 44 XI. Simulator Event Guide:

Event #6: Recirc Vibration, Seal Leakage, and Scram Position Expected Actions Sat/U nsat/Comments ATC Announces RECIRC PUMP A NO.2 SEAL LEAKAGE HIGH Alarm (3-ARP-9-4A window 18)

A. COMPARE No.2 cavity pressure indicator (3-PI-68-63A) to No.1 cavity pressure indicator (3-PI-68-64A). No.2 seal degradation is indicated if the pressure at No.2 seal is less than 50% of the pressure at No.1 seal Recognizes lowering pressure on Recirc Pump A

2 (outboard) seal; informs SRO C. IF dual seal failure is indicated, THEN

1. SHUTDOWN Recirc Pump 3A by depressing RECIRC DRIVE 3A SHUTDOWN, 3-HS-96-19.

( 2. VERIFY TRIPPED, RECIRC DRIVE 3A NORMAL FEEDER, 3-HS-57-17.

3. VERIFY TRIPPED, RECIRC DRIVE 3A ALTERNATE FEEDER, 3-HS-57-15.

4. CLOSE Recirculation Pump 3A suction valve.

5. CLOSE Recirculation Pump 3A discharge valve

6. REFER TO 3-AOI-68-1A or 3-AOI-68-1 BAND 3-01-68.

7. DISPATCH personnel to secure Recirculation Pump 3A seal water Monitors drywell parameters; notes pressure and temperature increasing; informs SRO of pressure rise and dual seal failure

HLTS-3-02 Rev 0 Page 23 of 44 XI. Simulator Event Guide:

(

Event #6: Recirc Vibration, Seal Leakage, and Scram Position Expected Actions SatlUnsat/Comments SRO When vibration report received or dual seal failure is reported, directs "A' Recirc Pump tripped Directs entry into 3-AOI-68-1A ATe Subsequent Actions

[2] IF Region I or II of the Power to Flow Map (Illustration 1) is entered, THEN (Otherwise N/A)

IMMEDIATELY take actions to INSERT control rods to less than 95.2% loadline. Refer to 0-TI-464, Reactivity Control Plan Development and Implementation

[3] RAISE core flow to greater than 45%. Refer to 3-01-68

(

HLTS-3-02 Rev 0 Page 24 of 44 XI. Simulator Event Guide:

Event #6: Recirc Vibration, Seal Leakage, and Scram Position Expected Actions SatlUnsatlComments SRO Directs 3A Recirc pump seal purge isolated and the pump suction and discharge valves isolated.

ATC Attempts to isolate 3A Recirc pump suction valve and dispatches AUO to isolate seal purge Reports to US that 3A Recirc suction valve will not close Informs US of entry into Region 1 of the Power to Flow map and driving rods per RCP Crew Monitors Drywell pressure SRO Directs venting Drywell per 3-AOI-64-1 BOP Vents Drywell 3-AOI-64-1

HLTS-3-02 Rev 0 Page 25 of 44 XI. Simulator Event Guide:

Event #6: Recirc Vibration, Seal Leakage, and Scram Position Expected Actions Sat/U nsat/Comments BOP Directs Control Bay AUO to monitor release rates Reports Drywell pressure still rising SRO Directs manual Rx scram prior to reaching +2.45 psig DW pressure.

ATC Scrams the Reactor Gives scram report (all rods in)

SRO Enters EOI-1 and EOI-2 at +2.45 psig Exits RC/Q and directs entry into 3-AOI-100-1 Directs venting per Appendix-12 BOP Vents Suppression Chamber per App-12

1. VERIFY at least one SGTS train in service

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE

HL TS-3-02 Rev 0 Page 26 of 44 XI. Simulator Event Guide:

Event #6: Recirc Vibration, Seal Leakage, and Scram Position Expected Actions Sat/U nsat/Comments NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented BOP 7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20

8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CaNT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CaNT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV 19 CONTROL, in OPEN (Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CaNT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12

HLTS-3-02 Rev 0 Page 27 of 44 XI. Simulator Event Guide:

Event #6: Recirc Vibration, Seal Leakage, and Scram Position Expected Actions Sat/UnsatlComments BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CaNT, or 3-FIC-84-20, PATH A VENT FLOW CaNT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

0-SI-4.8.B.1.a.1 release fraction of 1 Directs Control Bay AUO to monitor release rates

HLTS-3-02 Rev a Page 28 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions SatlU nsat/Com ments BOP Recognizes MSIV closure and reports to US SRO Directs RPV pressure controlled 800 to 1000 psig with one or more of the following:

MSRVs (Appendix-11A)

RCIC (Appendix-11 8) (will not work)

Directs level be maintained +2" to +51" with one or more of the following;

RCIC (Appendix-5C) (will not work)

CRD (Appendix-58)

( BOP Controls RPV pressure 800 - 1000 psig with MSRVs per App-11A

3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

(sequence is 1-13)

HLTS-3-02 Rev 0 Page 29 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions SatlU nsat/Com ments

1. IF ..... Emergency RPV Depressurization is required, OR Steam Cooling is required, THEN ... EXECUTE EOI Appendix 16A and 16B as necessary to bypass RCIC Low RPV Pressure and Test Mode Isolation Interlocks

2. IF ..... Suppression Pool level CANNOT be maintained below 5.25 in., THEN ... EXECUTE EOI Appendix 16E concurrently with this procedure to bypass HPCI High Suppression Pool Level Suction Transfer Interlock Reports RCIC failure (71-8 will not open) if attempted per App-11 B ATC Controls level with CRD per App-5B

1. IF ..... Maximum injection flow is NOT required, THEN ... VERIFY CRD aligned as follows:

a. VERIFY at least one CRD pump in service and aligned to Unit 3 CRD system.

b. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, as necessary to obtain flow rate of 65 to 85 gpm.

c. THROTTLE 3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VLV, to maintain 250 to 350 psid drive water header pressure differential.

d. EXIT this procedure

HLTS-3-02 Rev 0 Page 30 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/U nsat/Comments SRO Directs determining cause of MSIV closure Directs maintenance to investigate 71-8 problem with RCIC Directs maintenance to investigate problem with 3B CRD pump Directs H2 0 2 analyzers placed in service BOP Places H2 02 analyzers in service

1. Place Analyzer isolation bypass keylock switches to bypass.

2. Select DW or Supp Chmbr and momentarily pull out select switch handle to start sample pumps.

HLTS-3-02 Rev 0 Page 31 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/Unsat/Comments SRO Directs Suppression pool cooling placed in service per Appendix-17 A BOP Places Suppression pool cooling in service per Appendix-17 A

1. IF .............. Adequate core cooling is assured, OR Directed to cool the Suppression Pool irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS 1(11)

OUTBD INJ VLV BYPASS SEL in BYPASS

2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump

( supplying each EECW header.

b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

c. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV

d. IF ............. Directed by SRO, THEN ....... PLACE 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD in MANUAL OVERRIDE

HL TS-3-02 Rev 0 Page 32 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/U nsat/Comments BOP e. IF ............. LPCI INITIATION Signal exists, THEN ....... MOMENTARILY PLACE 3-XS 121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT in SELECT

f. IF ............. 3-FCV-74-53(67), RHR SYS 1(11)

LPCI INBD INJECT VALVE, is OPEN, THEN .......

VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11)

LPCI OUTBD INJECT VALVE

g. OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBR/POOL ISOL VLV

h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating

i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11)

( SUPPR POOL CLGITEST VLV, to maintain EITHER of the following as indicated on 3-FI 50(64), RHR SYS 1(11) FLOW:

Between 7000 and 10000 gpm for one-pump operation. OR

At or below 13000 gpm for two-pump operation

j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE

k. MONITOR RHR Pump NPSH using Att. 1 I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers

m. IF ............. Additional Suppression Pool Cooling flow is necessary, THEN ....... PLACE additional RHR and RHRSW pumps in service using Steps 2.b through 2.1 Notifies Chemistry that RHRSW is aligned to in-service RH R hx

HLTS-3-02 Rev 0 Page 33 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions SatlU nsatlComments SRO Determines cannot maintain suppression chamber pressure less than 12 psig and directs suppression chamber sprayed per Appendix-17C BOP 5. INITIATE Suppression Chamber Sprays as follows:

VERIFY at least one RHRSW pump supplying each EECW header.

VERIFY OPERATING the desired RHR System 1(11) pump(s) for Suppression Chamber Spray.

VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBRIPOOL ISOL VLV.

OPEN 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.

IF ............. RHR System 1(11) is operating ONLY in Suppression Chamber Spray mode, THEN .......

CONTINUE in this procedure at Step 5.k.

HLTS-3-02 Rev 0 Page 34 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/U nsat/Comments BOP VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

RAISE system flow by placing the second RHR System 1(11) pump in service as necessary.

MONITOR RHR Pump NPSH using Attachment 2.

VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

6. WHEN ...... EITHER of the following exists:

Before Suppression Pool pressure drops below 0 psig, OR

Directed by SRO to stop Suppression Chamber Sprays, THEN ....... STOP Suppression Chamber Sprays Monitors Containment parameters (notifies US when suppression chamber pressure is > 12 psig)

HLTS-3-02 Rev 0 Page 35 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/UnsatlComments SRO When SC pressure exceeds 12 psig or if SRO determines cannot maintain OW temp. < 280°F then directs the following: (after verifying in safe area of OW spray curve)

Ensures Recirc pumps shutdown

OW blowers secured

Orywell sprays per Appendix-17B ATC Trips Recirc pumps Secures OW blowers BOP Sprays the Orywell with RHR using App-17B

3. VERIFY Recirc Pumps and Orywell Blowers shutdown

HLTS-3-02 Rev 0 Page 36 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/U nsat/Comments BOP 6. INITIATE Drywell Sprays as follows:

VERIFY OPERATING the desired System 1(11)

RHR pump(s) for Drywell Spray.

OPEN the following valves:

3-FCV-74-60(74), RHR SYS 1(11) OW SPRAY OUTBD VLV

3-FCV-74-61 (75), RHR SYS 1(11) OW SPRAY INBO VLV.

VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

IF ............. Additional Drywell Spray flow is necessary, THEN ....... PLACE the second System 1(11) RHR Pump in service.

SRO Directs OW / PSC sprays secured when that area reaches 0 psig BOP Secures sprays if that area reaches 0 psig Monitors containment parameters

HLTS-3-02 Rev 0 Page 37 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/Unsat/Comments SRO Monitors RPV water level, determines level is lowering. Re-enters EOI-1 at +2" RPV level Directs injection with SLC (Boron tank or Test tank) per Appendix-7B ATC Calls for App-7B or starts SLC (If directed to inject from boron tank)

1. IF ..... EOI Appendix 3A is required to be performed, THEN ... EXIT this procedure.

NOTE: SLC Test Tank is preferred source because unborated water may be supplied to the RPV through this injection path

2. IF ..... RPV injection is needed immediately ONLY to prevent or mitigate fuel damage, THEN ... CONTINUE at Step 10 to inject SLC Boron Tank to RPV.

NOTE: Steps 3 through 8 inject demineralized water to the RPV using the SLC Test Tank

3. DISPATCH personnel to Unit 3 SLC pump area to line up SLC Test Tank as follows (RB NE, EI 639 ft)

Monitors OW / PSC pressure & temp and RPV water level

HLTS-3-02 Rev 0 Page 38 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/U nsat/Comments SRO Enters C1 at - -120" CRITICAL TASK Directs ADS inhibited Directs RFP discharge valves closed BOP Inhibits ADS ATC Closes RFP discharge valves Reports 3A CRD pump tripped SRO Directs aligning available systems to inject (containment sprays secured prior to ED at -162")

CRITICAL TASK When RWL reaches -162" but prior to -180", enters C2 and directs six ADS valves open Directs RWL restored to +2" to +51" using Condensate (Appendix-6A), Core Spray (Appendix-60 I 6E), or RHR (Appendix-68 16C)

BOP When directed by SRO, secures containment sprays and align RHR for injection Opens and verifies open six ADS valves SRO Classifies event as SAE (1.1-S1)

ATC Restores RWL to +2' to +51" using App-6A

HLTS-3-02 Rev 0 Page 39 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions SatlUnsatlComments

7. VERIFY at least one condensate pump running

8. VERIFY at least one condensate booster pump running

9. ADJUST 3-LlC-3-53, RFW START-UP LEVEL CONTROL, to control injection (Panel 3-9-5)

10. VERIFY RFW flow to RPV

(

HLTS-3-02 Rev 0 Page 40 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions Sat/U nsat/Comments BOP Injects with CS (App-6D - 6E similar) to maintain RPV water level above -162 when pressure is low enough

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VL V

3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VLV

3-FCV-75-23, CORE SPRAY SYS I OUTBD INJECT VALVE

2. VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALVE

3. VERIFY CS Pump 3A and/or 3C RUNNING

4. WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-25, CORE SPRAY SYS I INBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pump

5. MONITOR Core Spray Pump NPSH using Attachment 1

HLTS-3-02 Rev 0 Page 41 of 44 XI. Simulator Event Guide:

Event #7: MSIV CLOSURE/LOCA Position Expected Actions SatlUnsat/Comments BOP Injects with RHR (App 6C similar) to maintain RPV water level above -162 (If necessary)

4. VERIFY CLOSED the following valves:

3-FCV-74-61, RHR SYS I OW SPRAY INBO VLV

3-FCV-74-60, RHR SYS I OW SPRAY OUTBO VLV

3-FCV-74-57, RHR SYS I SUPPR CHBR/POOL ISOL VLV

3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE

3-FCV-74-59, RHR SYS I SUPPR POOL CLGITEST VL V

5. VERIFY RHR Pump 3A and/or 3C running

(

6. WHEN ...... RPV pressure is below 450 psig, THEN ...... .vERIFY OPEN 3-FCV-74-53, RHR SYS I LPCIINBO INJECT VALVE SRO If needed, directs PSC and/or OW sprays re-established after verifying Cond & CS can maintain level and in the safe area of the spray curve (for OW sprays)

HLTS-3-02 Rev 0 Page 42 of 44 XII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Manually isolate HPCI before 2 areas exceed Maximum Safe Radiation or Temperature levels

2) Inhibits ADS

3) Emergency depressurizes RPV based upon not being able to maintain reactor water level above -162", but before reaching -180"

4) Restores / maintains water level above -162" after ED

HLTS-3-02 Rev 0 Page 43 of 44 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-02 8 Total Malfunctions Inserted: List (4-8)

1) HPCI steam line break

2) Stuck open SRV

3) 3A Recirc. high vibration

4) 3A Recirc pump suction valve fails open and will not close

5) Drywell Leak

6) CRD pump 3B fails to start

7) CRD pump 3A trips

8) RCIC 71-8 fails to open 3 Malfunctions that occur after EOI entry: List (1-4)

1) CRD pump 3B fails to start

2) CRD pump 3A trips

3) RCIC 71-8 fails to open 2 Abnormal Events: List (1-3)

1) SRV fails open

2) HPCI steam line break

( 2 Major Transients: List (1-2)

1) Loss of all high pressure makeup

2) Drywell Leak 3 EOI's used: List (1-3)

1) EOI-1

2) EOI-2

3) EOI-3 2 EOI Contingencies used: List (0-3)

1) C1

2) C2 90 Run Time (minutes) 45 EOI Run Time (minutes): 50 % of Scenario Run Time 4 Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

3-SR-3.5.1.7 was stopped to place RHR in Torus Cooling. 3C RHR pump tripped for unknown reasons and is being investigated by maintenance. Plant management is currently making a Risk Determination regarding continuing 3-SR-3.5.1.7 with 3C RHR Pump INOPERABLE.

T.S 3.5.1.A.1, 3.6.2.3, 3.6.2.4, 3.6.2.5 have been entered. Unit 2 is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months into a seven day LCO. Appendix R LCO addressed and in LCO tracking.

Operations/Maintenance for the Shift:

Unit 3 is at 79% power, Alternate EHC Pumps per section of 0147A. Increase reactor power to

(

85% using Recirc flow (GOI-1 00-12,step 5.132) with no pre-conditioning limitations. Reactor Engineering will evaluate any further power changes. 3-SR-3.5.1. 7 is in progress and is complete up to Step 7.11 (HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure). Loop" RHR has been placed in Torus cooling and 3-SR-3.6.2.1.1 needs to be started 5 minutes before starting HPCI. Plant management will notify the control room regarding continuing 3-SR-3.5.1.7. Units 1 & 2 are at 100% power, Unusual Conditions/Problem Areas:

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Appendix D Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-5 Op-Test Number: HLT 0707 Examiners: Operators:

Initial Conditions: The unit is at 73% power with the 3A CRD Pump in standby and ready for a PMT this shift. 3B CRD pump is in service. 3B RFP is warming after maintenance to the oil system.

Turnover: The Reactor is at 73% Power because Recirc Pump 3A VFD tripped last night due to a logic card failure. Power was being restored when an oil leak developed on the 3B RFP.

Maintenance has completed repairs and the clearance is picked up. The RFP was placed in warming last shift. Plans are to return 3B RFP to service per 3-01-3 section 5.7 and place in Auto, then return reactor power to 100% with control rod withdrawal and Recirc flow per 3-GOI-1 00-12 step 5 [20].

Event Malfunction Event Event Number Number Type* Description 1 none N-ATC Place 3B RFP back in service and increase Rx power N-BOP with control rod withdrawal and Recirc flow increase.

R-SRO 2 imf ed09a C-ATC Loss of 4KV Shutdown Board "3EA" (Bus Lockout) Loss C-BOP causes loss of operating CRD pump, a loss of RPS "N ,

C-SRO a loss of RBCCW, a loss of RWCU, FPC, and a loss of TS-SRO SJAE. ATC will swap CRD pumps and restore RPS power. BOP will restore RBCCW, RWCU, FPC and re-start SJAE. The SRO will address Tech Specs due to multiple component failures 3 none TS-SRO Low oil level is reported on 3B Core Spray pump.

4 imf hp01 C-ATC HPCI inadvertently initiates and injects to the RPV C-BOP without a valid initiation signal. ATC will return FWLC C-SRO from 1-element to 3-element control.

TS-SRO 5 imf tc07 100 R-ATC EHC leak. BOP must lock out EHC pumps and trip C-BOP Main Turbine. ATC reduces power and scrams C-SRO Reactor.

6 bat atws95east M-AII ATWS with fuel failure. SRO and crew respond per EOI-1, EOI-2 and C-5 imfth2320

(N)ormal, (R)eactJvlty, (I)nstrument, (C)omponent, (M)aJor

HL TS-3-05 Rev 0 Page 1 of 58 SIMULATOR EVALUATION GUIDE TITLE: RETURN 3A RFP TO SERVICE FROM WARMING MODE, RETURN POWER TO 100% WITH CONTROL ROD WITHDRAWAL AND RECIRC FLOW INCREASE, LOSS OF 4KV SHUTDOWN BOARD 3EA, LOW OIL LEVEL ON 3B CORE SPRAY PUMP, INADVERTENT HPCIINITIATION AND INJECTION, EHC PUMP LEAK/SCRAM, ATWS/FUEL FAILURE, BPV FAIL CLOSED.

REVISION: 0 DATE: October 08, 2008 PROGRAM: BFN Operator Training - Hot License Have Off-Site power availability SR available.

Provide Crew with RCP and shove & pull sheets for restoring power PREPARED: \

(Operations Instructor) Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HLTS-3-05 Rev 0 Page 2 of 58 Nuclear Training Revision/Usage Log Revision Description of Date Pages Revised Number Changes Affected 0 Initial 10/08/08 All csf

HLTS-3-05 Rev 0 Page 3 of 58 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

RETURN 3A RFP TO SERVICE FROM WARMING MODE, RETURN POWER TO 100% WITH CONTROL ROD WITHDRAWAL AND RECIRC FLOW INCREASE, LOSS OF 4KV SHUTDOWN BOARD 3EA, LOW OIL LEVEL ON 3B CORE SPRAY PUMP, INADVERTENT HPCIINITIATION AND INJECTION, EHC PUMP LEAK/SCRAM, ATWS/FUEL FAILURE, BPV FAIL CLOSED.

IV. Length of Scenario - 1 to 1 Y:z hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment I unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HLTS-3-05 Rev 0 Page 4 of 58 B. Enabling Objectives:

1. The operating crew will return 3B RFP to service.

2. The operating crew will increase Rx power with control rod withdrawal and Recirc flow increase

3. The operating crew will recognize and respond to a low oil level in 3B Core Spray pump.

4. The operating crew will recognize and respond to a Loss of 4KV Shutdown Board 3EA, ( Loss of CRD Pump 3B ).

5. The operating crew will recognize and respond to an inadvertent initiation and injection of the HPCI system.

6. The operating crew will recognize and respond to an un-isolable EHC Leak and manually scram the reactor.

7. The operating crew will recognize and respond to a Hydraulic ATWS and Fuel Failure without bypass valves by inserting control rods and lowering level.

HLTS-3-05 Rev 0 Page 5 of 58 VI.

References:

The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

HLTS-3-05 Rev 0 Page 6 of 58 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat HLTS-3-05 MF/RF/OR# Description

1) bat atws95east ATWS

2) imfth23 (e11:00)204:00 Fuel failure

2. File: bat HLTS-3-05-1 MF/RF/OR# Description 11 I mrf dg01 a open Open 3EA DG logic breaker

2) I mrf dg04a stop locally stop 3EA DG

3. File: bat SGT_Stop MF/RF/OR# Description

1) mrf pc01 a stop Stops A SGT

2) mrf pc01 b stop Stops B SGT

3) mrf pc01 estop Stops C SGT

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HL TS-3-05 Rev 0 Page 7 of 58 VIII. Console Operators Instructions HLTS-3-05 ELAPTIME IC/MF/RF DESCRIPTION/ACTION Sim. Setup IC-26 73% power MOC (Snap 247)

Sim. Setup See Scenario Summary (bat HLTS-3-05)

Sim. Setup manual Verify 3A CRD pump OOS and 3B CRD pump I/S ROLE PLAY: When called to close 3-6-155 and 3-6-156 report that they are closed.

When 3B RFP is returned Loss of 4KV Shutdown Bd. 3EA to Auto and all control rods (imf ed09a) have been withdrawn ROLE PLAY: Plant AUO reports that 4KV Shutdown Board indicates that the feeder breaker Overcurrent flag is up and the bus is locked out.

ROLE PLAY: AUO reports back to the Control Room that the 3A CRD pump is operating normally if requested to by Control Room operators.

If requested to re-start Restart RPS MG set (mrf rp01 reset)

RPS MG set:

If requested to secure Secures A SBGT SBGT Secures B SBGT Secures C SBGT (bat SGT_stop)

If requested to secure Opens logic breaker and shuts down "3EA" DG locally the "3EA" DG (bat HLTS-3-05-1)

If requested to secure Secure "A" CREV (mrf fp05a)

CREV:

If requested to reset ATU Reset ATU gross failures gross failure alarms in Aux (mrf rp09 reset)

Instrument Room:

HLTS-3-05 Rev 0 Page 8 of 58 ELAP TIME DESCRIPTION/ACTION If directed to re-close VFD Re-close VFD Cooling Water Pump cooling water pumps 3A 1 breaker for 3A 1 and 381: (mrfth18a close)

Then: Re-close VFD Cooling Water Pump breaker for 381 (mrfth18b close)

When directed to restart (ior an:ov:xa558b[35] alarm_off)

UPS AC motor generator:

ROLE PLAY: When Fuel Pool Cooling pumps are being re-started, provide completed Appendix A form required by 3-01-78 step 5.1 [7.1]. (attached)

ROLE PLAY: When directed, report FPC FlO BYPASS ISOL VLV A, 3-FCV-078*66 is OPEN.

ROLE PLAY: When directed, report FPC PUMP 3A (3B) DISCH PRESS LOW, 3*PIS*78*

11 (16) indicates >120 psig.

ROLE PLAY: The green lights are illuminated on all 5 of the QLVPS located at bottom of Panel 9*14.

ROLE PLAY: When directed by the Chief Examiner: Call the Unit Operator and report, as the Reactor Building AUO, that you discovered that 3B Core Spray pump oil level is NOT visible in the sight glass.

When directed by Chief Inadvertent HPCI initiation. (imf hp01)

Examiner:

When directed by Chief High pressure EHC leak (imf tcO? 50)

Examiner, Insert EHC Leak

HLTS-3-05 Rev 0 Page 9 of 58 ELAP TIME DESCRIPTION/ACTION ROLE PLAY: AUO sent to respond to the EHC leak reports that a weld has blown out on the common discharge piping of the EHC system. EHC high pressure fluid is spraying on the EHC skid. System isolation is not possible.

When Reactor is Restores SDV hi level alarms (bat SDV) scrammed If requested to perform App. Bypasses scrams and ARI (bat app01f) 1F and 2, wait 5 minutes (bat app02)

When scram is reset Deletes ATWS (bat atws-1 )

If requested to close 3 Closes 3-85-586 (mrf rd06 close) 586, wait 5 minutes ROLE PLAY: AUO Reports that the 3-85-586 is closed If requested to perform Bypasses low level interlocks on MSIVs, App. 8A,E, wait 2 minutes Reactor Bldg. Ventilation (bat app08ae)

(make sure an actual group 6 exists before inserting)

If requested to open Opens 3-85-586 (mrf rd06 open) 3-85-586 then:

ROLE PLAY: AUO Reports that the 3-85-586 is open Terminates the scenario when the following conditions are satisfied or upon request of Lead Evaluator:

1. All rods are inserted.

2. Water level has been restored + 2" to + 51" with feedwater.

3 A cooldown has begun.

HLTS-3-05 Rev 0 Page 10 of 58 IX. Scenario Summary:

The unit is at 73% power with the 3A CRD Pump in standby and ready for a PMT this shift. The crew will return 3B RFP to service and increase power with a combination of control rod withdrawal and recirc flow increase.

The crew will experience a trip of the normal feeder breaker to the "3EA" 4KV Shutdown Board (Bus lockout). The 3B CRD Pump will trip and 3A CRD pump will be placed in-service.

The 4KV bus lockout will also result in a loss of the following equipment:

RPS Bus "A" RBCCW pump 3A and closure of 70-48 RWCU isolation due to loss of RBCCW flow Fuel Pool Cooling pump 3A trip SJAE "A" trip Recirc VFD Cooling water pumps The crew will respond to a report of low oil in the 3B Core Spray pump.

The Crew will respond to an inadvertent initiation and injection of HPCI without a valid initiation signal. The SRO will address actions required by Technical Specifications.

An EHC high pressure leak will require the crew to manually scram the reactor. An ATWS and subsequent fuel failure also occur. Turbine Bypass Valve accumulators bleed down and cause the Bypass Valves to close.

The crew will control RPV pressure using alternate pressure control systems.

The crew will lower RPV level and control level between - 50" and TAF using feedwater and condensate.

HLTS-3-05 Rev 0 Page 11 of 58

x. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. US: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. All rods inserted

2. Water level restored +2" - +51" with feed water.

3. Cooldown started on SRVs and/or alternate pressure control systems

HLTS-3-05 Rev 0 Page 12 of 58 XI. Simulator Event Guide:

Event #1: Place 38 RFP back in service and increase Rx power with control rod withdrawal and Recirc flow increase.

Position Expected Actions Sat/UnsatlComments SRO Directs placing 3B RFP back in service per 3-01-3 section 5.7 BOP Places 38 RFP back in service in accordance with 3-01-3 section 5.7

[2] VERIFY RFP 3B MIN FLOW VALVE, 3-HS-3-13, in OPEN position.

CHECK OPEN MIN FLOW VALVE, 3-FCV-3-20(13)(6)

[3] SLOWLY RAISE speed of RFPT using RFPT 3B SPEED CONT RAISE/LOWER, 3-HS-46-9A, to establish flow and maintain level in vessel

[4] WHEN RFPT discharge pressure is within 250 psig of reactor pressure, THEN VERIFY OPEN RFP 38 DISCHARGE VALVE, 3-FCV-3-12.

[5] SLOWLY RAISE RFPT speed using RFPT 38 SPEED CONT RAISE/LOWER switch, 3-HS 9A, to slowly raise RFP discharge pressure and flow on the following indications (Panel 3-9-6):

RFP Discharge Pressure - RFP 3B, 3-PI-3-9A

RFP Discharge Flow - RFP 3B, 3-FI-3-13

HLTS-3-05 Rev 0 Page 13 of 58 XI. Simulator Event Guide:

Event #1 : Place 3B RFP back in service and increase Rx power with control rod withdrawal and Recirc flow increase.

Position Expected Actions SatlUnsat/Comments BOP [6] WHEN sufficient flow is established to maintain RFP 3B MIN FLOW VALVE, 3-FCV-3-16, in CLOSED position (approximately 2 x 106Ibm/hr),

THEN PLACE RFP 3B MIN FLOW VALVE, 3-HS-3-13, in AUTO.

[7] OBSERVE lowering in speed and discharge flows of other operating RFPs.

[8] IF transferring RFPT from MANUAL GOVERNOR to individual RFPT Speed Control PDS, THEN PERFORM the following: (Otherwise N/A)

[8.1] PULL RFPT 3B SPEED CONT RAISE/LOWER switch, 3-HS-46-9A, to

( FEEDWATER CONTROL position.

[8.2] VERIFY amber light at switch extinguished above RFPT 3B SPEED CONT RAISE/LOWER switch,3-HS-46-9A.

[8.3] PERFORM the following on RFPT 3B SPEED CONTROL(PDS), 3-SIC-46-9 (Panel 3-9-5):

[8.3.1] SELECT Column 3.

[8.3.2] VERIFY PDS in MANUAL.

[9] IF transferring control of RFPT from individual RFPT Speed Control PDS to "AUTO" control using REACTOR WATER LEVEL CONTROL PDS, 3-LlC-46-5, THEN PERFORM the following:

(Otherwise N/A)

HLTS-3-05 Rev 0 Page 14 of 58 XI. Simulator Event Guide:

Event #1 : Place 38 RFP back in service and increase Rx power with control rod withdrawal and Recirc flow increase.

Position Expected Actions SatlUnsatlComments BOP [9.1] VERIFY REACTOR WATER LEVEL CONTROL (PDS), 3-LlC-46-5 is functioning properly and ready to control third RFP.

[9.2] SLOWLY RAISE RFP discharge flow and pressure by raising RFP speed.

[9.3] WHEN RFP speed is approximately equal to operating RFP(s) speed, THEN PERFORM the following on RFPT 3B SPEED CONTROL (PDS), 3-SIC-46-9:

[9.3.1] PLACE PDS in AUTO.

[9.3.2] VERIFY Column 3 selected.

[10] WHEN RFP in automatic mode on REACTOR WATER LEVEL CONTROL, (PDS) 3-LlC-46-5, THEN CLOSE the following valves:

RFPT 38 LP STOP VLV ABOVE SEAT DR,3-FCV-6-125

RFPT 38 LP STOP VL V BELOW SEAT DR,3-FCV-6-126

RFPT 38 HP STOP VLV ABOVE SEAT DR,3-FCV-6-127

RFPT 38 HP STOP VLV BELOW SEAT DR,3-FCV-6-128

RFPT 38 FIRST STAGE DRAIN VLV, 3-FCV-6-129 Calls AUO to close 3-6-155 and 3-6-156 ATC Performs peer check of RFP return to service

HLTS-3-05 Rev 0 Page 15 of 58 XI. Simulator Event Guide:

Event #1: Place 38 RFP back in service and increase Rx power with control rod withdrawal and Recirc flow increase.

Position Expected Actions Sat/U nsat/Comments SRO Directs power increase per the RCP and 3-GOI-100-12 Notifies ODS of impending power increase ATC Increases Rx power with control rod withdrawal When all remaining control rods are withdrawn, commences Recirc flow increase at the PC rate.

Event Terminus: 38 RFP returned to service and all remaining control rods have been withdrawn.

(

HLTS-3-05 Rev 0 Page 16 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions SatlU nsatlComments CREW Identifies/Reports a loss of 4KV SID Board "3EA" BOP Recognizes 3EA DIG starts and fails to load Attempts to load DG by placing 0-HS-211-A-22A in close and recognizes failure to close ATC Recognizes and announces "A" RPS % scram Recognizes and announces 3B CRD pump trip Crew Identifies loss of power to RHR 3A, CS 3A, and RHRSWA3 Identifies loss of power to 3A RBCCW pump and closure of 70-48 sectionalizing valve Identifies loss of operating SJAE.

Identifies RWCU pumps tripped due to NRHX high temperature.

Identifies loss of Fuel Pool Cooling Pump 3A.

BOP Dispatches AUO to 4KV SO Bd 3EA SRO Directs 3EA DIG shutdown per 3-01-82 and AUO to monitor while running Directs 480 VAC Shutdown board 3A transfer to alternate per 01-57B Directs "A" RPS restored Contacts Electrical Maintenance to trouble shoot the 4KV SO Bd

HLTS-3-05 Rev 0 Page 17 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/UnsatlComments SRO Directs placing 3A CRD pump in service per 3-AOI- 85-3 ATC Immediate Actions

[1] IF operating CRD PUMP has TRIPPED AND STANDBY CRD PUMP is AVAILABLE, THEN (Otherwise N/A) PERFORM the following at Panel 3-9-5:

[1.1] PLACE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, in MAN at minimum setting.

[1.2] START associated standby CRD Pump using one of the following:

CRD PUMP 3B, using 3-HS-85-2A

CRD Pump 3A, using 3-HS-85-1A

[1.3] ADJUST CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, to establish the

( following conditions:

CRD CLG WTR HDR DP, 3-PDI 18A, approximately 20 psid.

CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, between 40 and 65 gpm.

[1.4] BALANCE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, and PLACE in AUTO or BALANCE.

SRO Enters T.S. LCO 3.8.7 and declares "A" DG INOP (3.8.1) 7 days Declares 'A' Shutdown Board INOP (5 days)

Enters Appendix R LCO for DG and SID board Directs power availability SR performed Direct Unit 1 UO to perform ILL-3 of 0-01-57B

HLTS-3-05 Rev 0 Page 18 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/U nsat/Comments BOP Restores SJAE per 3-01-66 section 8.14

[1] IF determined necessary by Unit Supervisor, THEN (Otherwise N/A) BEFORE Standby SJAE in service on nuclear steam, PERFORM the following:

[1.1] NOTIFY Radiation Protection that an RPHP exist for the impending action to place the SJAE (3A or 3B) in service.

RECORD time Radiation Protection notified in the NOMS Narrative Log. [BFN PER 126211

[1 .2] VERIFY appropriate data and signatures recorded on Appendix A in accordance with Appendix A Instructions

[Tech Spec 5.7, SOER 01-1, BFN PER 126211]

SRO Determines RPHP is not required to return the same SJAE to service BOP [2] PLACE SJAE TRAIN PERMISSIVE 3-HS-001-0375 in the position for the SJAE being placed in service. This switch will normally be in the position of the standby SJAE.

[3] VERIFY RESET off-gas isolation using OG OUTLET/DRAIN ISOLATION VLVS, 3-HS-90-155 on Panel 3-9-8.

[4] VERIFY OPEN the following valves.

SJAE 3A(3B) INLET VALVE, 3-HS 11 (15), Panel 3-9-8

STEAM TO SJAE 3A(3B), 3-HS 155A(156A). Panel 3-9-7

HLTS-3-05 Rev 0 Page 19 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/Unsat/Comments BOP [5] VERIFY in AUTO/OPEN the following valve:

SJAE 3A(3B) OG OUTLET VALVE, 3-HS-66-14( 18). Panel 3-9-8

[6] PLACE SJAE 3A(3B) PRESS CONTROLLER 3-HS-1-150(152) in CLOSE, and THEN in OPEN.

Panel 3-9-7

[7] VERIFY the following valves open. Panel 3-9-7

STEAM TO SJAE 3A(3B) STAGES 1,2, AND 3, 3-PCV-1-151/166 (153/167)

SJAE 3A(3B) INTMD CONDENSER DRAIN 3-FCV-1-150(152)

[8] MONITOR hotwell pressure as indicated on HOTWELL TEMP AND PRESS recorder, 3-XR 2, Panel 3-9-6.

[9] For the SJAE NOT being placed in service,

VERIFY CLOSED SJAE 3B(3A) OG OUTLET VALVE, 3-HS-66-18(14). Panel 3-9-8

VERIFY CLOSED SJAE 3B(3A)

PRESSURE CONTROLLER 3-HS 152(150)

[10] VERIFY SJAE TRAIN PERMISSIVE 3-HS-001-0375 in the position for the SJAE selected for Standby operation SJAE B.

[11] After stable SJAE operation has been confirmed, REFER TO 3-01-4, HWC System for shut down and restart guidance if the HWC System had previously been in service.

(otherwise N/A)

HLTS-3-05 Rev 0 Page 20 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions SatlUnsat/Comments SRO Directs SBGT and Ventilation restored to normal after BOP transfers 3A SID bd to alt and restores RPS ATC Restoration to normal following RPS Bus Power Loss per 3-01-99 section 8.3

[1] OBTAIN Shift Manager's permission to restore to normal.

[2] MOMENTARILY PLACE SCRAM RESET, 3-HS-99-5A1S5, as follows:

A. RESET FIRST B. RESET SECOND C. NORMAL

[3] CHECK the following conditions:

(

A. All eight SCRAM SOLENOID GROUP AlB LOGIC RESET lights illuminated.

B. The following four lights illuminated:

SYSTEM A BACKUP SCRAM VALVE,3-IL-99-5A1AB

SYSTEM B BACKUP SCRAM VALVE,3-IL-99-5A1CD C. Scram Discharge Volume vent and drain valves indicate open.

D. Points SOE033 and SOE035 on ICS computer or on the First Out Printer reads "NOT TRIP" for RPS "A".

E. Points SOE034 and SOE036 on ICS computer or on the First Out Printer reads "NOT TRIP" for RPS "B".

HLTS-3-05 Rev 0 Page 21 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/UnsatlComments ATC [4] At Panel 3-9-4, RESET PCIS trip logic as follows:

[4.1] MOMENTARILY PLACE PCIS DIV I RESET, 3-HS-64-16A-S32, to left and right RESET positions.

[4.2] CHECK the following red lights illuminated:

MSIV GROUP A1, 3-IL-64-A1

MSIV GROUP B1, 3-IL-64-B1

[4.3] MOMENTARILY PLACE PCIS DIV" RESET, 3-HS-64-16A-S33, to left and right RESET positions.

[4.4] CHECK the following red lights illuminated:

MSIV GROUP A2, 3-IL-64-A2

MSIV GROUP B2, 3-IL-64-B2 NOTE: Steps 8.3[5] through 8.3[22] can be performed in any order.

BOP [5] CHECK the green lights are illuminated on all 5 of the QLVPS located at bottom of Panel 9-14. (pnl 9-14 not on U3 simulator)

HLTS-3-05 Rev 0 Page 22 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/U nsat/Comments BOP [6] RESTORE Reactor and Refuel Zone Ventilation to normal operation. REFER TO 3-AOI-64-2D, Group 6 Ventilation System Isolation.

Subsequent Actions

[1] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s). (Otherwise N/A)

[2] VERIFY Group 6 isolation valves penetrating Primary Containment are closed.

UTILIZE Panel 3-9-3 mimic or Containment Isolation Status System on Panel 3-9-4.

[4] VERIFY STEAM VAULT EXH BOOSTER FAN in service. REFER TO 3-01-30B.

(has AUO check fan I/S)

HLTS-3-05 Rev 0 Page 23 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions SatlU nsatlComments

[13] WHEN initiating signal has been corrected AND necessary repairs are made, THEN

[13.1] VERIFY PCIS RESET:

RESET PCIS DIV I RESET, 3-HS-64-16A-S32.

RESET PCIS DIV" RESET, 3-HS-64-16A-S33

[13.2] RESET Reactor/Refuel isolation logic, as required:

PLACE REFUEL ZONE FANS AND DMPRS, 3-HS-64-3A, in OFF. (N/A if previously performed.)

PLACE REACTOR ZONE FANS AND DMPRS, 3-HS-64-11A, in OFF.

[13.3] START Reactor/Refuel zone ventilation, as required:

PLACE REACTOR ZONE FANS AND DAMPERS switch, 3-HS-64-11A, in SLOW A (SLOW 8).

PLACE REFUEL ZONE FANS AND DAMPERS Switch, 3-HS-64-3A, in SLOW 3A (SLOW 38).

HLTS-3-05 Rev 0 Page 24 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions SatlUnsatlComments BOP [13.4] For the fans started, VERIFY that the dampers open and fans start as indicated by illuminated red lights above the following switches:

The two green lights A(B) above REACTOR ZONE FANS AND DAMPERS Switch 3-HS-64-11A, extinguish and the two red lights A(B) illuminate.

The two green lights A(B) above REFUEL ZONE FANS AND DAMPERS Switch 3-HS-64-3A, extinguish and the two red lights A(B) illuminate.

REACTOR ZONE SPLY OUTBD ISOL DMPR,3-HS-64-13

REACTOR ZONE SPL Y INBD ISOL DMPR,3-HS-64-14

REACTOR ZONE EXH INBD ISOL DMPR, 3-HS-64-42

REACTOR ZONE EXH OUTBD ISOL DMPR, 3-HS-64-43

REFUEL ZONE SPLY OUTBD ISOL DMPR, 3-HS-64-5

REFUEL ZONE SPLY INBD ISOL DMPR, 3-HS-64-6

REFUEL ZONE EXH OUTBD ISOL DMPR,3-HS-64-9

REFUEL ZONE EXH INBD ISOL DMPR, 3-HS-64-10

HLTS-3-05 Rev 0 Page 25 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/U nsat/Comments

[7] RESTORE Standby Gas Treatment System to standby readiness. REFER TO 0-01-65.

Contacts Unit 1 UO to secure SBGT

[8] At Panel 3-9-3, PLACE PSC head tank pumps in service as follows:

PLACE SUPPR POOL DRAIN INBD ISOL VALVE, 3-HS-75-57A, in AUTO After OPEN.

PLACE SUPPR POOL DRAIN OUTBD ISOL VALVE, 3-HS-75-58A, in AUTO After OPEN.

HLTS-3-05 Rev 0 Page 26 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions SatlUnsatlComments BOP [10] At Panel 3-9-3, RESTORE Drywell DP Compressor to automatic operation as follows:

[10.1] DEPRESS DRYWELL DP CPRSR SUCT VL V RESET pushbutton, 3-HS 139A.

[10.2] DEPRESS DRYWELL DP CPRSR DISCH VLV RESET pushbutton, 3-HS 140A.

[10.3] VERIFY OPEN DW TO SGT INBD ISOL VALVE using 3-HS-64-31.

[10.4] VERIFY OPEN SUPPR CHBR SGT INBD ISOL VALVE using 3-HS-64-34.

[11] At Panel 3-9-4, RESTORE Drywell Floor and Equipment Drain Systems to normal operation as follows:

(

[11.1] NOTIFY Radwaste Operator that Drywell Equipment and Floor Drain Sump isolation valves are being reopened. DO

[11.2] PLACE DRYWELL EQPT DR INBD ISOL VLV, 3-HS-77-15A, in AUTO After OPEN.

[11.3] PLACE DRYWELL EQPT DR OUTBD ISOL VLV, 3-HS-77-15B, in AUTO After OPEN.

[11.4] PLACE DRYWELL FLOOR DR INBD ISOL VLV, 3-HS-77-2A, in AUTO After OPEN.

[11.5] PLACE DRYWELL FLOOR DR OUTBD ISOL VLV, 3-HS-77-2B, in AUTO After OPEN.

HLTS-3-05 Rev 0 Page 27 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions SatlUnsatlComments BOP [12] At Panel 3-9-2, RESTORE Radiation Monitoring System as follows:

[12.1] DEPRESS RESET pushbutton.

[12.2] VERIFY OPEN the associated valve.

[12.3] RELEASE pushbutton.

OW RAO MON UPPER INBO SUPPLY ISV RESET, 3-HS-90-254A-A (opens FCV-90-254A)

OW RAO MON LOWER INBO SUPPLY ISV RESET, 3-HS-90-254B-A (opens FCV-90-254B)

OW RAO MON OUTBO RETURN ISV RESET, 3-HS-90-257A-A (opens FCV-90-257A)

OW RAO MON OUTBO SUPPLY ISV RESET, 3-HS-90-255A (opens FCV-90-255)

OW RAO MON INBO RETURN ISV RESET, 3-HS-90-257B-A (opens FCV-90-257B)

[13] At Panel 3-9-54, RESTORE H2/02 Analyzer A as follows:

[13.1] DEPRESS ANALYZER A SAMPLE VALVES RESET pushbutton, 3-HS-76-91.

[13.2] IF H2/02 Analyzer 3A was in service, THEN (Otherwise N/A) PULL ANO RELEASE ANAL YZER A SAMPLE SOURCE SELECTOR, 3-HS-76-49.

[14] At Panel 3-9-55, RESTORE H2/o2 Analyzer B as follows:

[14.1] DEPRESS ANALYZER B SAMPLE VALVES RESET pushbutton, 3-HS-76-92.

[14.2] IF H2/02 Analyzer 3B was in service, THEN (Otherwise N/A) PULL ANO RELEASE ANALYZER B Sample Source SELECTOR, 3-HS-76-59.

HLTS-3-05 Rev 0 Page 28 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions SatlUnsatlComments BOP [15] At Panel 3-9-55, VERIFY DRYWELL OR SUPPRESSION CHAMBER EXHAUST TO SGTS, 3-FIC-84-20, in AUTO with setpoint at 100 scfm.

ATC [16] RESTORE Reactor Water Cleanup System to normal operation. REFER TO 3-01-69. (N/A if Section 8.6 performed) 3-01-69 section 5.1

[3] VERIFY RESET the RWCU Group 3 isolation using PCIS DIV I RESET, 3-HS-64-16A-S32 and PCIS DIV II RESET, 3-HS-64-16A-S33 at Panel 3-9-4.

[5] VERIFY RWCU HEAT EXCHANGERS RBCCW FLOW CONTROL, 3-TIC-069-0010A is in MANUAL, and FULL OPEN demand is on 3-TCV-70-49. (REFER TO Illustration 5)[BFPER 03-000348-000]

[6] VERIFY CLOSED the following:

RWCU BLOWDOWN PRESS CONTROL VLV, using 3-HC-69-15

RWCU BLOWDOWN TO MAIN CNDR, using 3-HS-69-16A

RWCU BLOWDOWN TO RADWASTE, using 3-HS-69-17 A

HLTS-3-05 Rev 0 Page 29 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions SatlU nsatlComments

[8] NOTIFY chemistry RWCU is being placed in service and to check the durability monitor.

[9] VERIFY OPEN the following valves:

RWCU INBD SUCT ISOLATION VALVE, 3-FCV-69-1

RWCU OUTBD SUCT ISOLATION VALVE,3-FCV-69-2

RWCU DEMIN BYPASS VALVE, 3-FCV-69-8

[10] OPEN 3-FCV-069-0012 by one of the two methods described below.

PLACE 3-HS-69-12A in the OPEN position, THEN RETURN 3-HS-69-12A to the NORM position when intermediate position (red and green light) is indicated.

PLACE 3-HS-69-12A in the OPEN position, THEN RETURN 3-HS-69-12A to the NORM position when FULL OPEN position (red light only) is indicated.

HLTS-3-05 Rev 0 Page 30 of 58 XI. Simulator Event Guide:

(

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/Unsat/Comments ATC [11] PLACE seal purge in operation to pump(s) to be placed in service. REFER TO Section 8.2.

[12] START RWCU RECIRC PUMP 3A(3B) using control switch 3-HS-69-4A(4B)-A, and A RISE flow, using RWCU RETURN ISOLATION VALVE, 3-HS-69-12A, to prevent low flow trip.

[13] IF two pump operation is desired, THEN START the second RWCU RECIRC PUMP 3B(3A) using control switch 3-HS-69-4B(4A)-A, and A RISE flow using RWCU RETURN ISOLATION VALVE, 3-HS-69-12A, to prevent low flow trip.

[14] IF the RWCU filter-demineralizers is to be placed in service, THEN REFER TO Section 6.2.

Coordinates with AUO to place RWCU demins in service BOP 3-01-70 Contacts U 1 UO to place spare RBCCW pump in service to U3.

Reopens 3-FCV-70-48 when notified Spare RBCCW aligned to U3.

HLTS-3-05 Rev 0 Page 31 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/U nsat/Com ments BOP 5.1.4 IF required to use FPC Pump A(B) with Heat Exchanger B(A), THEN PERFORM the following:

5.1.4.1 VERIFY OPEN FPC HX 3B(3A)

INLET, 3-SHV-078-0505(0506).

5.1.4.2 VERIFY OPEN FPC HX 3B(3A)

OUTLET, 3-SHV-078-051 0(0511).

5.1.4.3 OPEN FPC PMP 3A&3B DISCH CROSSTIE,3-SHV-078-0507.

5.1.4.4 VERIFY CLOSED FPC HX 3A(3B)

OUTLET, 3-SHV-078-0511 (0510).

5.1.5 VERIFY FPC FlO C(D) EFFL FLOW recorder controller, 3(0)-FRC-078-0024, in MANUAL and SET at 0%.

5.1.6 START the FUEL POOL COOLING PUMP 3A(3B) using handswitch 3-HS-78-1 OA(15A), on

( Panel 3-9-4.

5.1.7 OPEN FPC FlO BYPASS ISOL VLV A(B), 3-FCV-078-0066(0065), using handswitch 3-HS-078-0066B(00658) (EI. 621, R18-S Line.

5.1.8 VERIFY pump started in Step 5.1.5 has a discharge pressure >120 psig as indicated on FPC PUMP 3A(3B) DISCH PRESS LOW, 3-PIS-078-0011 (0016) on 3-LPNL-925-0016.

HLTS-3-05 Rev 0 Page 32 of 58 XI. Simulator Event Guide:

Event #2: Loss of 4KV Shutdown Board "3EA" Position Expected Actions Sat/Unsat/Comments BOP 5.1.11 THROTTLE FPC HX A(B) CLG WTR OUTLET, 3-70-599A(B), REFER TO 3-01-70 to maintain Fuel Pool temperature less than or equal to 125°F as indicated on RHR/FUEL POOL CLG TEMPERATURE, 3-TR-74-80, (Points No. 19(20) & 21) on Panel 3-9-21.

5.1.12 IF available, THEN PLACE filter-demineralizer in service per Section 5.2.

Coordinates with Radwaste UO and AUO in plant to place FPC demin back in service.

ATC Directs AUO to shutdown DG "3EA" per 01-82 and leave the logic breaker open Event Terminus: Tech. Specs addressed and systems returned to normal

(

HLTS-3-05 Rev 0 Page 33 of 58 XI. Simulator Event Guide:

Event #3: Low Oil Level on 38 Core Spray pump Position Expected Actions SatlUnsatlComments SRO Recognizes Tech Spec operability issue with low oil level on 38 Core Spray pump.

Addresses Tech Spec section 3.5.1.H.1 and determines that 3.0.3 must be entered immediately.

Initiates a Priority 1 Work Order to restore 38 Core Spray pump oil level.

Recognize that a 4-hour report to the NRC is required due to a Tech Spec required shutdown.

Directs ATC to halt power ascension.

Event Terminus: Tech Spec evaluation complete and Priority 1 WO issued to restore 38 Core Spray pump oil level.

HLTS-3-05 Rev 0 Page 34 of 58 XI. Simulator Event Guide:

Event #4: Inadvertent HPCI initiation without a valid signal Position Expected Actions Sat/Unsat/Comments BOP Recognizes and responds to an inadvertent HPCI initiation and reports it to the SRO.

Verifies by multiple indications that the initiation signal is not valid and reports it to the SRO.

SRO Directs BOP to trip HPCI and place the Aux Oil Pump in Pull-to-Lock.

BOP Trips HPCI and places the Aux Oil Pump in Pull-to-Lock (after turbine stops).

ATC Reports power / level! pressure stable after HPCI secured Reports FWLC system transferred from 3-element control to single-element control SRO Addresses Tech Spec section 3.5.1.D and determines that HPCI must be returned to service in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months with 3A RHR and 3A Core Spray INOPERABLE.

Directs Instrument Mechanics to investigate the HPCI initiation logic.

Gives brief stating HPCI is INOP but still available for injection, if needed Directs placing FWLS system back in 3-element control per 3-01-3 section 8.27

HL TS-3-05 Rev 0 Page 35 of 58 XI. Simulator Event Guide:

Event #4: Inadvertent HPCI initiation without a valid signal Position Expected Actions SatlUnsatlComments ATC Places FWLC system back in 3-element control per 3-01-3

[1] IF desired to transfer level control from Single Element to Three Element, THEN PERFORM the following: (Otherwise N/A)

[1.1] VERIFY conditions in Note 2 are met for placing level control in Three Element.

[1.2] OBSERVE stable steam flow and Feedwater flow.

[1.3] DEPRESS THREE ELEMENT push-button, 3-HS-46-6/3.

VERIFY green backlight for push-button illuminates.

[1.4] VERIFY extinguished green backlight for SINGLE ELEMENT push-button, 3-HS-46-6/1.

[1.5] CHECK Reactor water level stable.

Reports to US that FWLC placed back in 3-element control.

Event Terminus: Tech Spec evaluation complete and HPCI stopped (Locked out). Also, FWLC system returned to 3-element control (if noticed)

HL TS-3-05 Rev 0 Page 36 of 58 i XI. Simulator Event Guide:

l Event #5: EHC LEAK / SCRAM Position Expected Actions SatlU nsat/Com ments BOP Recognizes and reports "EHC Reservoir Level Low" Alarm Responds per ARP 3-XA-55-7B window 9 A. IMMEDIATELY DEDICATE a Licensed Operator to continuously monitor the operating EHC pump's amperage and pressure for fluctuations and continue with this procedure.

SRO Directs an Operator to continuously monitor the operating EHC pump's amperage and pressure for fluctuations BOP B. IF, while performing this procedure, OR during the EHC reservoir level low transient, the operating pump's amperage or pressure begins to fluctuate (indicative of pump cavitation), THEN IMMEDIATELY:

1. INITIATE Reactor Scram

2. VERIFY main turbine trip

3. TRIP AND LOCK OUT the EHC pumps C. DISPATCH personnel to verify level on local gauge.

D. ADD fluid. REFER TO 3-01-47A, Section 8.1.

E. INITIATE search for cause of low level such as leaking servo, leaking line, open valve, etc.

F. NOTIFY Radwaste to LOCKOUT all 3 Units' Turbine Bldg Equipment and Floor drain Sump Pumps.

HLTS-3-05 Rev 0 Page 37 of 58 XI. Simulator Event Guide:

Event #5: EHC LEAK I SCRAM Position Expected Actions SatlU nsat/Com ments BOP Reports low EHC pressure Responds per ARP 3-XA-55-7B window 9 A. VERIFY Standby EHC PUMP 3B(3A), 3-HS-4 7-2A(1A) running.

S. CHECK EHC HEADER PRESSURE, pressure indicator, 3-PI-47-7 between 1550 and 1650 psig.

C. DISPATCH personnel to inspect EHC pump unit.

D. IF EHC Hydraulic system fails, THEN VERIFY turbine trips at or below 1100 psig.

SRO Directs ATC to insert a manual Scram and enter 3-AOI-100-1 (may direct Core Flow runback, if time permits.)

Directs BOP to trip turbine and lockout EHC pumps ATC Inserts core flow runback, if directed.

Inserts Manual Scram and takes actions per 3-AOI-100-1 BOP Locks out EHC pumps by placing

3-HS-47-2A in Pull To Lock

3-HS-47-1A in Pull To Lock Event Terminus: Manual scram inserted and EHC pumps locked out

HL TS-3-05 Rev 0 Page 38 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlU nsatlComments ATC Reports all rods not in and performs the following:

Mode Switch to SHUTDOWN

Initiates ARI

Recognizes and reports power is greater than 5% and Recirc Pumps NOT tripped

Inserts SRMs/IRMs

Gives scram report SRO Enters EOI-1 and C5 and directs/ensures the following:

Mode Switch to SHUTDOWN

ARI Initiated (both channels)

Recirc Pumps reduced to minimum and tri ed Directs Appendix-1 F, 2, and 1D be performed Directs Appendix-8A, 8E be performed CRITICAl. TASK #2 Directs Appendix-4 to lower water level until level

< -50" BOP Inhibits ADS Dispatches AUO to perform Appendix-1 F & 2 Dispatches AUO to perform Appendix-8A & E

HLTS-3-05 Rev 0 Page 39 of 58 XI. Simulator Event Guide:

Event #6: ATWSI FUEL FAILURE Position Expected Actions SatiUnsatiComments BOP Performs Appendix-4 on 9-3

a. HPCI

1) IF .............. HPCI Turbine is NOT at zero speed, THEN ........ PRESS and HOLD 3-HS-73-18A, HPCI TURBINE TRIP push-button.

2) WHEN ...... HPCI Turbine is at zero speed, THEN ........ PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK and RELEASE 3-HS 18A, HPCI TURBINE TRIP push-button.

b. RCIC

1) IF .............. DIRECTED by SRO to allow RCIC injection, THEN ........ EXIT step 1.b.

2) PRESS 3-HS-71-9A, RCIC TURBINE

( TRIP push-button to trip RCIC Turbine.

(RCIC not required to be secured)

c. CORE SPRAY NOTE: After receipt of an automatic initiation signal, it is NOT necessary to wait until the pump actually starts before performing the next step.

Following an initiation signal, PLACE ALL Core Spray pump control switches in STOP.

HLTS-3-05 Rev 0 Page 40 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlU nsatlComments BOP d. LPCI SYSTEM I PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM I pump control switches in STOP.

OR

BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL, in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE.

e. LPCI SYSTEM II PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE RHR SYSTEM II pump control switches in STOP.

OR

BEFORE RPV pressure drops below 450 psig,

1) PLACE 3-HS-74-155B, LPCI SYS II OUTBD INJ VLV BYPASS SEL, in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE.

HLTS-3-05 Rev 0 Page 41 of 58 XI. Simulator Event Guide:

Event #6: ATWS / FUEL FAILURE Position Expected Actions Sat/U nsat/Comments ATC Performs Appendix-4 on 9-5/6

f. CONDENSATE and FEEDWATER

1) LOWER RFPT 3A(38)(3C) speed to minimum setting (approximately 600 rpm) using ANY of the following methods on Panel 3-9-5:

Using 3-UC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL AND individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in AUTO, OR

Using individual 3-SIC-46-8(9)(1 0), RFPT 3A(38)(3C) SPEED CONTROL PDS in MANUAL, OR

Using individual 3-HS-46-8A(9A)(10A),

RFPT 3A(38)(3C) SPEED CO NT RAISE/LOWER switch in MANUAL GOVERNOR.

3) TRIP RFPTs as necessary to prevent injection by DEPRESSING the following push-buttons:

3-HS-3-125A, RFPT 3A TRIP

3-HS-3-151A, RFPT 38 TRIP

3-HS-3-176A, RFPT 3C TRIP

HLTS-3-05 Rev 0 Page 42 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlUnsatlComments ATC Performs Apendix-1 0 (when drive water is available - may dispatch AUO to close 85-586 valve)

1. VERIFY at least one CRD pump in service

2. IF ..... Reactor Scram or ARI CANNOT be reset, THEN ... DISPATCH personnel to CLOSE 3-SHV-085-0586, CHARGING WATER SOV (RB NE, EI 565 ft)

3. VERIFY REACTOR MODE SWITCH in SHUTDOWN

4. BYPASS Rod Worth Minimizer

5. REFER to Attachment 2 and INSERT control rods in thearea of highest power as follows:

a. SELECT control rod.

b. PLACE CRD NOTCH OVERRIDE switch in EMERG ROD IN position UNTIL control rod is NOT moving inward.

c. REPEAT Steps 5.a and 5.b for each control rod to be inserted

6. WHEN ... NO further control rod movement is possible or desired, THEN ... DISPATCH personnel to VERIFY OPEN 3-SHV-085-0586, CHARGING WATER SOV (RB NE, EI 565 ft)

HLTS-3-05 Rev 0 Page 43 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlU nsatlComments BOP Recognizes turbine trip and loss of Bypass valves as accumulators depressurize SRO Directs reactor pressure maintained less than 1073 psig with MSRV's Appendix-11A (pressure band 800-1000)

(May direct Alternate pressure control with MSL drains per Appendix-11 0)

BOP Maintains reactor pressure less than 1073 with MSRV's (or pressure band 800-1000 if directed)

3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

(sequence is 1-13)

HL TS-3-05 Rev 0 Page 44 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions Sat/UnsatlComments BOP If directed, performs App-11 D

2. VERIFY hotwell pressure below -7 in. Hg.

3. CONTROL RPV pressure with Main Steam line drains as follows:

a. VERIFY PCIS reset.

b. OPEN the following valves (Panel 3-9-3):

0 3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV 0 3-FCV-1-56, MN STM LINE DRAIN OUTBD ISOLATION VL V 0 3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER

4. THROTTLE 3-FCV-1-59, DOWNSTREAM MSL DRAIN TO CONDENSER, as necessary to control cooldown rate.

HL TS-3-05 Rev 0 Page 45 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions Sat/UnsatlComments BOP 5. IF ..... At least one main steam line is open AND EITHER of the following exist:

0 Turbine bypass valves are NOT available, OR 0 Additional RPV pressure control is necessary, THEN ... CONTROL RPV pressure with Main Turbine and RFPT drains as follows:

a. OPEN the following Main Turbine Drain valves (Panel 3-9-7):

0 3-FCV-6-100, STOP VALVE 1 BEFORE SEAT DR VL V 0 3-FCV-6-101, STOP VALVE 2 BEFORE SEAT DR VL V 0 3-FCV-6-102, STOP VALVE 3 BEFORE SEAT DR VLV 3-FCV-6-103, STOP VALVE 4 BEFORE SEAT DRVLV.

b. OPEN the following RFPT drain valves (Panel 3-9-6):

0 3-FCV-6-122, RFPT 3A HP STOP VLV ABOVE SEAT DR 0 3-FCV-6-127, RFPT 3B HP STOP VLV ABOVE SEAT DR 0 3-FCV-6-132, RFPT 3C HP STOP VLV ABOVE SEAT DR.

HLTS-3-05 Rev 0 Page 46 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions Sat/UnsatlComments BOP Reports Torus temp >95°F and or drywell pressure above 2.45 psig (if applicable)

SRO Enters EOI-2 and directs all available SIP cooling placed in service per Appendix-17 A and directs BOP 1. IF .............. Adequate core cooling is assured, OR Directed to cool the Suppression Pool irrespective of adequate core cooling, THEN ....... BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS 1(11)

OUTBD INJ VLV BYPASS SEL in BYPASS

2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

c. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLETVLV

HLTS-3-05 Rev 0 Page 47 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions Sat/U nsat/Comments BOP d. IF ............. Directed by SRO, THEN ....... PLACE 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD in MANUAL OVERRIDE

e. IF ............. LPCIINITIATION Signal exists, THEN ....... MOMENTARILY PLACE 3-XS 121(129), RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT in SELECT

f. IF ............. 3-FCV-74-53(67), RHR SYS 1(11) LPCI INBD INJECT VALVE, is OPEN, THEN .......

VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11)

LPCI OUTBD INJECT VALVE

g. OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBRIPOOL ISOL VLV

h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating

i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11)

SUPPR POOL CLGITEST VLV, to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR SYS 1(11) FLOW:

Between 7000 and 10000 gpm for one-pump operation.

OR

At or below 13000 gpm for two-pump operation

j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE

k. MONITOR RHR Pump NPSH using Att. 1

m. IF ............. Additional Suppression Pool Cooling flow is necessary, THEN ....... PLACE additional RHR and RHRSW pumps in service using Steps 2.b through 2.1

HLTS-3-05 Rev 0 Page 48 of 58 XI. Simulator Event Guide:

Event #6: ATWS / FUEL FAILURE Position Expected Actions SatlU nsat/Comments BOP Reports TB High Radiation alarm and evacuates appropriate areas Reports OG Pretreatment Rad High Alarm Reports RxB High Radiation alarm and evacuates appropriate areas (contingent)

SRO Enters EOI-3 if Rx bldg Hi Rad alarms Directs venting per Appendix-12 BOP 1. VERIFY at least one SGTS train in service

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE

HLTS-3-05 Rev 0 Page 49 of 58 XI. Simulator Event Guide:

(

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlUnsatlComments NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CONT, OR

3-FIC-84-20, PATH A VENT FLOW CONT NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented

6. IF '" ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR

Suppression Chamber can NOT be vented, OR

SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:

Step 10 to vent the Drywell through 3-FCV-84-19, OR

Step 11 to vent the Drywell through 3-FCV-84-20

HLTS-3-05 Rev 0 Page 50 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlUnsat/Comments BOP 7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20 I

8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3 54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3 55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12

HLTS-3-05 Rev 0 Page 51 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlU nsatlComments BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND MAINTAIN release rates below O-SI-4.8.B.1.a.1 release fraction of 1 Directs Control Bay AUO to monitor release rates

HLTS-3-05 Rev 0 Page 52 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions Sat/U nsat/Comments SRO Directs SLC Injection before Torus Temperature reaches 110 of per Appendix-3A ATC Injects SLC per Appendix-3A (if directed)

1. UNLOCK and PLACE 3-HS-63-6A, SLC PUMP 3A/3B, control switch in START PUMP 3A or START PUMP 3B position

2. CHECK SLC System for injection by observing the following:

Selected pump starts, as indicated by red light illuminated above pump control switch.

Squib valves fire, as indicated by SQUIB VALVE A and B CONTINUITY blue lights extinguished,

SLC SQUIB VALVE CONTINUITY LOST Annunciator in alarm on Panel 3-9-5 (3-XA-55-5B, Window 20).

3-PI-63-7A, SLC PUMP DISCH PRESS, indicates above RPV pressure.

System flow, as indicated by 3-IL-63-11, SLC FLOW, red light illuminated on Panel 3-9-5,

SLC INJECTION FLOW TO REACTOR Annunciator in alarm on Panel 3-9-5 (3-XA-55-5B, Window 14)

3. IF ..... Proper system operation CANNOT be verified, THEN ... RETURN to Step 1 and START other SLC pump

HLTS-3-05 Rev 0 Page 53 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlUnsatlComments ATC 4. VERIFY RWCU isolation by observing the following:

RWCU Pumps 3A and 3B tripped

3-FCV-69-1, RWCU INBD SUCT ISOLATION VALVE closed

3-FCV-69-2, RWCU OUTBD SUCT ISOLATION VALVE closed

3-FCV-69-12, RWCU RETURN ISOLATION VALVE closed

5. VERIFY ADS inhibited

6. MONITOR reactor power for downward trend

7. MONITOR 3-Ll-63-1A, SLC STORAGE TANK LEVEL, and CHECK that level is dropping approximately 1% per minute

8. WHEN .. , EITHER of the following exists:

SLC tank level drops to 0%,

OR

As directed by SRO, THEN ... STOP SLC Pump 3A or 3B

HLTS-3-05 Rev 0 Page 54 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlU nsatlCom ments BOP Recognizes and Reports the Reactor Building Area Radiation monitors are in alarm and Rad levels in the Rx Building are increasing.

SRO Orders evacuation of the Reactor Building, Notifies Rad Con, Ensures announcements are made.

Enters EOI-3 on Rx Bldg Hi rad ATC When Appendix-2 and the outside portions of Appendix-1 F are complete;

2. WHEN ... RPS Logic has been defeated, THEN ... RESET Reactor Scram

3. VERIFY OPEN Scram Discharge Volume vent and drain valves

4. DRAIN SDV UNTIL the following annunciators clear on Panel 3-9-4:

WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM (3-XA-55-4A, Window 1)

EAST CRD DISCH VOL WTR LVL HIGH HALF SCRAM (3-XA-55-4A, Window 29)

5. DISPATCH personnel to VERIFY OPEN 3-SHV-085-0586, CHARGING WATER SOV

HLTS-3-05 Rev 0 Page 55 of 58 XI. Simulator Event Guide:

Event #6: ATWS I FUEL FAILURE Position Expected Actions SatlUnsatlComments ATC 6. WHEN ... CRD Accumulators are recharged, THEN ... INITIATE manual Reactor Scram and ARI

7. CONTINUE to perform Steps 1 through 6 UNTIL ANY of the following exists:

ALL control rods are inserted to or beyond position 02, OR

NO inward movement of control rods is observed, OR

SRO directs otherwise Verifies rod motion and reports that all control rods are fully inserted SRO Exits EOI-1, RC/Q after rods are inserted or SLC tank level is <43%.

Directs termination of SLC injection if the system was initiated Directs RPV level restored and maintained + 2" to

+ 51" RWL ATC/BOP Maintains RPV level within band as directed by SRO SRO Declares a Site Area Emergency per EPIP-1 EAL 1.2-S Event Terminus: All rods inserted and water level restored to +2" to +51"

HLTS-3-05 Rev 0 Page 56 of 58 XII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Inhibits ADS

2) Control power by one or more of the following:

- Lowers RWL to <-50" per C-5

- Insert control rods per RC/Q

3) Inject SLC prior to exceeding 110 uF Torus temperature per RC/Q. (Contingent)

HL TS-3-05 Rev 0 Page 57 of 58 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HL TS-3-05

~ Total Malfunctions Inserted: List (4-8)

1) Loss of 4KV Shutdown Board

2) Inadvertent HPCI initiation

3) EHC Leak

4) ATWS

5) Fuel Failure

-.L Malfunctions that occur after EOI entry: List (1-4)

1) ATWS

2) Fuel failure 2 Abnormal Events: List (1-3)

1) Loss of 4KV Shutdown Board (CRD Pump)

2) Inadvertent HPCI initiation 1 Major Transients: List (1-2)

1) ATWS/Fuel Failure 3 EOl's used: List (1-3)

1) EOI-1

2) EOI-2

3) EOI-3 1 EOI Contingencies used: List (0-3)

1) C5 75 Run Time (minutes) 35 EOI Run Time (minutes): 47 % of Scenario Run Time 3 Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

3A CRD Pump ready for PMT after speed increaser inspection, Mechanical Maintenance due to perform this shift. 38 CRD pump is in Service. 38 RFP is warming after maintenance to the oil system.

Operations/Maintenance for the Shift:

The Reactor is at 73% Power because Recirc Pump 3A VFD tripped last night due to a logic card Failure. Power was being restored when an oil leak developed on the 38 RFP. Maintenance has completed repairs and the clearance is picked up. The RFP was placed in warming last shift.

Plans are to return 38 RFP to service per 3-01-3 section 5.7 and place in Auto and return reactor power to 100% with control rod withdrawal and Recircflow per3-GOI-100-12 step 5 [20]

Unusual Conditions/Problem Areas:

Remnants of Hurricane Harmon will pass thru this area today, severe weather is possible.

Appendix D Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-6 Op-Test Number: HLT 0707 Examiners: Operators:

Initial Conditions: Unit at 70% power due to 3A Condensate Booster Pump out of service for oil leak. CRD Pump 3B tagged out for breaker work. 3-FCV-74-100 tagged out for maintenance on the actuator, valve has a mechanical locking device installed and is closed.

Actuator is removed. HPCI injection valves tagged for replacement of contactors in supply breakers. A 14 day LCO (TS 3.5.1) has been entered. Work has been completed and the clearance has been released.

Turnover: CRD Timer has been replaced, perform CRD Timer Test per 3-01-85 section 8.14, then withdraw rods per RE instructions to establish rod pattern. When 3A CBP is restored, continue to raise power and monitor pump amps. (step 5.0[18.3] of 3-GOI-100-12). When HPCI clearance is picked up, perform PMT per WO (copy attached) prior to making HPCI operable. EM connecting MOVAT equipment to Sys 69 valves, should be invisible to control room personnel.

Event Malfunction Event Event Number Number Type* Description 1 None N-ATC ATC performs CRD Timer test per 3-01-85.

2 None R-ATC Raise Reactor Power by control rod withdrawal.

R-SRO 3 imf C-ATC Control Rod 34-19 uncouples during Control Rod rd05r3419 C-SRO movement, ATC responds per AOI. Tech Spec call for ITS-SRO SRO.

4 ior zdihs691 C-BOP BOP responds to RWCU inadvertent isolation. Tech close C-SRO Spec call for SRO.

ITS-SRO 5 ior C-ATC ATC responds to loss of VFD cooling water system.

zdihs682a1 a C-SRO off 6 ior zdihs719a C-BOP BOP responds to RCIC trip and performs HPCI PMT.

trip C-SRO SRO refers to Tech Specs.

ITS-SRO 7 imf ad01 b 25 C-BOP BOP responds to stuck open MSRV which results in C-SRO rising Suppression Chamber pressure due to a tailpipe ITS-SRO break. SRO address Tech Specs for ADS valve failure and direct manual scram before DW pressure exceeds 2.45 psig.

8 imf pc14 50 M-AII Crew responds to lowering Suppression Pool level due to an un-isolable leak.

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor

HL TS-3-06 Rev 0 Page 1 of 46 SIMULATOR EVALUATION GUIDE TITLE: CRD TIMER TEST, CONTROL ROD ADJUSTMENT, CONTROL ROD 34-19 UNCOUPLED, SPURIOUS RWCU ISOLATION, RECIRC DRIVE 3A COOLING WATER PUMP FAILURE, RCIC TRIP, MSRV TAILPIPE BREAK IN SUPPRESSION CHAMBER, UN-ISOLABLE LEAK IN SUPPRESSION CHAMBER.

REVISION: 0 DATE: October 09,2008 PROGRAM: BFN Operator Training - Hot License THIS SCENARIO REQUIRES STOPWATCH, PROVIDE WO PMT AND ROD PULL SHEET TO CANDIDATES AT TURNOVER. (PMT & Turnover at end of this Evaluation Guide)

PREPARED: \

(Operations Instructor) Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date

( TASK LIST \

UPDATED Date

HLTS-3-06 Rev 0 Page 2 of 46 Nuclear Training Revision/Usage Log Revision Description of Date Pages Revised Number Changes Affected 0 Initial 09/08/08 All csf

HLTS-3-06 Rev 0 Page 3 of 46 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

CRD TIMER TEST, CONTROL ROD ADJUSTMENT, CONTROL ROD 34-19 UNCOUPLED, SPURIOUS RWCU ISOLATION, RECIRC DRIVE 3A COOLING WATER PUMP FAILURE, RCIC TRIP, MSRV TAILPIPE BREAK IN SUPPRESSION CHAMBER, UN-ISOLABLE LEAK IN SUPPRESSION CHAMBER.

IV. Length of Scenario - 1 to 1 % hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment / unit from operation. (SOER 94-1 and SOER 96-01)

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3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HLTS-3-06 Rev 0 Page 4 of 46 B. Enabling Objectives:

1. The operating crew will perform CRD Timer Test.

2. The operating crew will raise power with control rods per RE instructions.

3. The operating crew will recognize and respond to an uncoupled control rod (34-19)

4. The operating crew will recognize and respond to a Spurious RWCU Group 3 isolation.

5. The operating crew will recognize and respond to Recirc Drive 3A Cooling Water pump failure(s) which should lead to removing the Recirc pump from service.

6. The operating crew will recognize and respond to a broken MSRV tailpipe in the Suppression Chamber per 3-AOI-64-1.

7. The operating crew will recognize and respond to an un-isolable leak in the Suppression Chamber per 3-EOI-1 and 2.

8. The operating crew will spray the Suppression Chamber to maintain containment pressure less than the PCP curve and the RPV will be depressurized when Suppression Chamber level cannot be maintained above 11.5 feet..

HLTS-3-06 Rev 0 Page 5 of 46 VI.

References:

The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

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HL TS-3-06 Rev 0 Page 6 of 46 VIII. Console Operator Instructions

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A. Scenario File Summary

1. File: bat HL TS3-6 MF/RF/OR# Description

1) trg e 1 3ARH RST ART Assigns trigger to 3A RHR pump switch

2) trg e2 3A2VFDCOOL Sets trigger e2 to 3a2 cooling water pump handswitch

3) imffw02a 3A Condensate Booster Pump Trip

4) imf rh01 b Prevents 3B RHR pump manual start

5) imf rh01d Prevents 3B RHR pump manual start

6) ior zlohs0256a[1] off Green light off for 3A Condensate Booster Pump

7) ior zlohs0256a[2] off White light off for 3A Condensate Booster Pump

8) ior ypovfcv741 00 fail power now FCV 74-100 tag out

9) imf rd05r3419 34-19 Rod uncoupled

10) imf rd01 b CRD Pump Tagout 11 ) ior zlohs852a [1] off CRD Pump Tagout

12) ior zdihs852a stop CRD Pump Tagout

13) ior zlohs7334a[2] off HPCI tagout

14) ior zlohs7344a[1] off HPCI tagout

15) mrf th 18b trip Open breaker for 3A VFD 3A2 cooling water pump

16) trg e1 = imf pc14 50 Trigger e1 initiates a leak in the suppression chamber when 3A RHR pump is started.

17) trg e2= mrf th18b close Trigger e2 allows 3A2 VFD cooling pump to start manually.

18) tr~ e3 PCISRSTA Assigns trigger to PCIS Reset switch "A" 191 trg e4 PCISRSTB Assigns trigger to PCIS Reset switch "B"

20) trg e3= dar zloil643a 1 Deletes override on GP3 amber light "A"

21) trg e4= dar zloil643b1 Deletes override on GP3 amber light "B"

22) Imf rp06 Auto scram failure

23) imf pc07b 25 MSRV tailpipe break in Suppression Chamber

2. File: bat HLTS3-6-1 MF/RF/OR# Description

1) dar zlohs7334a[2] Deletes override for red light

2) dar zlohs7344a[1] Deletes override for green light

HLTS-3-06 Rev 0 Page 7 of 46 A. Scenario File Summary

3. File: bat app08e MF/RF/OR# Description

1) mrf rp14a Bypass Group 6 inboard low level/high drywell pressure interlocks

2) mrf rp14b Bypass Group 6 outboard low level/high drywell pressure interlocks

4. File: bat GP31S0L MF/RF/OR# Description

1) ior zloil643a1 [1] on Overrides GP3 PCIS "A" amber light on

2) ior zloil643b1 [1] on Overrides GP3 PCIS "B" amber light on

3) ior zdihs691 [2] close Closes 69-1

4) ior zdihs692a[2] close Closes 69-2

5) ior zdihs6912a[2] close Closes69-12A

5. File: bat GP3IS0L-1 MF/RF/OR# Description

1) dor zdihs691 Deletes override to allow opening 69-1

2) dar zdihs692a Deletes override to allow opening 69-2

3) dor zdihs6912a Deletes override to allow opening 69-12A

HLTS-3-06 Rev 0 Page 8 of 46 VIII. Console Operator Instructions HLTS-3-06 ELAPSED TIME PFK DESCRIPTION/ACTION Sim. Setup IC-26, 70% power (SNAP 258)

Sim. Setup bat HLTS-3-06 See scenario summary Sim Setup manual a. Tag 73-34 and 73-44,

b. Tag 3A CBP

c. Tag 3B CRD Pump,

d. Tag FCV 74-100 Sim Setup manual Reset alarms - Hit fault reset on "A" Recirc & reset alarms Instructor manual Provide turnover sheet, PMT, and pull sheet to crew ROLE PLAY: When requested as Reactor Engineer, Notify the control room that thermal limits will be checked and permission is granted to try and re-couple rod 34-19 per 3-AOI-85-2 When rod is inserted allows re-coupling control rod to 46 (dmf rd05r3419)

When requested by RWCU isolation examiner: (bat GP3IS0L)

Just before role play Allows Group 3 isolation reset below: (bat GP3IS0L-1)

HLTS-3-06 Rev 0 Page 9 of 46 ROLE PLAY: 5 minutes after RWCU isolates, Call as electrician foreman and report that while performing a WO on Unit 3, an electrician jumpered contacts 3 to 4 of relay 16AK26 which caused a Group 3 isolation.

The electrician was on the wrong Unit - the jumper was removed and Unit 3 is restored to normal. A PER will be generated.

ROLE PLAY: Act as RB AUO and report demins properly in hold and you are raising flow when requested to place them in service.

When asked to reset (mrf an01e reset) - allows control room local alarm alarm reset.

2 minutes after tech Trips 3A VFD cooling water pump 3A 1 specs addressed (ior zdihs682a1 a off) after low flow alarm Trips 3A VFD cooling water pump 3A2 cleared (ior zdihs682a2a off)

ROLE PLAY: If RB AUO is dispatched to check 3A1 VFD cooling water pumps, after 2 minutes report local breaker tripped and won't reset. If sent to VFD to check temps (after both pumps tripped), report VFD is too hot to approach.

4 minutes after 3A RCIC Turbine trips VFD cooling water (ior zdihs719a trip) pump is lost ROLE PLAY: Personnel dispatched to RCIC report latch broken on overspeed trip mechanism for RCIC ROLE PLAY: When SRO requests HPCI clearance status, inform SRO that you are standing by to close breakers for 73-34 and 73-44.

HLTS-3-06 Rev 0 Page 10 of 46 When requested to Allow PMT for HPCI valves turn on breakers for (bat HLTS-3-06-1) 73-34 and 73-44 When directed by Opens MSRV 1-19 to 25% with the tailpipe Chief Examiner: broken in the Suppression Chamber at 25% severity. (imf ad01 b 25)

When directed to Removes power from MSRV 1-19.

pull fuses for MSRV (mrf ad01 bout) 1-19:

If directed to re- Restores power to MSRV 1-19.

install fuses for (mrf ad01 bin)

MSRV 1-19:

ROLE PLAY: When directed to investigate flooding alarms in Unit 3 Reactor building, wait three minutes and report that there is a very large leak upstream of the 3A RHR pump suction valve, 74-1, and it can NOT be isolated.

When asked to Allows Reactor Building ventilation perform appendix restoration 8e, wait 5 minutes (bat app08e)

Terminate the scenario when the following conditions are satisfied or when requested by Lead Evaluator:

RPV has been depressurized.

Reactor level stable between + 2" and + 51"

HLTS-3-06 Rev 0 Page 11 of 46 IX. Scenario Summary:

The unit is operating at 70% power. The 3B Condensate Booster Pump is out of service for repair of an oil leak. HPCI Injection valves tagged for contactor replacement in the breakers. Currently in a 14 day LCO via Tech Spec 3.5.1. FCV 74-100 is tagged out for maintenance.

The crew will perform a CRD Timer Test per 3-01-85 section 8.14 and alternate EHC pumps per 3-01-47A section 6.2.

The crew will commence to raise power by pulling control rods, Control Rod 34-19 will uncouple and the crew will respond to an uncoupled rod per 3-AOI-85-2.

The crew will respond to a spurious RWCU System isolation and restore the system to service.

The crew will respond to failure of 3A Recirc Drive Cooling Water pump A. Followed shortly afterwards by B. The crew should secure 3A Recirc Pump.

The crew will respond to an inadvertent trip of the RCIC turbine. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months LCO that may be exited if HPCI is returned to operable status.

The crew will respond to a stuck open MSRV which results in rising Suppression Chamber pressure due to a broken tailpipe in the Suppression Chamber air space. The SRO will direct venting the Suppression Chamber per 3-AOI-64-1. The SRO may direct a manual scram before Drywell pressure reaches 2.45 psig. The reactor fails to automatically scram, therefore a manual scram must be directed after exceeding 2.45 psig.

When 3A RHR pump is started for Suppression Chamber sprays, a leak develops on the Suppression Chamber causing a loss of Suppression Pool water level. If RHR Loop II operation is attempted, 3B and 3D RHR pumps will not start manually. The SRO will enter and execute 3-EOI-1 and 3-EOI-2. The SRO will direct HPCI Aux Oil Pump to be placed in Pull-to-Lock before Suppression Pool level drops below 12.75 feet. When it is determined that Suppression Pool level cannot be maintained above 11.5 feet, the crew may anticipate Emergency Depressurization and rapidly depressurize the RPV using Bypass Valves. Otherwise, Emergency Depressurization must be initiated when Suppression Pool level drops below 11.5 feet due to uncovering the downcomer pipes.

HLTS-3-06 Rev 0 Page 12 of 46

x. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. US: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. RPV has been depressurized.

2. RPV level at + 2" to + 51"

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HLTS-3-06 Rev 0 Page 13 of 46 XI. Simulator Event Guide:

Event #1 : PERFORM CRD TIMER TEST Position Expected Actions Sat/Unsat/Comments SRO Directs ATC to perform CRD Timer Test per 3-01-85 section 8.14.

ATC [1] REVIEW all Precautions and Limitations in Section 3.2 and 3.3.

[2] PLACE WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3A1S6, in TEST AND HOLD for at least two seconds.

[3] CHECK the white indicating light above the WITHDRAW AUXILIARY TIMER TEST, 3-HS 3A1S6 illuminates.

[4] CHECK the red indicating light above the WITHDRAW AUXILIARY TIMER TEST, 3-HS 3A1S6 illuminates after approximately two seconds.

[5] CHECK CONTROL ROD SELECT BLOCK TIMER MALFUNCTION annunciator(3-XA-55-5A, Window 21) in alarm.

[6] PLACE WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3A1S6 in RESET.

[7] CHECK all Reactor Manual Control System WITHDRAW AUXILIARY TIMER TEST, 3-HS 3A1S6 indicating lights are extinguished.

[8] RESET CONTROL ROD SELECT BLOCK TIMER MALFUNCTION annunciator (3-XA-55-5A, Window 21).

HLTS-3-06 Rev 0 Page 14 of 46 XI. Simulator Event Guide:

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Event #1 : PERFORM CRD TIMER TEST Position Expected Actions SatlUnsatlComments ATC [9] LOWER the CRD DRIVE WTR HDR DP, 3-PDI-85-17A to less than 75 psid, using CRD DRIVE WATER PRESS CONTROL VLV, 3-HS 23A.

[10] SELECT a peripheral control rod by depressing the appropriate CRD ROD SELECT push-button, 3-XS-85-40.

[11] IF Rod Motion is observed while performing Step 8.14[12], THEN

[11.1] IMMEDIATELY RELEASE CRD CONTROL SWITCH, 3-HS-85-48, and CO NTACT System Engineer

[11.2] ADJUST the CRD DRIVE WTR HDR DP, 3-PDI-85-17A, to between 250 psid and 270 psid, using CRD DRIVE WATER PRESS CONTROL VLV, 3-HS-85-23A

[11.3] STOP all tests or checks until

( authorized by the Unit Supervisor

[12] ATTEMPT to withdraw the peripheral control rod using CRD CONTROL SWITCH, 3-HS-85-48 while observing the RMCS timer in the Auxiliary Instrument Room and/or the indicating lights on Panel 3-9-5.

[13] REPEAT step 8.14.11 as required to determine that the RMCS timer is operating as required.

[13.1] IF the RMCS timer is not operating as required, THEN GENERATE a WOo

[14] IF the RMCS timer is operating as required, THEN ADJUST the CRD DRIVE WTR HDR DP, 3-PDI-85-17A, to between 250 psid and 270 psid, using CRD DRIVE WATER PRESS CONTROL VLV, 3-HS-85-23A BOP Peer Checks manipulations

HLTS-3-06 Rev 0 Page 15 of 46 XI. Simulator Event Guide:

Event #2: RAISE POWER USING CONTROL RODS Position Expected Actions SatlUnsat/Comments SRO Directs ATC to withdraw rods per movement sheet ATC Withdraws rods per movement sheet BOP Peer Checks rod withdrawals

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HL TS-3-06 Rev 0 Page 16 of 46 XI. Simulator Event Guide:

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Event #3: CONTROL ROD 34-19 UNCOUPLED Position Expected Actions SatlU nsatlComments CREW Recognizes symptoms of an uncoupled rod SRO Directs ATC to respond to uncoupled rod per 3-AOI-85-2 Refers to Tech. Specs. 3.1.3 and dec/ares rod INOP while uncoupled.

ATC [1] NOTIFY Reactor Engineer to evaluate the suspect uncoupled control rod for its impact on core thermal limits and rod worth

[2] ADJUST the rod pattern as directed by the Reactor Engineer throughout the performance of this procedure

[3] IF the control rod drive is at position 48 AND with Reactor Engineer concurrence, THEN PERFORM the following:

[3.1] NOTCH INSERT the control rod drive to position 46 to attempt to couple the control rod.

[3.2] RESET associated annunciators.

[3.3] NOTCH WITHDRAW the control rod drive to position 48.

[3.4] PERFORM a coupling check.

[3.5] IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism

[3.5.1] RESET associated annunciators.

[3.5.2] NOTCH WITHDRAW control rod to position 48.

[3.5.3] PERFORM a coupling check Reports to SRO rod is coupled SRO Determines rod is operable

HLTS-3-06 Rev 0 Page 17 of 46 XI. Simulator Event Guide:

Event #4: RWCU ISOLATION Position Expected Actions SatlU nsatlComments Crew Recognizes Group 3 RWCU Isolation, responds per the ARP(s) 3-ARP-9-4B XA-55-4B win 10 (RWCU flow low) & win 24 RWCU demin abnor 3-XA-55-8C WIN 33 Motor tripout SRO Directs entry into 3-AOI-64-2A Evaluate Tech. Spec. (TRM TSR 3.4.1) Monitor conductivity every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (not in mode 4 or 5)

Chemistry, sampling required (If not returned to service)

BOP Enters 3-AOI-64-2A Immediate Actions

[1] VERIFY automatic actions occur

[2] PERFORM any automatic actions which failed to occur Subsequent Actions

[1] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s)

[2] CHECK the following to confirm high area temperature condition exists:

LEAK DETECTION SYSTEM TEMPERATURE, 3-TI-69-29 (Panel 3-9-21)

ATUs in Auxiliary Instrument Room

HLTS-3-06 Rev 0 Page 18 of 46 XI. Simulator Event Guide:

Event #4: RWCU ISOLATION Position Expected Actions SatlUnsatlComments BOP [4] REQUEST Reactor Engineering to make the necessary Heat Balance adjustments

[5] CHECK the following monitors for a rise in activity:

AREA RADIATION, 3-RR-90-1, Points 9, 13, and 14 (Panel 3-9-2)

AIR PARTICULATE MONITOR CONSOLE, 3-MON-90-50, 3-RM-90-55 and 57 (Panel 3-9-2)

RB, TB, and Refuel Zone Exhaust Rad on CONTROL ROOM CONSOLE, O-CONS 361A (Panel 1-9-44)

[7] NOTIFY Chemistry that RWCU has been removed from service and to begin sampling Reactor Water.

HL TS-3-06 Rev 0 Page 19 of 46 XI. Simulator Event Guide:

Event #4: RWCU ISOLATION Position Expected Actions Sat/Unsat/Comments BOP [9] EVALUATE Technical Requirements Manual Section 3.4.1, Coolant Chemistry, for limiting conditions for operation

[10] WHEN initiating signal has reset AND necessary repairs have been made, THEN RESET the following (Panel 3-9-4):

PCIS DIV I RESET, 3-HS-64-16A-S32

PCIS DIV II RESET, 3-HS-64-16A-S33

[11] RESTORE the system to normal operation.

REFER TO 3-01-69 SRO Directs restoration of system after cause is determined per 3-01-69 BOP Restores RWCU per 3-01-69

[3] VERIFY RESET the RWCU Group 3 isolation using PCIS DIV I RESET, 3-HS-64-16A-S32 and PCIS DIV II RESET, 3-HS-64-16A-S33 at Panel 3-9-4.

HLTS-3-06 Rev 0 Page 20 of 46 XI. Simulator Event Guide:

Event #4: RWCU ISOLATION Position Expected Actions Sat/U nsat/Comments

[6] VERIFY CLOSED the following:

RWCU BLOWDOWN PRESS CONTROL VLV, using 3-HC-69-15

RWCU BLOWDOWN TO MAIN CNDR, using 3-HS-69-16A

RWCU BLOWDOWN TO RADWASTE, using 3-HS-69-17A

[8] NOTIFY chemistry RWCU is being placed in service and to check the durability monitor.

[9] VERIFY OPEN the following valves:

RWCU INBD SUCT ISOLATION VALVE, 3-FCV-69-1

RWCU OUTBD SUCT ISOLATION VALVE,3-FCV-69-2

RWCU DEMIN BYPASS VALVE, 3-FCV-69-8

HLTS-3-06 Rev 0 Page 21 of 46 XI. Simulator Event Guide:

Event #4: RWCU ISOLATION Position Expected Actions SatlUnsatlComments

[10] OPEN 3-FCV-069-0012 by one of the two methods described below.

PLACE 3-HS-69-12A in the OPEN position, THEN RETURN 3-HS-69-12A to the NORM position when intermediate position (red and green light) is indicated.

PLACE 3-HS-69-12A in the OPEN position, THEN RETURN 3-HS-69-12A to the NORM position when FULL OPEN position (red light only) is indicated.

[11] PLACE seal purge in operation to pump(s) to be placed in service. REFER TO Section 8.2.

EVALUATOR RWCU is susceptible to an automatic NOTE isolation while being placed in service if sufficient flow is not established quickly following the first pump start.

[12] START RWCU RECIRC PUMP 3A(3B) using control switch 3-HS-69-4A(4B)-A, and A RISE flow, using RWCU RETURN ISOLATION VALVE, 3-HS-69-12A, to prevent low flow trip.

[13] IF two pump operation is desired, THEN START the second RWCU RECIRC PUMP 3B(3A) using control switch 3-HS-69-4B(4A)-A, and A RISE flow using RWCU RETURN ISOLATION VALVE, 3-HS-69-12A, to prevent low flow trip.

[14] IF the RWCU filter-demineralizers is to be placed in service, THEN REFER TO Section 6.2.

Coordinates with AUO to place RWCU demins in service Notifies Chemistry & Rx Engineer that RWCU has been restored

HLTS-3-06 Rev 0 Page 22 of 46 XI. Simulator Event Guide:

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Event #5: VFD COOLING WATER PUMP FAILURES Position Expected Actions SatlUnsat/Comments Crew Announces Recirc Drive 3A Coolant Flow Low.

Informs SRO 3A VFD Cooling Water Pump 3A 1 has tripped and 3A2 failed to start.

SRO Directs A TC to refer to ARP.

ATC Consults ARP, 3-ARP-9-4A XA-55-4A WIN 12 A. VERIFY RECIRC DRIVE cooling water pump running Manually starts 3A2 Cooling Water pump B. DISPATCH personnel to the RECIRC DRIVE to check the operation of the Recirc Drive cooling water system SRO Directs Outside US/maintenance to check on problem with 3A 1 cooling water pump ATC Announces Recirc Drive 3A Coolant Flow Low.

Informs SRO 3A VFD Cooling Water Pump 3A2 has tripped and 3A 1 or 3A2 failed to re-start.

SRO Directs trip of 3A Recirc Pump and entry into 3-AOI-68-1 A

HL TS-3-06 Rev 0 Page 23 of 46 XI. Simulator Event Guide:

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Event #5: VFD COOLING WATER PUMP FAILURES Position Expected Actions SatlUnsatlComments ATC Trips 3A Recirc pump Subsequent Actions

[2] IF Region I or II of the Power to Flow Map (Illustration 1) is entered, THEN (Otherwise N/A)

IMMEDIATELY take actions to INSERT control rods to less than 95.2% load line. Refer to O-TI-464, Reactivity Control Plan Development and Implementation Inserts control rods

HLTS-3-06 Rev 0 Page 24 of 46 XI. Simulator Event Guide:

Event #5: VFD COOLING WATER PUMP FAILURES Position Expected Actions SatlU nsatlComments ATC [3] RAISE core flow to greater than 45%. Refer to 3-01-68

[5] CLOSE tripped Recirc Pump discharge valve

[6] MAINTAIN operating Recirc pump flow less than 46,600 gpm. Refer to 3-01-68

[7] [NERlC] WHEN plant conditions allow, THEN, (Otherwise N/A) MAINTAIN operating jet pump loop flow greater than 41 x 106 Ibm/hr (3-FI-68-46 or 3-FI-68-48). [GE SIL 517]

[9] NOTIFY Reactor Engineer to PERFORM the following:

Tech Specs 3.4.1

3-SR-3.4.1 (SLO), Reactor Recirculation System Single Loop Operation

0-TI-248, Core Flow Determination in Single Loop Operation

[10] [NERlC] WHEN the Recirc Pump discharge valve has been closed for at least five minutes (to prevent reverse rotation of the pump) [GE SIL-517], THEN (N/A if Recirc Pump was isolated in Step 4.2[8]) OPEN Recirc Pump discharge valve as necessary to maintain Recirc Loop in thermal equilibrium SRO Addresses Tech Spec 3.4.1 for Single Loop Operations.

Request RE implement SR-3.4.1 (SLO) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

HLTS-3-06 Rev 0 Page 25 of 46 XI. Simulator Event Guide:

Event #6: INADVERTANT TRIP OF RCIC TURBINE Position Expected Actions SatiUnsatiComments BOP Announces RCIC Turbine tripped refers to ARP 3-XA-55-3B win 14.

Verifies; A. RCIC Turbine trip B. RCIC TURBINE THROT VALVE, 3-FCV-71-9, closes.

C. RCIC PUMP MIN FLOW VALVE, 3-FCV-71-34, closes A. DETERMINE cause B. IF valid alarm, THEN REFER TO 3-01-71, Section 8.3 C. REFER TO Tech Spec Section 3.5.3 SRO Dispatches field personnel to investigate and troubleshoot RCIC turbine trip.

Declares RCIC Inop per TS 3.5.3.A, 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months LCO due to inop HPCI Mode 3 required within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Reactor Pressure <150 psig within 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months .

SRO requests status of HPCI Directs BOP to perform PMT for 3-FCV-73-34 and 44, when clearance is released.

BOP Performs timing of 3-FCV-73-34 and 44 per WO (see next page)

SRO Reviews PMT (when complete) and declares HPCI operable. RCIC now in 14 day LCO.

HLTS-3-06 Rev 0 Page 26 of 46 XI. Simulator Event Guide:

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Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions SatlU nsat/Comments BOP Recognizes MSRV 1-19 is open. Performs immediate actions of 3-AOI-1-1.

Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 3-FMT 4, on Panel 3-9-3, OR

MSRV DISCHARGE TAILPIPE TEMPERATURE, 3-TR-1-1 on Panel 3-9-47

[2] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch several times as required:

CLOSE to OPEN to CLOSE positions

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A) N/A Subsequent Action 4.2.1 Attempt to close valve from Panel 9-3:

[1] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the OFF position.

[2] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON position.

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A)

[4] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT, 3-XS-1-202 in INHIBIT:

[5] IF relief valve closes, THEN OPEN breaker or PULL fuses as necessary using Attachment 1 (Unit 3 SRV Solenoid Power Breaker/Fuse Table).

[6] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT 3-XS-1-202, in AUTO.

HLTS-3-06 Rev 0 Page 27 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions SatlUnsatlComments BOP [7] IF the SRV valve did not close, THEN PERFORM the appropriate section from table below SRV 1-19 Step 3B 250 RMOV Bd 3-LPNL-925-0658, 3B Electric 4.2.2[6] (EI593' Board Room)

BOP [6] IF 3-PCV-1-19 is NOT closed, THEN PERFORM the following: (Otherwise N/A this section.)

[6.1] REMOVE the power from 3-PCV-1-19 by performing one of the following:

(Otherwise N/A):

A. OPEN the following breaker:

(Preferred method)

3B 250V RMOV, Compartment 1B2 OR B. In 3-LPNL-925-0658, (EI 593' 3B Electric Board Room, South Wall)

PULL the following fuses as necessary:

Fuse 3-FU1-001-0019A

Fuse 3-FU1-001-0019B

[6.2] IF the valve does NOT close, THEN CLOSE breaker or REINSTALL fuses removed in Step 4.2.2[6.1].

[6.3] CONTINUE at Step 4.2.3.

HLTS-3-06 Rev 0 Page 28 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions SatlUnsatlComments

[1] IF ANY EOI entry condition is met, THEN ENTER the appropriate EOI(s)

[2] REFER TO Technical Specifications Sections 3.5.1 and 3.4.3 for Automatic Depressurization System and relief valve operability requirements

[3] INITIATE suppression pool cooling as necessary to maintain suppression pool temperature less than 95°F

[4] IF the relief valve can NOT be closed AND suppression pool temperature Can NOT be maintained less than or equal to 95°F, THEN PLACE the reactor Modeo4 in accordance with 3-GOI-100-12A Report to SRO that valve did not close

HLTS-3-06 Rev 0 Page 29 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions Sat/U nsat/Com ments SRO Addresses Tech Specs for MSRV 1-19 (ADS valve) 3.5.1.E.1 (Restore ADS valve to OPERABLE status in 14 days)

BOP Recognizes rising Suppression Chamber pressure.

SRO Directs BOP to enter 3-AOI-64-1 and vent the Drywell.

BOP Initiates Drywell venting in accordance with 3-AOI-64-1.

4.2.1 EOI Entry Conditions

[1] IF any EOI entry condition is met, THEN ENTER appropriate EOI(s). (Otherwise N/A) 4.2.2 Orywell Pressure is High

[1] CHECK Drywell pressure using multiple indications.

[2] ALIGN and START additional Drywell coolers and fans as necessary. REFER TO 3-01-64.

HLTS-3-06 Rev 0 Page 30 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions SatlUnsatlComments BOP [3] VENT Drywell as follows:

[3.1] CLOSE SUPPR CHBR INBD ISOLATION VLV 3-FCV-64-34 (Panel 3-9-3).

[3.2] VERIFY OPEN, DRYWELL INBD ISOLATION VLV, 3-FCV-64-31 (Panel 3-9-3).

[3.3] VERIFY 3-FIC-84-20 is in AUTO and SET at 100 scfm (Panel 3-9-55).

[3.4] VERIFY Running, required Standby Gas Treatment Fan(s) SGTS Train(s) A, B, C (Panel 3-9-25).

[3.5] IF required, THEN REQUEST Unit 1 Operator to START Standby Gas Treatment Fan(s) SGTS Train(s) A, B. (Otherwise N/A)

[3.6] IF required, THEN RECORD venting data in 3-SI-4.7.A.2.a (Otherwise N/A)

[3.7] PLACE 3-FCV-84-20 CONTROL DW/SUPPR CHBR VENT, 3-HS-64-35, in OPEN (Panel 3-9-3)

[3.8] MONITOR stack release rates to prevent exceeding ODCM limits SRO Determines that Drywell pressure will exceed 2.45 psig and directs manual scram. (conservative decision making)

HLTS-3-06 Rev 0 Page 31 of46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Acti~ SatiUnsatiCommenls

...~::-4 I I [If!.' . . f!.l-""i:

Crew Recognizes that an automatic scram did not occur at +2.45 psig. (If not scramed prior to +2.45 psig)

ATC Inserts a manual scram; Places mode switch in shutdown verifies all rods in makes scram report SRO Enters EOI-1 on low level and directs:

Verifications of group isolations and initiations Directs entry into AOJ-1 00-1 Enters EOI-2 and re-enters EOI-1 when drywell pressure exceeds +2.45 psig.

BOP Verifies Diesel generators start Directs AUO to monitor DIG SRO Directs the following:

All available drywell cooling in service Venting per Appendix-12 H2/0 2 Analyzers placed in service

HLTS-3-06 Rev 0 Page 32 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions SatlU nsatlComments BOP Verifies all drywell blowers in service Places H2/0 2 Analyzers in service using keylock bypass switches.

Monitors containment parameters and reports rate of rise of suppression chamber pressure and drywell pressure Vents per Appendix-12 BOP 1. VERIFY at least one SGTS train in service

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CONT, OR

3-FIC-84-20, PATH A VENT FLOW CONT

HLTS-3-06 Rev 0 Page 33 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions Sat/UnsatlComments BOP NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented

6. IF ... ANY of the following exists:

Suppression Pool water level can not be determined to be below 20 ft, OR

Suppression Chamber can NOT be vented, OR

SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:

Step 10 to vent the Drywell through 3-FCV-84-19, OR

Step 11 to vent the Drywell through 3-FCV-84-20

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20

HLTS-3-06 Rev 0 Page 34 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions Sat/U nsat/Comments BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3 54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3 55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12

HLTS-3-06 Rev 0 Page 35 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions Sat/U nsat/Comments BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CaNT, or 3-FIC-84-20, PATH A VENT FLOW CaNT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

Release rates as determined below:

0 0-SI-4.8.B.1.a.1 release fraction of 1

HLTS-3-06 Rev 0 Page 36 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions SatlU nsatlComments SRO Determines venting and plant cooldown will not maintain suppression chamber pressure <12 psig and:

Directs BOP to initiate Suppression Pool Sprays in accordance with Appendix 17C.

BOP Initiates Suppression Pool Sprays in accordance with Appendix-17C.

1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in this procedure at Step 6

2. IF .............. Adequate core cooling is assured, OR Directed to spray the Suppression Chamber irrespective of adequate core cooling, THEN ....... ByPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS 155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS

HLTS-3-06 Rev 0 Page 37 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions Sat/U nsat/Comments BOP 5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

LPCI Initiation signal is NOT present, OR

Directed by SRO, THEN ....... PLACE keylock switch 3-XS-74-122(130), RHR SYS 1(11) LPCI2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121 (129),

RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

( d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11)

INBD INJECT VALVE, is OPEN, THEN .......

VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11)

OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired RHR System 1(11) pump(s) for Suppression Chamber Spray.

f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBR/POOL ISOL VLV.

g. OPEN 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.

h. IF ............. RHR System 1(11) is operating ONLY in Suppression Chamber Spray mode, THEN .......

CONTINUE in this procedure at Step 5.k.

HLTS-3-06 Rev 0 Page 38 of 46 XI. Simulator Event Guide:

Event #7: MSRV tailpipe break in Suppression Chamber Position Expected Actions SatlUnsatlComments BOP i. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

j. RAISE system flow by placing the second RHR System 1(11) pump in service as necessary.

k. MONITOR RHR Pump NPSH using Attachment 2.

I. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

m. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

n. NOTIFY Chemistry that RHRSW is aligned to in-service RH R Heat Exchangers

6. WHEN ...... EITHER of the following exists:

Before Suppression Pool pressure drops below 0 psig, OR

Directed by SRO to stop Suppression Chamber Sprays, THEN ....... STOP Suppression Chamber Sprays

HLTS-3-06 Rev 0 Page 39 of 46 XI. Simulator Event Guide:

Event #8: Un-isolable leak in Suppression Chamber Position Expected Actions SatlU nsat/Comments BOP Announces the following annunciators in quick succession:

RHR LOOP I PUMP ROOM FLOOD LEVEL HIGH (9-4C W17)

CORE SPRAY LOOP I RCIC PUMP ROOM FLOOD LEVEL HIGH (9-4C W24)

SUPPR CHMB RM FLOOD LEVEL HIGH (9-4C W3)

RHR LOOP II PUMP ROOM FLOOD LEVEL HIGH (9-4C W30)

CORE SPRAY LOOP II RCIC PUMP ROOM FLOOD LEVEL HIGH (9-4C W31)

SRO Dispatch personnel to visually check the secondary containment.

Enter 3-EOI-3 on Rx bldg flood levels.

Evaluator Note: The progression through 3-EOI-3 will eventually lead to the conclusion that two areas are greater than Max Safe values but depressurization will NOT reduce the leak into secondary containment. The flowchart will then direct a normal reactor shutdown, which has already been accomplished. At this point, the SRO should then focus on 3-EOI-2 actions to address the problem.

HLTS-3-06 Rev 0 Page 40 of 46 XI. Simulator Event Guide:

Event #8: Un-isolable leak in Suppression Chamber Position Expected Actions SatlUnsatlComments BOP Determine that Suppression Pool level is lowering and report to the SRO.

SRO Address 3-EOI-2 path SP/L for lowering SP level.

Direct ATC/BOP to perform Appendix-18 to add water to the Suppression Pool.

BOP Address Appendix-18 to add water to the Suppression Pool.

CRITICAL TASK SRO Direct HPCI operation be prevented by placing the Aux Oil Pump control switch in Pull-to-Lock before Suppression Pool level reaches 12.75 feet.

BOP Place the HPCI Aux Oil Pump control switch in Puil-to-Lock.

Evaluator Note: Once the report is received that the leak is significant and un-isolable, the SRO may make the decision that "Emergency Depressurization is Required." The decision step states "Can Suppression Pool Level be maintained above 11.5 feet." If this determination is made early enough, the SRO may take advantage of anticipating Emergency Depressurization and rapidly depressurize the RPV using Main Turbine Bypass Valves.

HLTS-3-06 Rev 0 Page 41 of 46 XI. Simulator Event Guide:

Event #8: Un-isolable leak in Suppression Chamber Position Expected Actions SatlUnsatlComments SRO Anticipate Emergency Depressurization and direct the RPV be rapidly depressurized using Main Turbine Bypass Valves. (conditional)

ATC/BOP Open Main Turbine Bypass Valves using the Bypass Valve manual Jack. (If directed)

CRITICAL TASK (conditional)

SRO When Suppression Pool level approaches or exceeds 11.5 feet, direct Emergency Depressurization using MSRVs in accordance with 3-EOI-C2.

BOP Opens six ADS valves to initiate Emergency Depressu rization.

NOTE: ADS MSRV 1-19 is failed open to 25% at this point. The crew may decide to open an additional non-ADS MSRV in place of 1-19. If not, MSRV 1-19 will come full open when the switch is placed in OPEN, which satisfies the requirement of six ADS valves.

HLTS-3-06 Rev 0 Page 42 of 46 XI. Simulator Event Guide:

Event #8: Un-isolable leak in Suppression Chamber Position Expected Actions SatlU nsatlComments Crew Recognize that an Accident Signal (CASx) will be received when RPV pressure drops below 450 psig if Drywell pressure is still above 2.45 psig.

SRO Direct ECCS pumps not required for injection be secured when the CASx signal is received.

BOP Secure ECCS pumps as necessary to restore and maintain RPV level +2 to +51 inches.

SRO Classifies the event as a SITE AREA EMERGENCY (2.1-S) due to Suppression Pool level below 11.5 feet, which is in the UNSAFE area of Curve 2.1-S (PSP Curve).

HLTS-3-06 Rev 0 Page 43 of 46 XII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Manually Scram the Reactor within 1 minute of automatic scram signal at 2.45 psig DW pressure. (conditional - If not scramed prior to +2.45 psig)

2) Prevent HPCI operation with Suppression Pool level below 12.75 feet.

3) Anticipate Emergency Depressurization and direct the RPV be rapidly depressurized using Main Turbine Bypass Valves. (conditional - if time permits - accomplishes the same task as Emergency Depressurization)

4) Emergency Depressurize the RPV within 5 minutes of Suppression Pool level dropping below 11.5 feet.

HLTS-3-06 Rev 0 Page 44 of 46 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-06

-.JL Total Malfunctions Inserted: List (4-8)

1) Suppression Chamber leak

2) Stuck Open MSRV

3) MSRV tailpipe break in Suppression Chamber

4) Control Rod Uncoupled

5) RWCU Isolation valve closure

6) RCIC Trip

7) Recirc Drive 3A Cooling water pump trip

8) RHR 3B and 3D manual start failure

9) Auto scram failure

~ Malfunctions that occur after EOI entry: List (1-4)

1) Auto scram failure

2) Suppression Chamber leak

3) RHR 3B and 3D manual start failure

~ Abnormal Events: List (1-3)

1) Control Rod Uncoupled

2) RWCU isolation

3) Recirc Drive 3A Cooling water pump trip 1 Major Transients: List (1-2) 1)

EOI's used: List (1-3)

1) EOI-1

2) EOI-2

3) EOI-3 1 EOI Contingencies used: List (0-3)

1) C2 80 Run Time (minutes)

~ EOI Run Time (minutes): 44 % of Scenario Run Time 4 Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

Unit at 70% power due to 3A Condensate Booster Pump out of service for oil leak. 3-FCV 100 tagged out for maintenance on the actuator, valve has a mechanical locking device installed and is closed. Actuator is removed. HPCI injection valves tagged for replacement of contactors in supply breakers. A 14 day LCO (TS 3.5.1) has been entered. Work has been completed and the clearance has been released. 3B CRD pump is tagged for bearing replacement.

Operations/Maintenance for the Shift:

Perform CRD Timer Test per 3-01-85 section 8.14, then withdraw rods per RE instructions to establish rod pattern. When 3A CBP is restored, continue to raise power and monitor pump amps. (step 50 [18.3] of 3-GOI-100-12). When HPCI clearance is picked up, perform PMT per WO (copy attached) prior to making HPCI operable. HLT class in the plant performing JPMs.

Unusual Conditions/Problem Areas:

Reactor Engineer expects Xenon to build-in over next few hours.

WO XX-XXXXX-XX PMT

1. CLOSE and TIME 3-FCV-73-34 using HPCI PUMP DISCHARGE VALVE, 3-HS-73-34A and RECORD the stroke time below:

3-FCV-73-34 Closing Time (sec)

Normal I Measured I Maximum N/A I I N/A

2. OPEN and TIME 3-FCV-73-44 using HPCI PUMP INJECTION VALVE, 3-HS-73-44A and RECORD the stroke time below:

3-FCV-73-44 Opening Time (sec)

Normal I Normal I Maximum 15.6-21.0 I I 30.0

3. VERIFY the stroke time recorded is less than or equal to the maximum value listed.

4. CLOSE and TIME 3-FCV-73-44 using HPCI PUMP INJECTION VALVE, 3-HS-73-44A and RECORD the stroke time below:

3-FCV-73-44 Closing Time (sec)

Normal I Normal I Maximum 16.6-22.4 I I 30.0

5. VERIFY the stroke time recorded is less than or equal to the maximum value listed.

6. OPEN and TIME 3-FCV-73-34 using HPCI PUMP DISCHARGE VALVE, 3-HS-73-34A and RECORD stroke time below:

3-FCV-73-34 Opening Time (sec)

Normal I Normal I Maximum 12.8-17.4 I I 26.7

7. VERIFY the stroke time recorded is less than or equal to the maximum value listed.

8. PMT COMPLETE Performed By: _ _ _ _ _ _ _ __

Reviewed By: _ _ _ _ _ _ _ _ __

Stopwatch Calibration Date: _ _ _ _ _ _ _ __

Appendix D Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HLTS-3-7 Op-Test Number: HL T 0707 Examiners: Operators:

Initial Conditions: Unit 3 is at 100% rated power. HPCI was tagged out 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago for repair to the Gland Seal Exhauster. Expected return to service is in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . A 14 day LCO Action has been entered in accordance with TSR 3.5.1.

Turnover: Maintain 100% power. Unit 3 has been operating for 187 days. Unit 1 and Unit 2 are at 100% power. Perform 3-SR-3.3.1.1.8(11) REACTOR PROTECTION SYSTEM MANUAL SCRAM FUNCTIONAL TEST. Severe thunderstorms are expected to pass through the area for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Limestone County is currently under a tornado watch.

Event Malfunction Event Event Number Number Type* Description 1 none N-ATC The ATC will perform 3-SR-3.3.1.1.8(11) REACTOR N-SRO PROTECTION SYSTEM MANUAL SCRAM FUNCTIONAL TEST.

2 mrf R-ATC The operating crew will recognize and respond to a rd10r1839 R-SRO control rod scram in accordance with 3-AOI-85-5.

scram TS-SRO 3 imf C-ATC The crew will recognize that control rod 22-39 is stuck rd06r2239 C-SRO and difficult to withdraw. The ATC will respond in accordance with 3-01-85.

4 imf ad01f C-80P The operating crew will recognize and respond to a stuck C-SRO open SRV in accordance with 3-AOI-1-1.

TS-SRO The SRO will recognize an inoperable ADS valve and HPCI in accordance with Technical Specifications.

5 imf ed06b The operating crew will recognize a loss of 161 KV.

6 imfth33a M-ALL The operating crew will recognize and respond to a imf th22 steam line break per the ARPs and EOls.

7 imf ed01 M-ALL The operating crew will recognize and respond to a loss of offsite power per 0-AOI-57-1A.

8 imf dg01a C-80P The operating crew will recognize and respond to diesel imf dg03d generator failures per 0-AOI-57-1A.

(N)ormal, (R)eactivlty, (I)nstrument, (C)omponent, (M)aJor

HLTS-3-07 Rev 0 Page 1 of 41 SIMULATOR EVALUATION GUIDE TITLE: ROD SCRAM, SRV FAILURE, LOSS OF OFFSITE POWER, STEAM LINE BREAK WITHIN DRYWELL, FAILURE OF DIESELS REVISION: 0 DATE: October 09, 2008 PROGRAM: BFN Operator Training - Hot License PREPARED: \

(Operations Instructor) Date REVIEWED: \

(LOR Lead Instructor or Designee) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date LOGGED-IN: \

(Librarian) Date TASK LIST \

UPDATED Date

HLTS-3-07 Rev 0 Page 2 of 41 Nuclear Training Revision/Usage Log Revision Description of Date Pages Revised Number Changes Affected 0 Initial 10/09/08 All csf

HLTS-3-07 Rev 0 Page 3 of 41 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

ROD SCRAM, SRV FAILURE, LOSS OF OFFSITE POWER, STEAM LINE BREAK WITHIN DRYWELL, FAILURE OF DIESELS IV. Length of Scenario - 1 to 1 % hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment I unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

B. Enabling Objectives:

1. The operating crew will recognize and respond to a control rod scram in accordance with 3-AOI-8S-S.

2. The operating crew will recognize and respond to a stuck control rod in accordance with 3-01-8S.

3. ' The operating crew will recognize and respond to a stuck open SRV in accordance with 3-AOI-1-1.

4. The operating crew will recognize and respond to an inoperable ADS valve and HPCI in accordance with Technical Specifications.

S. The operating crew will recognize and respond to a steam line break per the ARPs and EOls.

6. The operating crew will recognize and respond to a loss of offsite power and diesel generator failures per 0-AOI-S7-1A.

HLTS-3-07 Rev 0 Page 4 of 41 VI.

References:

The procedures used in the simulator are controlled copies and are

( used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order I Caution Order tags E. Annunciator window covers F. Steam tables

HLTS-3-07 Rev 0 Page 5 of 41 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat HLTS3-7 MF/RF/OR# Description

1) trg e1 MODESW Assigns trigger #1 to the Mode Switch

2) trg e2 adssrv1-34 Assigns trigger #2 to the MSRV 1-34 control switch

3) trg e3 8SCRAMLIGHT Assigns trigger #3 to the 8 Manual scram button light.

4) bat tohpci Tags out HPCllights

5) imfdg01a Fails DG 'A' from auto starting

6) imf dg03d Fails DG 'D' output breaker from auto closing

7) ior zloxi8546 off one rod permissive light

8) imf rc04 (e1 0) 0 Fails RCIC auto controller

9) imf fw14c (e1 :15) Trips 3C RFP

10) trg e2 =dmf ad01f Trigger #2 deletes ad01 f malfunction

11) imf ad02f (e2 :02) Initiates malfunction when trigger #2 fires

12) trge3 =mrf rd1 Of2239 scram Modifies remote function to scram rod 22-39 when "8" manual scram pushbutton is pushed.

2. File: bat HLTS3-7-2 MF/RF/OR# Description

1) I imf ed01 Loss of offsite power

2) I imf th22 (none 14:00) 100 10:00 Rx bottom head drain leak

3. File: bat tohpci MF/RF/OR# Description

1) ior ypovfcv7316 fail now FCV 73-16 power

2) ior ypovfcv733 fail now FCV 73-3 power

3) ior ypovfcv7381 fail now FCV 73-81 control power

4) ior zdihs7347a ptl Aux. oil pump failure

5) ior zlohs7347a[1] off Aux. oil pump light

6) ior ypomtrglexh fail en po Removes power from gland exhauster

HLTS-3-07 Rev 0 Page 6 of 41

4. File: bat eecw MF/RF/OR# Description

1) ior zdihs6753b reset Opens 67-53 from 25-32

2) ior xdihs6751 b reset Opens 67-51 from 25-32

3) ior zdihs6750b reset Opens 67-50 from 25-32

5. File: bat eecw-1 MF/RF/OR# Description

1) dor zdihs6753b reset Opens 67-53 from 25-32

2) dor xdihs6751 b reset Opens 67-51 from 25-32

3) dor xdihs6750b reset Opens 67-50 from 25-32

6. File: bat app07b MF/RF/OR# Description mrf s101 on Aligns SLC to Test Tank for injection to vessel

HL TS-3-07 Rev 0 Page 7 of 41 VIII. Console Operator Instructions

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ELAPSED TIME PFK DESCRIPTION I ACTION Sim. Setup 100% power, MOC Sim. Setup manual Close FCV 73-3, 81; Aux. oil pump and Gland Exhauster in pull to lock.

Sim. Setup manual Tag 73-2 & 3,81, & 16, Aux. Oil Pump, Gland Seal Exhauster.

Sim. Setup See scenario summary (bat HLTS3-7)

Whenever B half scram is reset Deletes Scram malfunction from rod 22-39 mrf rd10r2239 norm When Rod 22-39 has settled to notch Sticks rod 22-39 at position 00 00: imf rd06r2239 ROLE PLAY: If requested to check on cause of scrammed control rod, wait 5 minutes and report that fuse 5A-F19A (22-39) is blown. Fuse has been replaced.

ROLE PLAY: When requested for R.E. guidance, direct lowering power with recirc to 90% and notch withdraw control rod 22-39 back to notch 14 AFTER determining rod 22-39 does Deletes the stuck rod malfunction not withdraw and 3-01-85 has been (dmf rd06r2239) entered to address the stuck rod:

Two minutes after rod is withdrawn stuck open SRV 1-34 (imf ad01f 50) back to position 48 ROLE PLAY: 3 minutes after requested, report fuse 3E-F6J is blown in panel 25-32.

If requested to replace fuse Re-opens SRV Then: Restores power to MSRV 1-19

HLTS-3-07 Rev 0 Page 8 of 41 VIII. Console Operator Instructions ELAPSED TIME PFK DESCRIPTION I ACTION When directed by Chief Examiner: Loss of 161KV. (imf ed06b)

When directed by Chief Examiner: Steam Line Break (imf th33a 2 15:00)

When directed by Chief Examiner: LOSP (bat HLTS3-7-2)

ROLE PLAY: Reactor Engineer directs inserting emergency rods while he loads RWM.

ROLE PLAY: As the Incident Commander contact the SM on CSST spraying (no fire just spraying).

When requested to restore EECW to Opens 67-50,67-51 and 67-53 from 25-32 RBCCW, Air Compressor wait 3 (bat eecw) minutes NOTE: After bat eecw entered then Allows valves to reclose if another signal comes in (bat eecw-1)

When asked to reset Control Air Resets, restarts Control Air compressors A, Compressor wait 7 min D, and G (bat ca)

When asked to Reset RPS wait 5 Resets RPS circuit protectors (bat min rpsreset)

ROLE PLAY: Report EECW valves, control air, and RPS reset.

If requested to perform Appendix 7b, Aligns SLC to Test Tank wait 25 minutes bat app07b)

Terminate the scenario when the following conditions are satisfied or upon request of instructor:

1) Reactor Water level restored between +2 to +51"

2) Drywell sprayed

3) Cooldown begun

HLTS-3-07 Rev 0 Page 9 of 41 IX. Scenario Summary:

With the Unit at 100% power with HPCI out of service, a control rod will scram into the core. After replacing the fuse and recovering the control rod, an ADS relief valve fails open. When cycling the valve per the AOI, the valve closes, but the control power fuses blow. After addressing Tech Specs for HPCI with an inoperable ADS valve, a steam line breaks inside containment causing a drywell pressure/temperature increase. Shortly after the steam line break, a loss of offsite power occurs. One diesel fails to auto start, and one fails to auto tie to its 4KV Shutdown Board. The RCIC flow controller fails in auto, requiring operation in manual.

HLTS-3-07 Rev 0 Page 10 of 41 X. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. US: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1. Reactor water level restored at +2" to +51"

2. Drywell sprayed

3. Cooldown begun

HLTS-3-07 Rev 0 Page 11 of 41 XI. Simulator Event Guide:

Event #1 : Manual Scram functional test Position Expected Actions SatlUnsatlComments ATC Requests Peer Check for performance of 3-SR-3.3.1.1.8(11 )

Performs 3-SR-3.3.1.1.8(11)

Performs section 7.2 for RPS Channel "A".

Performs section 7.3 for RPS Channel "B".

Terminates the SR when indications of Control Rod 22-39 scram are received and reports conditions to the SRO.

HLTS-3-07 Rev 0 Page 12 of 41 XI. Simulator Event Guide:

Event #2: ROD 22-39 SCRAM Position Expected Actions SatiUnsatiComments SRO Directs the ATC to back out of 3.SR-3.3.1.1 .8[11]

Directs ATC to reset the half scram on RPS "8" Directs ATC to enter 3-AOI-8S-S, Rod Drift In Dispatches outside US to investigate single rod scram When determined that a blown fuse exists, directs replacement ATC Does not reset % scram for 10 seconds.

Notifies Reactor Engineer per 3-AOI-8S-S Checks thermal limits on ICS as directed by 3-AOI-8S-S.

EXAMINER No component manipulations are required per NOTE 3-AOI-85-5 in response to the scrammed control rod.

SRO Determines Control Rod 22-39 remains operable per Technical Specifications even though it has scrammed.

HLTS-3-07 Rev 0 Page 13 of 41 XI. Simulator Event Guide:

Event #2: ROD 22-39 SCRAM Position Expected Actions SatlUnsatlComments SRO Determines Control Rod 22-39 remains operable per Technical Specifications even though it has scrammed.

Contacts Rx Engineer to disposition rod Directs power reduced to 90% per R.E. instructions ATC Reduces recirc flow until power 90%

SRO Directs control rod 22-39 withdrawn to position 14 per R.E. direction ATC Attempts to notch withdraw control rod 22-39 to position 14 Determines control rod 22-39 will not withdraw.

HLTS-3-07 Rev 0 Page 14 of 41 XI. Simulator Event Guide:

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Event #2: ROD 22-39 SCRAM Position Expected Actions SatlUnsatlComments SRO Directs ATC to enter 3-01-85 section 8.15 for control rod difficult to withdraw.

ATC Enters 3-01-85 section 8.15 for control rod 22-39.

IF the control rod problem is not believed to be air in the hydraulic system, THEN PERFORM the following to double clutch the control rod at Position 00:

PLACE AND HOLD CRD NOTCH OVERRIDE, 3-HS-85-47, in EMERG ROD IN, for several seconds.

CHECK the control rod full in indication (double green dashes) on the Full Core Display for the associated control rod.

SIMULTANEOUSLY PLACE CRD NOTCH OVERRIDE, 3-HS-85-47, in NOTCH OVERRIDE AND CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH.

WHEN EITHER of the following occur:

Control rod begins to move, OR

It is determined the rod will not move, THEN RELEASE 3-HS-85-47 AND 3-HS-85-48.

IF the control rod successfully notches out, THEN PROCEED to Section 6.6 and WITHDRAW the control rod to the appropriate position.

HLTS-3-07 Rev 0 Page 15 of 41 XI. Simulator Event Guide:

Event #2: ROD 22-39 SCRAM Position Expected Actions SatlUnsatlComments SRO Directs ATC to withdraw rod 22-39 to position 14 as directed by the Reactor Engineer.

ATC Notch withdraws rod 22-39 to position 14.

SRO Direct the A TC to raise power to 100% using Recirc flow as directed by the Reactor Engineer.

ATC Raises reactor power to 100% using Recirc flow.

HLTS-3-07 Rev 0 Page 16 of 41 XI. Simulator Event Guide:

Event #4: SRV FAILURE WITH HPCI OUT OF SERVICE Position Expected Actions SatlUnsatlComments BOP Announces alarm "Main Steam" Relief valve open SRO Directs entry into AOI-1-1 BOP Enters AOI-1-1

. Identifies open SRV as 1-34 via acoustic monitor Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 3-FMT 4, on Panel 3-9-3, OR

MSRV DISCHARGE TAILPIPE TEMPERATURE, 3-TR-1-1 on Panel 3-9-47

[2] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch several times as required:

CLOSE to OPEN to CLOSE positions

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A) N/A Announces that SRV 1-34 indicates closed Reports loss of green light on SRV 1-34 SRO Directs outside SRO to check fuses. (If directs replacing fuse, the SRV will re-open and stay open)

Reviews Tech. Spec 3.5.1.H (with HPCI also INOP) and enters LCO 3.0.3

HLTS-3-07 Rev 0 Page 17 of 41 XI. Simulator Event Guide:

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Event #5: Loss of 161 KV (Trinity Line)

Position Expected Actions Sat/Unsat/Comments Crew Recognize a failure of 161KV SRO Contacts Unit 1 or 2 control room to verify a loss of 161KV.

Determine if Off-site Power Availability is being performed by another unit in response to the loss of 161KV.

HLTS-3-07 Rev 0 Page 18 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatlUnsatlComments Crew Notes Drywell pressure rising and reports to US BOP Announces alarm DRYWELL TO SUPPR CHAMBER DIFF PRESS ABNORMAL and enters ARP 3-ARP-9-38 window 26 A. VERIFY alarm by checking Drywell to Suppression Chamber DP.

B. REFER TO 3-01-64.

C. REFER TO Tech Spec Section 3.6.2.6.

Alarm quickly followed by PRI CONTAINMENT N2 PRESS HIGH, 3-ARP-9-38 window 10.

A. VERIFY containment pressure using multiple indications.

B. CHECK containment temperature.

C. REFER TO 3-01-64 Venting the Drywell with Standby Gas Treatment Fan.

SRO Determines that Drywell pressure rising too rapidly to try to vent per AOL Determines DW pressure will exceed 2.45 psig and directs core flow runback (If time permits) and a manual scram. (conservative decision making)

HLTS-3-07 Rev 0 Page 19 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatlUnsatlComments ATC Performs a core flow runback (If directed)

Inserts a manual scram; Places mode switch in shutdown Verifies all rods in Makes scram report Crew Announces Rx scram over P.A.

HLTS-3-07 Rev 0 Page 20 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions Sat/Unsat/Comments SRO Enters EOI-1 on low level and directs:

Verifications of group isolations and initiations Directs entry into AOI-1 00-1 Verifies Turbine Bypass valves controlling pressure Enters EOI-2 and re-enters EOI-1 when drywell pressure exceeds +2.45 psig.

BOP Verifies Diesel generators start Directs AUO to monitor DIG EXAMINER The crew may recognize the failure of 3EA DIG to start and manually start NOTE the DIG. This satisfies part of Event #7 component manipulations.

SRO Directs the following:

All available drywell cooling in service H2/0 2 Analyzers placed in service Venting per Appendix-12 BOP Verifiesall drywell blowers in service Places H2 /0 2 Analyzers in service using keylock bypass switches.

Monitors containment parameters and reports rate of rise of suppression chamber pressure and drywell pressure

HLTS-3-07 Rev 0 Page 21 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatlUnsatlComments BOP Vents per Appendix-12

1. VERIFY at least one SGTS train in service

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CONT, OR

3-FIC-84-20, PATH A VENT FLOW CONT

HLTS-3-07 Rev 0 Page 22 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatlUnsatlComments BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV 19 CONTROL, in OPEN (Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.

f. CONTINUE in this procedure at step 12

HLTS-3-07 Rev 0 Page 23 of 41 XI. Simulator Event Guide:

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Event #6: Steam Line Break in Drywell Position Expected Actions SatlUnsatlComments BOP 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CaNT, or 3-FIC-84-20, PATH A VENT FLOW CaNT, as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

MAINTAIN release rates below O-SI-4.8.B.1.a.1 release fraction of 1

HLTS-3-07 Rev 0 Page 24 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatlUnsatlComments SRO Determines venting and plant cooldown will not maintain suppression chamber pressure <12 psig and:

Directs BOP to initiate Suppression Pool Sprays in accordance with Appendix 17C.

BOP Initiates Suppression Pool Sprays in accordance with Appendix-17C.

1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in this procedure at Step 6

HLTS-3-07 Rev 0 Page 25 of 41 XI. Simulator Event Guide:

Event #5: Steam Line Break in Drywell Position Expected Actions SatlU nsatlComments BOP 5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

LPCI Initiation signal is NOT present, OR

Directed by SRO, THEN ....... PLACE keylock switch 3-XS-74-122(130), RHR SYS 1(11) LPCI2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121(129),

RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11)

INBD INJECT VALVE, is OPEN, THEN .......

VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11)

OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired RHR System 1(11) pump(s) for Suppression Chamber Spray.

f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBRIPOOL ISOL VL V.

g. OPEN 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.

h. IF ............. RHR System 1(11) is operating ONLY in Suppression Chamber Spray mode, THEN .......

CONTINUE in this procedure at Step 5.k.

HLTS-3-07 Rev 0 Page 26 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatlUnsatlComments BOP i. VERIFY CLOSED 3-FCV-74-7(30}, RHR SYSTEM 1(11) MIN FLOW VALVE.

j. RAISE system flow by placing the second RHR System 1(11) pump in service as necessary.

k. MONITOR RHR Pump NPSH using Attachment 2.

I. VERIFY RHRSW pump supplying desired RHR Heat Exchanger( s).

m. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV

3-FCV-23:'40, RHR HX 3C RHRSW OUTLET VLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

n. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers

6. WHEN ...... EITHER of the following exists:

Before Suppression Pool pressure drops below 0 psig, OR

Directed by SRO to stop Suppression Chamber Sprays, THEN ....... STOP Suppression Chamber Sprays Crew Monitors DW and Torus pressure

HL TS-3-07 Rev 0 Page 27 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatlU nsatlComments SRO Contacts Operations Duty Specialist (ODS) of OW steam leak and scram. (EAL 2.1-A)

BOP Reports Suppression Chamber pressure is 12 psig SRO Directs Recirc Pumps Tripped Directs Drywell Blowers stopped Directs Drywell Sprayed per Appendix-17B ATC/BOP Verifies Recirc pumps tripped Secures OW blowers BOP Sprays OW per App-17B

1. BEFORE Drywell pressure drops below 0 psig, CONTINUE in this procedure at Step 7

2. IF .............. Adequate core cooling is assured, OR Directed to spray the Drywell irrespective of adequate core cooling,THEN ...... .BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS 1(11)

OUTBD INJ VLV BYPASS SEL in BYPASS.

HLTS-3-07 Rev 0 Page 28 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatiUnsatiComments BOP 3. VERIFY Recirc Pumps and Drywell Blowers shutdown

6. INITIATE Drywell Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF ............. EITHER of the following exists:

LPCI Initiation signal is NOT present, OR

Directed by SRO, THEN ....... PLACE keylock switch 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121(129),

RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

d. IF ............. 3-FCV-74-53(67), RHR SYS 1(11)

LPCI INBD INJECT VALVE, is OPEN, THEN .......

VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11)

LPCI OUTBD INJECT VALVE.

e. VERIFY OPERATING the desired System 1(11)

RHR pump(s) for Drywell Spray.

HLTS-3-07 Rev 0 Page 29 of 41 XI. Simulator Event Guide:

Event #6: Steam Line Break in Drywell Position Expected Actions SatlUnsatlComments BOP f. OPEN the following valves:

3-FCV-74-60(74), RHR SYS 1(11) OW SPRAY OUTBD VLV

3-FCV-74-61 (75), RHR SYS 1(11) OW SPRAY INBD VLV.

g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

h. IF ............. Additional Drywell Spray flow is necessary, THEN ....... PLACE the second System 1(11) RHR Pump in service.

i. MONITOR RHR Pump NPSH using Attachment 2.

j. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).

k. THROTTLE the following in-service RHRSW outlet valves to obtain between 1350 and 4500 gpm RHRSW flow:

3-FCV-23-34, RHR HX 3A RHRSW OUTLET VL V

3-FCV-23-46, RHR HX 3B RHRSW OUTLET VL V

3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV

3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat Exchangers.

7. WHEN ...... EITHER of the following exists:

Before drywell pressure drops below 0 psig, OR

Directed by SRO to stop Drywell Sprays, THEN ....... STOP Drywell Sprays

HLTS-3-07 Rev 0 Page 30 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions SatlUnsatlComments ATC Announces Rx Scram, all rods in, provides scram report Crew Identifies loss of offsite power SRO Enters EOI-1 Directs O-AOI-S7-1A be performed Directs pressure be maintained 800-1000 psig using MSRVs (Appendix-11A)

Directs level be maintained above -162 (+2 to +51" with RCIC) (Appendix-SC)

Event #8: DIESEL FAILURES BOP Announces failure of 'A' Diesel Generator to start and failure of 'D' Diesel Generator to tie to shutdown board Starts 'A' Diesel and verifies/ties to SID Bd Manually tie 'D' Diesel to Shutdown Bd BOP Maintains RPV level with RCIC (App-5C)

1. IF ..... BOTH of the following exist:

RPV Pressure is at or below 50 psig, AND

Bypass of RCIC low RPV pressure isolation interlocks is necessary, THEN ... EXECUTE EOI Appendix 16A concurrently with this procedure

2. IF ..... BOTH of the following exist:

High temperature exists in the RCIC area, AND

SRO directs bypass of RCIC High Temperature Isolation interlocks, THEN ...

PERFORM the following:

a. EXECUTE EOI Appendix 16K concurrently with this procedure.

b. RESET auto isolation logic using RCIC AUTO-ISOL LOGIC A(B) RESET 3-XS 51A(B) pushbuttons

HLTS-3-07 Rev 0 Page 31 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions SatlUnsatlComments EXAMINER The RCIC Controller will not function in AUTOMATIC. The BOP must NOTE place the controller in MANUAL to operate RCIC.

BOP 3. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPITHROT VALVE RESET

4. VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller in AUTO with setpoint at 600 gpm

5. OPEN the following valves:

3-FCV-71-39, RCIC PUMP INJECTION VALVE

3-FCV-71-34, RCIC PUMP MIN FLOW VALVE

3-FCV-71-25, RCIC LUBE OIL COOLING WTRVLV

6. PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START

7. OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPL Y VLV, to start RCIC Turbine

8. CHECK proper RCIC operation by observing the following:

a. RCIC Turbine speed accelerates above 2100rpm.

b. RCIC flow to RPV stabilizes and is controlled automatically at 600 gpm.

c. 3-FCV-71-40, RCIC Testable Check Vlv, opens by observing 3-ZI-71-40A, DISC POSITION, red light illuminated.

d. 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE, closes as flow rises above 120 gpm When RCIC is used for level control identifies controller failure and takes manual control SRO Direct entry into AOI-1 00-1

HLTS-3-07 Rev 0 Page 32 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions SatlUnsatlComments BOP Maintains reactor pressureless than 1073 with MSRV's (App-11A) (if directed)

3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

(sequence is 1-13)

ATC Performs O-AOI-57 -1 A Immediate Actions

[1] VERIFY Diesel Generators have started and tied to respective 4kV Shutdown Boards, THEN DISPATCH personnel to Diesel Generators

[2] VERIFY two EECW Pumps (not using the same EECW strainer) are in service supplying Diesel Generators.

[2.1] IF two EECW Pumps (not using the same EECW strainer) are not in service supplying Diesel Generators, THEN PERFORM Attachment 9 (Cooling water is required to be established within 8 minutes)

(Otherwise N/A)

[3] PERFORM the following to ensure at least one train of Diesel Generator Room Fans are energized:

VERIFY 480V DSL Aux Board A or B energized.

VERIFY 480V DSL Aux Board 3EA or 3EB energized

HLTS-3-07 Rev 0 Page 33 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions SatlUnsatlComments ATC Subsequent Actions

[2] VERIFY automatic actions and PERFORM any that failed to occur

[6] PLACE RPS MG Sets A and B in service.

REFER TO 3-01-99 SRO Contacts Operations Duty Specialist (ODS) of loss of all Offsite Power and request assistance in getting power restored. (EAL 5.1-U)

Crew Coordinates starting RHR pumps to insure all motor breakers on associated Bd are tripped SRO Directs Injection with CRD (Appendix-58)

ATC Starts/aligns 3B CRD pump per App-5B

1. IF ..... Maximum injection flow is NOT required, THEN ... VERIFY CRD aligned as follows:

a. VERIFY at least one CRD pump in service and aligned to Unit 3 CRD system.

b. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, as necessary to obtain flow rate of 65 to 85 gpm.

c. THROTTLE 3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VL V, to maintain 250 to 350 psid drive water header pressure differential.

d. EXIT this procedure

HLTS-3-07 Rev 0 Page 34 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions SatlUnsatlComments ATC 2. IF ..... BOTH of the following exist:

CRD is NOT required for rod insertion, AND

Maximum injection flow is required, THEN ...

LINE UP ALL available CRD pumps to the RPV as follows:

a. IF ..... CRD Pump 3A is available, THEN

... VERIFY RUNNING CRD Pump 3A or 3B.

b. IF ..... CRD Pump 3B is available, THEN

... VERIFY RUNNING CRD Pump 3A or 3B

c. OPEN the following valves to increase CRD flow to the RPV:

3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VLV

3-PCV-85-27, CRD CLG WATER PRESS CONTROL VLV

3-FCV-85-50, CRD EXH RTN LINE SHUTOFF VALVE.

d. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, on Panel 9-5 to control injection WHILE maintaining 3-PI-85-13A, CRD ACCUM CHG WTR HDR PRESS, above 1450 psig, if possible.

e. IF ....... Additional flow is necessary to prevent or mitigate core damage, THEN

..... DISPATCH personnel to fully open the following valves as required:

3-THV-085-0527, CRD PUMP DISCH THROTTLING (RB NE, el 565')

3-BYV-085-0551, CRD PUMP TEST BYPASS (RB NE, el 565')

HLTS-3-07 Rev 0 Page 35 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions SatlUnsatlComments SRO Directs Injection with SLC (Appendix-7B)

ATC Calls for App-7B or starts SLC (If directed to inject from boron tank)

1. IF ..... EOI Appendix 3A is required to be performed, THEN ... EXIT this procedure.

NOTE: SLC Test Tank is preferred source because unborated water may be supplied to the RPV through this injection path

3. DISPATCH personnel to Unit 3 SLC pump area to line up SLC Test Tank as follows (RB NE, EI 639 ft)

SRO Directs cooldown be started ATC Starts cooldown at <1 OOoF/hr

HLTS-3-07 Rev 0 Page 36 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions SatlU nsatlComments Crew Recognize load shed and failure of "3D" DG to re-tie to board Verify that SBGT A and B re-start after 40 seconds ATC Directs RPS MG sets, EECW & Control air restored again after load shed SRO Directs injection with Core Spray Appendix-60 or 6E when pressure is low enough BOP Injects with CS (App-6D - 6E similar) to maintain RPV water level above -162 when pressure is low enough

1. VERIFY OPEN the following valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VL V

3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCT VL V

3-FCV-75-23, CORE SPRAY SYS I OUTBD INJECT VALVE

2. VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALVE

3. VERIFY CS Pump 3A and/or 3C RUNNING

4. WHEN ... RPV pressure is below 450 psig, THEN ... THROTTLE 3-FCV-75-25, CORE SPRAY SYS IINBD INJECT VALVE, as necessary to control injection at or below 4000 gpm per pump

5. MONITOR Core Spray Pump NPSH using Attachment 1

HLTS-3-07 Rev 0 Page 37 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions Sat/U nsat/Comments SRO Directs injection with RHR Appendix-68 or 6C when pressure is low enough (If necessary - keep in sprays, if needed)

BOP Injects with RHR (App-6B - 6C similar) to maintain RPV water level above -162 (If necessary)

2. VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VL V

3. VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VL V

4. VERIFY CLOSED the following valves:

3-FCV-74-61, RHR SYS I OW SPRAY INBDVLV

3-FCV-74-60, RHR SYS I OW SPRAY OUTBD VLV

3-FCV-74-57, RHR SYS I SUPPR CHBRIPOOL ISOL VLV

3-FCV-74~58, RHR SYS I SUPPR CHBR SPRAY VALVE

3-FCV-74-59, RHR SYS I SUPPR POOL CLG/TEST VL V

5. VERIFY RHR Pump 3A and/or 3C running

6. WHEN ...... RPV pressure is below 450 psig, THEN ...... .vERIFY OPEN 3-FCV-74-53, RHR SYS I LPCIINBD INJECT VALVE

HLTS-3-07 Rev 0 Page 38 of 41 XI. Simulator Event Guide:

Event #7: Loss of Off-site Power Position Expected Actions SatlUnsatlComments BOP 7. IF .............. RPV pressure is below 230 psig, THEN ....... VERIFy CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE

8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, as necessary to control injection

9. MONITOR RHR Pump NPSH using Attachment 1

10. PLACE RHRSW pumps in service as soon as possible on ANY RHR Heat Exchangers discharging to the RPV

11. THROTTLE the following in-service RHRSW outlet valves to maintain flow between 1350 and 4500 gpm:

(

3-FCV-23-34, RHR HX 3A RHRSW OUTLETVLV

3-FCV-23-40, RHR HX 3C RHRSW OUTLETVLV

(

HLTS-3-07 Rev 0 Page 39 of 41 XII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Maintains RPV water level above TAF (-162")

2) Spray the drywell after Suppression Pool Pressure exceeds 12 psig or Before Suppression Pool Pressure exceeds PSP curve or Orywell temperature exceeds 280°F

HL TS-3-07 Rev 0 Page 40 of 41 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-07 8 Total Malfunctions Inserted: List (4-8)

1) Indvidual Rod Scram

2) Stuck control rod

3) SRV Failure (open)

4) SRV Fuse Failure

5) LOSP

6) '3A' DG Failure

7) '3D' DG Failure

8) Steam Line Break

9) RCIC Controller Failure 4 Malfunctions that occur after EOI entry: List (1-4)

1) '3A' DG Failure

2) '3D' DG Failure

3) Steam Line Break

4) RCIC Controller Failure 2 Abnormal Events: List (1-3)

1) Control Rod Scram

2) SRV Open (AOI) 2 Major Transients: List (1-2)

1) LOSP

2) Steam Line Break (Small LOCA) 2 EOl's used: List (1-3)

1) EOI-1

2) EOI-2

~ EOI Contingencies used: List (0-3) 70 Run Time (minutes) 35 EOI Run Time (minutes): 50 % of Scenario Run Time 2 Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

HPCI was tagged out 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago for repair to the Gland Seal Exhauster. Expected back in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Operations/Maintenance for the Shift:

Maintain 100% power. Operating 187 days. Unit 1 and 2 are at 100% power. Perform 3-SR-3.3.1.1.8(11) REACTOR PROTECTION SYSTEM MANUAL SCRAM FUNCTIONAL TEST Unusual Conditions/Problem Areas:

Severe thunderstorms in area for next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Limestone County is currently under a Tornado Watch. Actions in accordance with 0-AOI-100-7. "Severe Weather" are complete through section 3.1 .

AppendixD Scenario Outline Form ES-D-l FINAL Facility: BFN Scenario Number: HL TS-3-8 Op-Test Number: HLT 0707 I Examiners: Operators:

Initial Conditions: Unit 3 is at -1 % power with a unit startup in progress. Currently at step 5.0[60.3] of 3-GOI-100-1A, Rod Group 17, control rod 30-11. 3C RFP is warmed at 600 rpm ready to be started. 3B CRD pump has been tagged for bearing replacement. IRM "G" is bypassed due to periodic noise spikes. System Engineering is monitoring IRM operation.

Turnover: Continue start-up. Commence inerting the Suppression Chamber per 3-01-76 Section 5.1. The potential for icing of power lines due to freezing rain has been reported by Transmission Power Services.

Event Malfunction Event Event Number Number Type* Description 1 none N-ATC Place 3C RFP in service per 3-01-3.

2 none N-BOP The operating crew will commence inerting the suppression chamber per 3-01-76.

3 none R-ATC The operating crew will withdraw control rods in R-SRO accordance with 3-01-85 and 3-GOI-1 00-1A.

4 imf rd02a C-ATC The operating crew will recognize and respond to a failed C-SRO CRD Flow Control valve per 3-AOI-85-3.

5 imf nm05c C-ATC The operating crew will recognize and respond to a failed C-SRO IRM instrument per 3-01-92 and Tech. Specs.

TS-SRO 6 C-BOP The operating crew will recognize and respond to a failed C-SRO H2/02 analyzer in accordance with ARPs and Tech.

TS-SRO Specs.

7 imf ed07a C-BOP The operating crew will recognize and respond to a trip C-SRO of 480V Unit Board 3A per ARPs.

8 imf nm05b M-ALL The operating crew will recognize and respond to another IRM instrument failure and subsequent Rx.

Scram.

9 imf th33c M-ALL The operating crew will respond to 3-EOI-1 and 3-EOI-2 entry conditions for failure to scram and drywell leak.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

HL TS-3-08 Rev 0 Page 1 of 46 SIMULATOR EVALUATION GUIDE TITLE: Containment Inerting, Control Rod Withdrawal, IRM Failures CRD Flow Control Failure, H2/02 Analyzer Failure, 3A Unit Board Failure, ATWS, Steam Line Break in Containment, Drywell Spray Failure, Emergency Depressurization.

REVISION: 0 DATE: October 12, 2008 PROGRAM: BFN Operator Training - Hot License A Radcon RPHP is required to swap steam loads from Aux Boiler to Nuclear Steam (Seal steam, SJAE's, and Preheaters per 3-01-47C and 3-01-66)

PREPARED: \

(Operations Instructor) Date REVIEWED: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee Required for Exam Scenarios) Date VALIDATED: \

(Operations SRO) (Required for Exam Scenarios) Date

HLTS-3-08 Rev 0 Page 2 of 46 Nuclear Training Revision/Usage Log Revision Description of Date Pages Revised Number Changes Affected 0 Initial 10/12/08 All csf

\,

HLTS-3-08 Rev 0 Page 3 of 46 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

Containment Inerting, Control Rod Withdrawal, IRM Failures CRD Flow Control Failure, H2/02 Analyzer Failure, 3A Unit Board Failure, A TWS, Steam Line Break in Containment, Drywell Spray Failure, Emergency Depressurization.

IV. Length of Scenario - 1 to 1 % hours V. Training Objectives:

A. Terminal Objective:

1. Perform routine shift turnover, plant assessment and routine shift operation in accordance with BFN procedures.

2. Given uncertain or degrading conditions, the operating crew will use team skills to conduct proper diagnostics and make conservative operational decisions to remove equipment / unit from operation. (SOER 94-1 and SOER 96-01)

3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition per normal, annunciator, abnormal, and emergency procedures.

HLTS-3-08 Rev 0 Page 4 of 46 B. Enabling Objectives:

1. The operating crew will commence inerting the suppression chamber per 01-76.

2. The operating crew will withdraw control rods in accordance with 01-85 and GOI-100-1A.

3. The operating crew will recognize and respond to a failed CRD Flow Control valve per AOI-85-3.

4. The operating crew will recognize and respond to a failed IRM instrument per 01-92 and Tech. Specs.

5. The operating crew will recognize and respond to a failed H2/02 analyzer I.A.W. ARPs and Tech. Specs.

6. The operating crew will recognize and respond to a trip of 480V Unit Board 3A per ARPs.

7. The operating crew will recognize and respond to another IRM instrument failure and subsequent Rx. Scram.

8. The operating crew will recognize and respond to EOI-1 and EOI-2 entry conditions for failure to scram and dryweilleak.

HLTS-3-08 Rev 0 Page 5 of 46

) VI.

References:

The procedures used in the simulator are controlled copies and are i used in development and performance of simulator scenarios. Scenarios are validated prior to use, and any procedure differences will be corrected using the procedure revision level present in the simulator. Any procedure differences noted during presentation will be corrected in the same manner. As such, it is expected that the references listed in this section need only contain the reference material which is not available in the simulator.

VII. Training Materials: (If needed, otherwise disregard)

A. Calculator B. Control Rod Insertion Sheets C. Stopwatch D. Hold Order / Caution Order tags E. Annunciator window covers F. Steam tables

HLTS-3-08 Rev 0 Page 6 of 46 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat HLTS-3-08 MF/RF/OR# Description

1) bat atws95 Hydraulic ATWS

2) mrf eg02 resA prevents the standby stator water cooling pump from auto starting

3) ior zdixs927as4b null Prevents "B" side IRM bypass joystick from working

4) imf nm05g 100 Fails IRM "G" high

5) ior zdihs7475a null prevents drywell spray on Loop 2

6) imf rp09c fails "B" RPS manual channel.

2. File: bat app01f MF/RF/OR# Description

1) mrf rp13a byp

2) mrf rp13b byp Auto Scram bypasses

3) mrf rp13e byp

4) mrf rp13d byp

3. File: bat app02 MF/RF/OR# Description

1) mrf rp12a test Auto ARI bypassed

2) mrf rp12b test

5. File: bat app08ae MF/RF/OR# Description

1) mrfrp14a Bypass Group 6 inboard low level/high drywell

2) mrf rp14b pressure interlocks

HLTS-3-08 Rev 0 Page 7 of46

\ VIII. Console Operator Instructions

)

ELAPSED TIME PFK DESCRIPTION I ACTION Sim. Setup ~ 1%, Start-up (IC-15) (snapshot 241)

Sim. Setup Inserts Batch file (bat HL TS 3-8)

See file Sim. Setup Manual Bypass G IRM, Reset % scram, acknowledge annunciators and reset.

Sim. Setup Secure purge filter fan (mrf pc06 stop)

Close containment purge valves When first bypass valve is open 10- Fails CRD Flow Control Valve 15 % and C RFP is in service for (imf rd02a) level control ROLE PLAY: When asked to align the "B" FCV wait 3 minutes and Report that Steps 3.1 thru 3.7 of 3-01-85 section 6.3 are complete.

When requested by board operator Swaps CRD Flow Control Valve to place 3-XS-85-11 to "B" valve (imf rd05 b)

ROLE PLAY: When asked for stabilizing flow (step [11]), report 6 gpm.

2 minutes after CRD flow control Fails H2/02 analyzer valve returned to service and after torus is being inerted When directed by lead examiner 480V Unit Board 3A failure (imf ed07a)

ROLE PLAY: As OSUS report that there is an overcurrent lockout on 3A 480V Unit Board.

HLTS-3-08 Rev 0 Page 8 of 46

)

When directed by lead examiner (imf nm05C) Fails "C" IRM high After Tech. Specs. addressed for (imf nm05b 100 3:00)

IRM"C" Slowly fails IRM "8" high After 5 control rods inserted (imf th33c 10 12:30) Starts steam leak in drywell After a scram is inserted: Restore SDV annunciators (bat SDV)

If Requested to perform App-1 F Defeats auto scram signals wait 6 minutes (bat app01f)

If requested to perform App-2, Defeats ARI (bat app02) wait 6 minutes When scram is reset: Allows SDV to drain (bat atws-1 )

ROLE PLAY: Call and report Appendix-1 F and 2 are complete If requested to perform App-8A and bypasses -122 MSIV isolation and 8E Group 6 2.45 and +2 inch isolation Wait 5 minutes (bat app08ae)

ROLE PLAY: Call and report Appendix-SA and SE are complete Before Drywell Sprays are Fails power to Loop1 drywell spray valve attempted (ior ypovfcv7460 faiLpower_now)

Terminate the scenario when the following conditions are satisfied or upon request of instructor:

1) Emergency Depressurization completed (with rods out)

2) Water level restored +2" to +51"

HLTS-3-08 Rev 0 Page 9 of 46 IX. Scenario Summary:

Given the unit at -1 % power with a unit startup in progress the crew will commence inerting the suppression chamber and continue with control rod withdrawal for startup.

After the first RFP is placed in service and the bypass valves start to open, the CRD flow control valve will fail forcing the crew to place the alternate flow control valve in service. After containment inerting is in progress, a failure of the "B" H2/02 analyzer will occur. During the startup another IRM will fail forcing the crew to recognize the Tech. Spec. implications. A loss of 480V Unit Board 3A will occur with several automatic functions failing to occur. After the Unit Board failure, another IRM will fail with a resultant ATWS. The crew will respond per AOI-1 00-1 to insert control rods.

After rod insertion has begun, a steam line break will occur causing drywell pressure to rise to the point where Drywell sprays are required. The drywell sprays for both loops are inoperable causing the crew to emergency depressurize with control rods still withdrawn.

HLTS-3-08 Rev 0 Page 10 of 46

) X. Floor Instructor Instructions A. Assign crew positions (assign positions based on evaluation requirements for personnel.

1. US: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide US with a copy of the shift turnover sheet for the scenario.

C. Direct the shift crew to review the control boards and take note of present conditions, alarms, etc.

D. Ensure recorders are inking are recording and ICS is active and updating. Note any deficiencies during shift briefing.

E. Terminate the scenario when the following conditions are satisfied or upon request of Lead Examiner.

1) Emergency Depressurization completed (with rods out)

2) Water level restored +2" to +51"

HLTS-3-08 Rev 0 Page 11 of 46 XI. Simulator Event Guide:

Event #1 : Place 3C RFP in service Position Expected Actions Sat/U nsat/Comments SRO Directs 3C RFP placed in service per 3-01-3, section 5.7.

Directs initiating Containment inerting per 3-01-76, section 5.1 Directs power increase re-commenced with control rods per GOI-100-1A Directs steam loads transferred from aux boilers to i nuclear steam I BOP Place "C" RFP in service per 01-3

[2] VERIFY RFP 3A(3B)(3C) MIN FLOW VALVE, 3-HS-3-20(13)(6), in OPEN position.

[3] SLOWLY RAISE speed of RFPT using RFPT 3A(3B)(3C) SPEED CO NT RAISE/LOWER, 3-HS-46-8A(9A)(10A), to establish flow and maintain level in vessel

[4] WHEN RFPT discharge pressure is within 250 psig of reactor pressure, THEN VERIFY OPEN RFP 3C)DISCHARGE VALVE, 3-FCV-3-5.

BOP [5] SLOWLY RAISE RFPT speed using RFPT 3C SPEED CONT RAISE/LOWER switch, 3-HS 10A, to slowly raise RFP discharge pressure and flow on the following indications (Panel 3-9-6):

RFP Discharge Pressure - RFP 3C, 3-PI-3-2A

RFP Discharge Flow - RFP 3C, 3-FI-3-6

[6] WHEN sufficient flow is established to maintain RFP 3C MIN FLOW VALVE, 3-FCV-3-6, in CLOSED position (approximately 2 x 106 Ibm/hr),

THEN PLACE RFP 3C MIN FLOW VALVE, 3-HS-3-6, in AUTO

HLTS-3-08 Rev 0 Page 12 of 46 XI. Simulator Event Guide:

Event #1 : Place 3C RFP in service Position Expected Actions SatlUnsatlComments

BOP [10] WHEN RFP in automatic mode on REACTOR i WATER LEVEL CONTROL, (PDS) 3-LlC-46-5, THEN CLOSE the following valves:

RFPT 3C LP STOP VLV ABOVE SEAT DR, 3-FCV-6-130

RFPT 3C LP STOP VLV BELOW SEAT DR, 3-FCV-6-131

RFPT 3C HP STOP VLV ABOVE SEAT DR, 3-FCV-6-132

RFPT 3C HP STOP VLV BELOW SEAT DR, 3-FCV-6-133

RFPT 3C FIRST STAGE DRAIN VLV, 3-FCV 134

RFPT C HP STEAM SHUTOFF ABOVE SEAT DRAIN, 3-FCV-006-0157 (local control)

RFPT C LP STEAM SHUTOFF ABOVE SEAT DRAIN, 3-FCV-006-0158 (local control)

[11] VERIFY CLOSED the following valves on first RFP started in Section 5.5:

RFPT 3C LP STOP VLV ABOVE SEAT DR,3-FCV-6-130

RFPT 3C LP STOP VLV BELOW SEAT DR,3-FCV-6-131

RFPT C LP STEAM SHUTOFF ABOVE SEAT DR, 3-FCV-006-0158 (local control)

[12] VERIFY both RFPT Main Oil Pumps running.

HLTS-3-0B Rev 0 Page 13 of 46 XI. Simulator Event Guide:

Event #2: Containment Inerting Position Expected Actions SatlUnsatlComments BOP Begins inerting Containment

[3] VERIFY the following initial conditions are satisfied:

Reactor Zone Ventilation in operation with Reactor Zone Supply and Exhaust Fan in fast speed. REFER TO 3-01-30B. i

Primary Containment Purge Filter Fan is in Standby Readiness. REFER TO 3-01-64.

H2/02 Analyzers are in service. REFER TO Section B.1 .

Oryweli/Torus has been vented to less than 0.25 psig. REFER TO 3-01-64.

Auxiliary Boilers System is in operation.

REFER TO 0-01-12.

HLTS-3-08 Rev 0 Page 14 of 46 XI. Simulator Event Guide:

Event #2: Containment Inerting Position Expected Actions SatlU nsatlComments BOP [4] VERIFY the following valves are closed (Panel 3-9-3):

PRI CTMT N2 MAKEUP OUTBD ISOLATION VLV, 3-HS-76-17

DRYWELL N2 MAKEUP INBD ISOLATION VLV, 3-HS-76-18

SUPPR CHBR N2 MAKEUP INBD ISOLATION VLV, 3-HS-76-19 Contacts AUO to perform steps [5] thru [18].

[19] CLOSE I VERIFY CLOSED, the following:

A. DRYWELL ATM SUPPLY INBD ISOLATION VLV,3-HS-64-18.

)

B. DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-29 (3-HS-64-29, Panel 3-9-3).

C. DRWELL VENT OUTBD ISOLATION VLV, 3-FCV 30 (3-HS-64-30, Panel 3-9-3).

[21] OPEN SUPPR CHBR VENT INBD ISOL VALVE, using 3-HS-64-32 (Panel 3-9-3).

[22] OPEN SUPPR CHBR VENT OUTBD ISOLATION VLV, using 3-HS-64-33 (Panel 3-9-3).

HLTS-3-08 Rev 0 Page 15 of 46 XI. Simulator Event Guide:

Event #2: Containment Inerting Position Expected Actions SatlU nsatlCom ments BOP [23] OPEN SUPPR CHBR ATM SPLY INBO ISOLATION VLV, using 3-HS-64-19 (Panel 3-9-3).

[24] START CTMT PURGE FILTER FAN, using local pushbutton, 3-HS-64-131 (Reactor Bldg EI 621', R-12 S-LlNE).

[25] OBSERVE purge filter differential pressure is less than 6" H20, as indicated by the total OP across HEPA filter, 3-POI-64-125, and charcoal filter, 3-POI-64-126 (Reactor Bldg. EI 621').

Contacts AUO to perform steps [26] and [27]

[28] OPEN PRI CTMT N2 PURGE OUTBO ISOLATION VLV, using 3-HS-76-24 (Panel 3-9-3).

Contacts AUO to perform steps [29] thru [35]

[36] CHECK OW/SUPP CHBR PURGE AIR/N2, 3-FI-76-25, stabilizes between 3000 and 4500 SCFM at Panel 3-9-3.

Contacts AUO to perform steps [37] thru [40]

[41] MONITOR OW/SUPPR CHBR PURGE AIR/N2 TEMP, 3-TI-76-26, periodically during inerting to ensure 2! 50°F (Panel 3-9-3).

HLTS-3-08 Rev 0 Page 16 of 46 XI. Simulator Event Guide:

Event #3: Control rod withdrawal Position Expected Actions SatlU nsatlComments ATC Withdraw control rods per 3-01-85, section 6.6, 3-SR-3.1.3.5(A), and O-TI-464.

[2] VERIFY the following prior to control rod movement:

CRD POWER, 3-HS-85-46 in ON.

Rod Worth Minimizer is operable and LATCHED into the correct ROD GROUP when Rod Worth Minimizer is enforcing.

6.6.3 Control Rod Notch Withdrawal

[1] SELECT the desired control rod by depressing the appropriate CRD ROD SELECT pushbutton, 3-XS-85-40.

[2] OBSERVE the following for the selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED

White light on the Full Core Display ILLUMINATED

Rod Out Permit light ILLUMINATED

HLTS-3-08 Rev 0 Page 17 of 46 XI. Simulator Event Guide:

Event #3: Control rod withdrawal Position Expected Actions SatiUnsatlComments ATC [3] VERIFY Rod Worth Minimizer is operable and LATCHED into the correct ROD GROUP when the Rod Worth Minimizer is enforcing.

I

[4] PLACE CRD CONTROL SWITCH, 3-HS-85-48, I in ROD OUT NOTCH, and RELEASE

[5] OBSERVE the control rod settles into the desired position and the ROD SETTLE light extinguishes

[6] IF control rod is notch withdrawn to rod notch Position 48, THEN PERFORM control rod coupling integrity check as follows:

[6.1] PLACE CRD CONTROL SWITCH, 3-HS-85-48, in ROD OUT NOTCH, and RELEASE.

[6.2] CHECK control rod coupled by observing the following:

Four rod display digital readout and the full core display digital readout and background light remain illuminated.

CONTROL ROD OVERTRAVEL annunciator, 3-XA-55-5A, Window 14, does not alarm.

[6.3] CHECK the control rod settles into Position 48 and the ROD SETTLE light extinguishes.

[6.4] IF Control Rod Coupling Integrity Check fails, THEN REFER TO 3-AOI-85-2

HLTS-3-08 Rev 0 Page 18 of 46

) XI. Simulator Event Guide:

Event #3: Control rod withdrawal I Position Expected Actions Sat/U nsat/Comments BOP 6.1 Shifting Supply from Auxiliary Steam to Main Steam

[1] CHECK reactor pressure is greater than 200 psig.

[2] OPEN MAIN STEAM SUPPLY TO STEAM SEAL valve, 3-FCV-1-146.

[3] CLOSE AUX BOILER SUPPLY TO STEAM SEAL valve, 3-FCV-1-154.

[4] CHECK steam seal header pressure, as indicated on STEAM SEAL HDR PRESSURE, 3-PI-1-148A, is between 2 1/2 and 5 1/2 psig.

Contact AUO to perform step [5]

[6] THROTTLE STEAM SEAL REG BYPASS VALVE, 3-FCV-1-145, to keep steam seal header pressure, as indicated on STEAM SEAL HDR PRESS, 3-PI-1-148A, between 2 1/2 and 5 1/2 psig, if necessary.

[7] CHECK SPE vacuum, as indicated on STEAM PACKING EXH VACUUM, 3-PI-66-54, is between 10 and 12 in H20 vacuum.

HL TS-3-08 Rev 0 Page 19 of 46 XI. Simulator Event Guide:

Event #3: Control rod withdrawal Position Expected Actions Sat/UnsatlComments BOP 5.9 Transfer of SJAEs from Aux Boiler Steam to Main Steam

[1] BEFORE placing SJAE on nuclear steam, PERFORM the following:

[1.1] NOTIFY Radiation Protection that an RPHP exist for the impending action to transfer SJAE to nuclear steam. RECORD time Radiation Protection notified in the NOMS Narrative Log. [BFN PER 126211]

(R) Initials

[1.2] VERIFY appropriate data and signatures recorded on Appendix A in accordance with Appendix A Instructions

[Tech Spec 5.7, SOER 01-1,

[2] WHEN directed by 3-GOI-100-1A to transfer SJAEs from Auxiliary Steam to Main Steam, THEN PERFORM Steps 5.9[3] through 5.9[17].

Contact AUO to perform steps [3] and [4]

[5] VERIFY OPEN (steam trap bypass valve) MAIN STEAM TO SJAE 3A(3B) DRAIN VALVE, using 3-HS-6-113A(114A) at Panel 3-9-7.

[6] PLACE the STEAM TO SJAE 3A(3B) handswitch, 3-HS-1-155A(156A) in OPEN at Panel 3-9-7 (this will open valves 3-FCV-1-155 and 172 (3-FCV-1-156 and 173>>.

Contact AUO to perform step [7]

[8] PLACE the SJAE 3A(3B) PRESS CONTROLLER handswitch, 3-HS-1-150(152), in OPEN at Panel 3-9-7.

HLTS-3-08 Rev 0 Page 20 of 46 XI. Simulator Event Guide:

Event #3: Control rod withdrawal Position Expected Actions SatlU nsatlComments BOP [9] CHECK the following red, open indicating lights have illuminated at Panel 3-9-7:

A. STEAM TO SJAE 3A(3B) STAGES 1,2, AND 3, 3-ZI-1-151/166(153/167)

B. SJAE 3A(3B) INTMD CONDENSER DRAIN,3-ZI-1-150(152)

Contact AUO to perform steps [10] thru [13]

[14] CLOSE the following steam trap bypass valves at Panel 3-9-7:

A. MAIN STEAM TO SJAE 3A DRAIN VALVE, using 3-HS-6-113A B. MAIN STEAM TO SJAE 3B DRAIN VALVE, using 3-HS-6-114A

[15] CHECK hotwell pressure as indicated on HOTWELL TEMP AND PRESS recorder, 3-XR 2, Panel 3-9-6, is being maintained below -25 inches Hg.

[16] [GE/R] PLACE the SJAE 3B(3A) PRESS CONTROLLER handswitch, 3-HS-1-152(150), in CLOSE at Panel 3-9-7 for the SJAE selected for Standby operation. [GE-SIL-150]

Contact AUO to perform step [17]

')

/

HL TS-3-08 Rev 0 Page 21 of 46 XI. Simulator Event Guide:

Event #3: Control rod withdrawal Position Expected Actions SatiUnsat/Comments BOP 5.10 Transfer of Preheaters from Aux Boiler Steam to Main Steam

[1] BEFORE placing Preheaters on nuclear steam, PERFORM the following:

[1.1] NOTIFY Radiation Protection that an RPHP exist for the impending action to transfer Preheaters to nuclear steam.

RECORD time Radiation Protection notified in the NOMS Narrative Log. [BFN PER 126211] (R) Initials

[1.2] VERIFY appropriate data and signatures recorded on Appendix A in accordance with Appendix A Instructions

[Tech Spec 5.7, SOER 01-1, BFN PER 126211]

BOP [2] WHEN directed by 3-GOI-1 00-1A to transfer preheaters from Auxiliary Steam to Main Steam, THEN PERFORM Steps 5.10[3] through 5.10[8].

Contact AUO to perform steps [3] thru [8]

[9] CHECK Recombiner temperatures stabilize greater than 275°F as indicated on RECOMBINER 3A13B TEMPERATURE recorder 3-TRS-66-77 at Panel 3-9-53

[10] CHECK hydrogen concentrations are stable as indicated by OFFGAS HYDROGEN ANAL YZER recorder 3-H2R-66-96 at Panel 3-9-53

HLTS-3-08 Rev 0 Page 22 of 46 XI. Simulator Event Guide:

Event #4: CRD flow control valve failure Position Expected Actions SatlU nsatlComments ATC Recognizes and reponds to FCV 85-11A failing closed i

SRO Directs actions per 3-01-85, section 6.3 Directs AUO to line up "B" FCV per 01-85 section 6.3 (steps [3.1] thru [3.7]

[4] VERIFY CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, in BAL position on outer control selector wheel.

[4.1] BALANCE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, by turning Manual Control Pot inside Control Selector Wheel until red deviation pointer is in Green Band.

[4.2] TURN CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, Control Selector from BAL position to MAN position

[5] ADJUST CRD SYSTEM FLOW using 3-FIC 11, to approximately 40 gpm with Manual Control Pot on 3-FIC-85-11.

(Note: This step cannot be performed)

Directs AUO to perform step [6] (select valve "B")

")

"l

HLTS-3-08 Rev 0 Page 23 of 46 XI. Simulator Event Guide:

Event #4: CRD flow control valve failure Position Expected Actions Sat/U nsat/Comments ATC [7] CHECK selected in-service valve opening and out-of-service valve closing.

Directs AUO to perform steps [8.1] and [8.2] to remove 85-11A from service.

[9] ADJUST CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, to establish between 40 gpm and 65 gpm.

[10] BALANCE CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, by TURNING Flow Demand Thumb Wheel until Red Deviation Pointer is in the Green band AND PLACE in AUTO or BALANCE.

Directs AUO to perform step [11]

[12] CHECK CRD DRIVE WTR HDR FLOW, 3-FI-85-15A is approximately 0 gpm.

[13] ESTABLISH the following by alternately adjusting the tape setpoint of the CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, and the throttled position of the CRD DRIVE WATER PRESS CONTROL VLV, 3-HS-85-23A:

CRD CLG WTR HDR DP, 3-PDI-85-18A, of approximately 20 psid

CRD DRIVE WTR HDR DP, 3-PDI-85-17A, between 250 psid and 270 psid

CRD SYSTEM FLOW, 3-FIC-85-11 between 40 gpm and 65 gpm SRO Recognizes that CRD temps are >350 and declares them slow per T.S. 3.1.4-1 and TI-393

HLTS-3-08 Rev 0 Page 24 of 46 XI. Simulator Event Guide:

Event #5: IRM FAILURE Position Expected Actions Sat/U nsat/Comments ATG Recognizes 1/2 scram and IRM "G" failed high SRO Recognizes that IRM "G" already bypassed and cannot bypass IRM "G" Refers to Tech. Specs and determines that less than required IRMs are operable and places channel in trip or Trip system in Trip. (3.3.1) within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . (actions taken with % scram sealed in)

- - _..... _ .. _- L-_ _ _ _ _

HLTS-3-08 Rev 0 Page 25 of 46 XI. Simulator Event Guide:

Event #6: H2/02 Analyzer Failure Position Expected Actions SatlU nsatlComments BOP Responds to Annunciator 9-7C window 22 for H2/02 analyzer malfunction I A. CHECK Panel 3-9-54 and 3-9-55 for abnormal indicating lights such as low flow, H2 or 02 downscale, pump off, etc. (low flow, H2 or 02 downscale, and pump off may exist if analyzer(s) are in standby)

B. IF sample pumps are required to be running, THEN PULL OUT 3-HS-76-49 or 3-HS-76-59 to start pumps.

C. DISPATCH personnel to Panels25-340 and 25-420 or 25-341 and 25-421 to check for abnormal flow/heat trace conditions D. REFER TO Tech Spec 3.3.3.1, Technical Requirements Manual Section 3.6.2.

E. USE the operable analyzer to monitor, as necessary, the drywell atmosphere.

F. IF Suppression Chamber atmosphere needs to be checked for SI/SR or other purposes, THEN PLACE in service analyzer to Suppression Chamber to obtain concentrations and then RETURN analyzer to desired condition.

Recognizes failure of the "B" Analyzer and swaps the "A" analyzer to Suppression Chamber per step "F" above.

SRO Refers to Tech. Spec. 3.6.3.2 and TRM 3.6.2 and determines no action required

HLTS-3-08 Rev 0 Page 26 of 46 XI. Simulator Event Guide:

Event #7: Loss of 480V Unit Board 3A Position Expected Actions Sat/U nsat/Com ments Crew Recognize loss of 480V Unit Board 3A BOP Recognize trip of 3A Bus Duct Cooling fan and i starts 3B Bus Duct cooling Fan per 3-01-47 I section 6.11

[1] VERIFY Raw Cooling Water System is in service to Generator Bus Duct Heat Exchanger.

REFER TO 3-01-24.

[2] START the Generator Bus Duct Heat Exchanger Fan as follows:

[2.1] LOCALLY VERIFY the Generator Bus Duct Heat Exchanger fan is not rotating backwards.

[2.2] IF the normal feeder breaker is to supply the fan motor, THEN (Otherwise N/A)

PUSH GEN BUS DUCT HX FAN, 3-HS 31 in the DOWN position.

[2.3] IF the alternate feeder breaker is to supply the fan motor, THEN (Otherwise N/A)

PULL GEN BUS DUCT HX FAN, 3-HS 31 in the UP position.

[2.4] MOMENTARILY PLACE GEN BUS DUCT HX FAN, 3-HS-57-31 in the START position.

HL TS-3-08 Rev 0 Page 27 of 46 XI. Simulator Event Guide:

Event #7: Loss of 480V Unit Board 3A Position Expected Actions Sat/U nsat/Comments BOP Recognize failure of 3B Stator Water Cooling pump to auto start and manually starts 3B Stator Water I Cooling Pump per 3-01-35A section 8.4

[1] START the Standby Stator Cooling Water Pump B by placing GEN STATOR CLG WATER PUMP B, 3-HS-35-36A on Panel 3-9-8 to START.

[2] STOP the Stator Cooling Water Pump A by placing GEN STATOR CLG WATER PUMP 3A, 3-HS-35-35A on Panel 3-9-8 to STOP Direct AUO to perform steps [3] and [4]

[5] VERIFY the pump control switch for the stator cooling water pump stopped in Step 6.4[2] is returned to AUTO on Panel 3-9-8.

Direct AUO to perform step [6]

ATC Verifies auto start or starts 3B EHC pump per 3 47A section 6.3 SRO Dispatches Outside Unit Supervisor to check on 3A 480V Unit Board

HLTS-3-08 Rev 0 Page 28 of 46 XI. Simulator Event Guide:

Event #8: "8" IRM Failure Upscale/ Scram/ATWS Position Expected Actions SatlU nsatlComments I

ATC Recognizes IRM "8" failing upscale and attempts to i range up.

Reports failure to range to US SRO Directs manual scram ATC Manually scrams reactor Reports failure to scram and initiates a channel of ARI Reports all rods NOT inserted Reports power < 5%

80P Announces Rx scram SRO Recognizes that no entry conditions exist for EOls and directs 8UO to control RPV water level +2" to

+51" 80P Controls water level +2" to +51" with RFPs SRO Directs using AOI-1 00-1 & 3-01-85 to insert control rods ATC Recognizes that scram is reset and drives control rods per 3-01-85 section 8.19 8.19 Control Rods Which Fail to Fully Insert After Scram

[4] IF it is desired to Insert Control Rods Using Reactor Manual Control System, THEN PERFORM the following:

[4.1] VERIFY the reactor scram has been reset. REFER TO 3-AOI-100-1.

HLTS-3-08 Rev 0 Page 29 of 46 XI. Simulator Event Guide:

Event #8: "B" IRM Failure Upscale/ Scram/ATWS Position Expected Actions SatlU nsatlComments ATC [4.2] IF scram CANNOT be reset, THEN CLOSE CHARGING WATER SHUTOFF, 3-SHV-085-0586 (RB, EL 565, NE Corner).

[4.5] BYPASS the Rod Worth Minimizer.

[4.6] DEPRESS the appropriate CRD Rod Select pushbutton on 3-XS-85-40.

[4.7] CHECK the backlit CRD ROD SELECT pushbutton is brightly illuminated and that the white indicating light on the Full Core Display is illuminated.

[4.8] CONTINUOUSLY INSERT the control rod to Position 00, by holding the CRD CONTROL SWITCH, 3-HS-85-48, in ROD IN or CRD NOTCH OVERRIDE SWITCH, 3-HS-85-47 in EMERG ROD IN.

SRO Declares Alert (1.2.A)

HLTS-3-08 Rev 0 Page 30 of 46 XI. Simulator Event Guide:

Event #9: Drywell leak requiring Emergency Depressurization Position I Expected Actions Sat/U nsat/Comments Crew I Identifies drywell pressure/temperature rise SRO I Enters EOI-2 on high drywell temperature above 160°F, and enters EOI-1 and re-enters EOI-2 when drywell pressure exceeds 2.45 psig Verifies appropriate group isolations Enters C5 and directs ADS inhibited and Appendices 8A and 8E performed Verifies Diesel generators start BOP I Directs AUO to monitor D/G SRO I Directs the following:

All available drywell cooling in service

"A" H2/0 2 Analyzer placed in service

Venting per Appendix-12 BOP I Verifies all drywell blowers in service Places "A" H2/0 2 Analyzers in service using keylock bypass switches

1. Place Analyzer isolation bypass keylock switches to bypass.

2. Select OW or Supp Chmbr and momentarily pull out select switch handle to start sample pumps.

HLTS-3-08 Rev 0 Page 31 of 46 XI. Simulator Event Guide:

Event #9: Dryweilleak requiring Emergency Depressurization Position Expected Actions Sat/U nsatlCom ments BOP Vents per Appendix-12

1. VERIFY at least one SGTS train in service

2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):

3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV

3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE

3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV

3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE

HLTS-3-08 Rev 0 Page 32 of 46 XI. Simulator Event Guide:

Event #9: Dryweilleak requiring Emergency Depressurization Position I Expected Actions Sat/U nsat/Comments BOP I NOTE: Venting may be accomplished using EITHER:

3-FIC-84-19, PATH B VENT FLOW CaNT, OR

3-FIC-84-20, PATH A VENT FLOW CaNT

7. CONTINUE in this procedure at:

Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR

Step 9 to vent the Suppression Chamber through 3-FCV-84-20 BOP I 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CaNT, as follows:

a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

c. PLACE 3-FIC-84-19, PATH B VENT FLOW CaNT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

d. PLACE keylock switch 3-HS-84-19, 3-FCV 19 CONTROL, in OPEN (Panel 3-9-55).

e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CaNT, is indicating approximately 100 scfm.

HLTS-3-08 Rev 0 Page 33 of 46 XI. Simulator Event Guide:

Event #9: Drywell leak requiring Emergency Depressurization Position I Expected Actions SatlU nsatlComments BOP I 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CO NT , as applicable, to maintain ALL of the following:

Stable flow as indicated on controller, AND

3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND

Release rates as determined below:

MAINTAIN release rates below o Stack release rate of 1.4 x 107 j.JCi/s AND o 0-SI-4.8.B.1.a.1 release fraction of 1 o

) Monitors containment parameters and reports rate of rise of suppression chamber pressure and drywell temperature SRO Determines venting will not maintain suppression chamber pressure <12 psig and directs Torus Sprays be placed in service per Appendix-17C BOP Places Torus sprays in service per Appendix-17C BYPASS LPCI injection valve auto open signal as necessary by PLACING 3-HS-74-155A(B), LPCI SYS 1(11) OUTBD INJ VLV BYPASS SEL in BYPASS

HL TS-3-08 Rev 0 Page 34 of 46 XI. Simulator Event Guide:

Event #9: Drywellieak requiring Emergency Depressurization Position Expected Actions SatlU nsatlComments BOP 5. INITIATE Suppression Chamber Sprays as follows:

a. VERIFY at least one RHRSW pump supplying each EECW header.

b. IF Directed by SRO, THEN ....... PLACE keylock switch 3-XS-74-122(130), RHR SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.

c. MOMENTARILY PLACE 3-XS-74-121 (129),

RHR SYS 1(11) CTMT SPRAY/CLG VLV SELECT, switch in SELECT.

e. VERIFY OPERATING the desired RHR System 1(11) pump(s) for Suppression Chamber Spray.

f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11)

SUPPR CHBRIPOOL ISOL VLV.

g. OPEN 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.

6. WHEN ...... EITHER of the following exists:

Before Suppression Pool pressure drops below 0 psig, OR

Directed by SRO to stop Suppression Chamber Sprays, THEN ....... STOP Suppression Chamber Sprays

HLTS-3-08 Rev 0 Page 35 of 46 XI. Simulator Event Guide:

Event #9: Drywell leak requiring Emergency Depressurization Position Expected Actions SatiUnsatiComments SRO When PSC pressure exceeds 12 psig or if determines drywell temperature to exceed 280°F, Directs drywell blowers and Recirc pumps removed from service and directs drywell sprays initiated per Appendix-17B BOP Attempts OW sprays per App-17B

1. BEFORE Drywell pressure drops below 0 psig, CONTINUE in this procedure at Step 7

3. VERIFY Recirc Pumps and Drywell Blowers shutdown BOP e. VERIFY OPERATING the desired System 1(11)

RHR pump(s) for Drywell Spray

f. OPEN the following valves:

3-FCV-74-60(74), RHR SYS 1(11) OW SPRAY OUTBD VLV

3-FCV-74-61 (75), RHR SYS 1(11) OW SPRAY INBD VLV.

g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE.

h. IF ............. Additional Drywell Spray flow is necessary, THEN ....... PLACE the second System 1(11) RHR Pump in service.

Attempts to spray drywell and determines neither loop of drywell sprays are operable.

HLTS-3-08 Rev 0 Page 36 of 46 XI. Simulator Event Guide:

Event #9: Drywelileak requiring Emergency Depressurization Position I Expected Actions Sat/UnsatlComments SRO I Determines that conditions are such that the drywell temperature cannot be maintained below 280°F and Emergency Depressurization is Required CRITICAL TASK Directs all injection into the RPV be stopped and prevented except from CRD, SLC, and RCIC per Appendix-4 BOP I Performs Appendix-4 on 9-3

a. HPCI

1) IF .............. HPCI Turbine is NOT at zero speed, THEN ........ PRESS and HOLD 3-HS-73-18A, HPCI TURBINE TRIP push-button.

2) WHEN ...... HPCI Turbine is at zero speed, THEN ........ PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK and RELEASE 3-HS 18A, HPCI TURBINE TRIP push-button.

b. RCIC

1) IF .............. DIRECTED by SRO to allow RCIC injection, THEN ........ EXIT step 1.b.

2) PRESS 3-HS-71-9A, RCIC TURBINE TRIP push-button to trip RCIC Turbine.

(RCIC not required to be secured)

c. CORE SPRAY NOTE: After receipt of an automatic initiation signal, it is NOT necessary to wait until the pump actually starts before performing the next step.

Following an initiation signal, PLACE ALL Core Spray pump control switches in STOP.

HLTS-3-08 Rev 0 Page 37 of 46 XI. Simulator Event Guide:

Event #9: Drywell leak requiring Emergency Depressurization Position Expected Actions SatlU nsatlComments BOP d. LPCI SYSTEM PREVENT injection by EITHER of the following methods:

Following automatic pump start, PLACE I

RHR SYSTEM I pump control switches in STOP.

ATC Performs Appendix-4 on 9-5/6

f. CONDENSATE and FEEDWATER

1) LOWER RFPT 3C speed to minimum setting (approximately 600 rpm) using ANY of the following methods on Panel 3-9-5:

Using 3-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL AND individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in AUTO, OR

Using individual 3-SIC-46-8(9)(10), RFPT 3A(38)(3C) SPEED CONTROL PDS in MANUAL, OR

Using individual 3-HS-46-8A(9A)(10A),

RFPT 3A(38)(3C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR.

3) TRIP RFPTs as necessary to prevent injection by DEPRESSING the following push-buttons:

3-HS-3-176A, RFPT 3C TRIP

HLTS-3-08 Rev 0 Page 38 of 46 XI. Simulator Event Guide:

Event #9: Drywell leak requiring Emergency Depressurization Position I Expected Actions Sat/U nsat/Comments SRO I Enters C2 and directs 6 ADS valves opened BOP I Opens 6 ADS valves SRO I Directs injection re-commenced not before 190 psig CRITICAL TASK BOP/ATC I Re-commences injection at 190 psig with either condensate or RHR SRO Directs RPV level restored to +2" to +51" with either condensate (Appendix-6A) or RHR (Appendix-68 or 6C)

ATC Injects with Condensate App-6A when Rx pressure

< 190

1. VERIFY CLOSED the following Feedwater heater return valves:

3-FCV-3-71, HP HTR 3A1 LONG CYCLE TO CNDR

3-FCV-3-72, HP HTR 3B1 LONG CYCLE TO CNDR

3-FCV-3-73, HP HTR 3C1 LONG CYCLE TO CNDR

2. VERIFY CLOSED the following RFP discharge valves:

3-FCV-3-19, RFP 3A DISCHARGE VALVE

3-FCV-3-12, RFP 3B DISCHARGE VALVE

3-FCV-3-5. RFP 3C DISCHARGE VALVE

3. VERIFY OPEN the following drain cooler inlet valves:

3-FCV-2-72, DRAIN COOLER 3A5 CNDS INLET ISOL VLV

3-FCV-2-84, DRAIN COOLER 3B5 CNDS INLET ISOL VLV

3-FCV-2-96, DRAIN COOLER 3C5 CNDS

/

! INLET ISOL VLV

HLTS-3-0S Rev 0 Page 39 of 46 XI. Simulator Event Guide:

Event #9: Dryweilleak requiring Emergency Depressurization Position Expected Actions Sat/U nsat/Com ments ATC 4. VERIFY OPEN the following heater outlet valves:

3-FCV-2-124, LP HEATER 3A3 CNDS OUTL ISOL VLV

3-FCV-2-125, LP HEATER 383 CNDS OUTL ISOL VLV

3-FCV-2-126, LP HEATER 3C3 CNDS OUTL ISOL VLV

5. VERIFY OPEN the following heater isolation valves:

3-FCV-3-3S, HP HTR 3A2 FW INLET ISOL VLV

3-FCV-3-31, HP HTR 382 FW INLET ISOL VLV

3-FCV-3-24, HP HTR 3C2 FW INLET ISOL VLV

3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV

3-FCV-3-76, HP HTR 381 FW OUTLET ISOL VLV

3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV

6. VERIFY OPEN the following RFP suction valves:

3-FCV-2-S3, RFP 3A SUCTION VALVE

3-FCV-2-95, RFP 38 SUCTION VALVE

3-FCV-2-10S, RFP 3C SUCTION VALVE

7. VERIFY at least one condensate pump running S. VERIFY at least one condensate booster pump running

9. ADJUST 3-LlC-3-53, RFW START-UP LEVEL CONTROL, to control injection (Panel 3-9-5)

10. VERIFY RFW flow to RPV

HLTS-3-08 Rev 0 Page 40 of 46 XI. Simulator Event Guide:

Event #9: Orywell leak requiring Emergency Depressurization Position Expected Actions Sat/U nsatlComments BOP Injects with RHR (App-6B - 6C similar) to maintain RPV water level above -162 (If necessary)

1. IF .............. Adequate core cooling is assured, AND It becomes necessary to bypass the LPCI injection valve auto open signal to control injection, THEN ....... PLACE 3-HS-74-155A, LPCI SYS I OUTBO INJ VLV BYPASS SEL in BYPASS

2. VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT VLV

3. VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL SUCT VLV

4. VERIFY CLOSED the following valves:

3-FCV-74-61, RHR SYS I OW SPRAY INBO VLV

3-FCV-74-60, RHR SYS lOW SPRAY OUTBO VLV

3-FCV-74-57, RHR SYS I SUPPR CHBR/POOL ISOL VLV

3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE

3-FCV-74-59, RHR SYS I SUPPR POOL CLG/TEST VL V

5. VERIFY RHR Pump 3A and/or 3C running

6. WHEN ...... RPV pressure is below 450 psig, THEN .......VERIFY OPEN 3-FCV-74-53, RHR SYS I LPCIINBO INJECT VALVE

HLTS-3-08 Rev 0 Page 41 of 46 XI. Simulator Event Guide:

Event #9: Drywell leak requiring Emergency Depressurization Position Expected Actions Sat/U nsat/Comments BOP 7. IF .............. RPV pressure is below 230 psig, THEN .......VERIFy CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE

8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, as necessary to control injection BOP/ATC Restores RPV level to +2 TO +51 inches while monitoring power BOP Monitors torus temperature and reports to US prior to 110°F

HLTS-3-08 Rev 0 Page 42 of 46 XI. Simulator Event Guide:

Event #9: Drywell leak requiring Emergency Depressurization Position I Expected Actions Sat/U nsat/Comments SRO I Directs SLC Injection before Torus Temperature reaches 110°F per Appendix-3A if not sub-critical (conditional)

ATC I Injects SLC per App-3A (if directed)

1. UNLOCK and PLACE 3-HS-63-6A, SLC PUMP 3N3B, control switch in START PUMP 3A or START PUMP 3B position

2. CHECK SLC System for injection by observing the following:

Selected pump starts, as indicated by red light illuminated above pump control switch.

Squib valves fire, as indicated by SQUIB VALVE A and B CONTINUITY blue lights exti ngu ish ed,

SLC SQUIB VALVE CONTINUITY LOST Annunciator in alarm on Panel 3-9-5 (3-XA-55-5B, Window 20).

3-PI-63-7A, SLC PUMP DISCH PRESS, indicates above RPV pressure.

System flow, as indicated by 3-IL-63-11, SLC FLOW, red light illuminated on Panel 3-9-5,

SLC INJECTION FLOW TO REACTOR Annunciator in alarm on Panel 3-9-5 (3-XA-55-5B. Window 14

HLTS-3-0B Rev 0 Page 43 of 46 XI. Simulator Event Guide:

Event #9: Drywelileak requiring Emergency Depressurization Position Expected Actions SatlU nsat/Comments I ATC 4. VERIFY RWCU isolation by observing the following:

RWCU Pumps 3A and 3B tripped

3-FCV-69-1, RWCU INBD SUCT ISOLATION VALVE closed

3-FCV-69-2, RWCU OUTBD SUCT ISOLATION VALVE closed

3-FCV-69-12, RWCU RETURN ISOLATION VALVE closed

5. VERIFY ADS inhibited

6. MONITOR reactor power for downward trend

7. MONITOR 3-Ll-63-1A, SLC STORAGE TANK LEVEL, and CHECK that level is dropping

/:

approximately 1% per minute B. WHEN ... EITHER of the following exists:

SLC tank level drops to 0%,

OR

As directed by SRO, THEN ... STOP SLC Pump 3A or3B

9. NOTIFY Chemistry to mix additional solution to compensate for dilution as directed by the SRO

HLTS-3-08 Rev 0 Page 44 of 46 XII. Crew Critical Tasks:

TASK SAT/UNSAT

1) Inhibit ADS

2) Stop and prevent injection per Appendix-4 prior to emergency depressurizing.

3) Emergency depressurize within 5 minutes of drywell temperature reaching 280 of

4) Maintain RPV level above -180 inches

5) Inject SLC prior to 110 uF (conditional)

HLTS-3-08 Rev 0 Page 45 of 46 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER: HLTS-3-08 7 Total Malfunctions Inserted: List (4-8)

1) IRM failure

2) H2/02 Analyzer failure

3) CRD flow control valve failure

4) Electrical/Hydraulic ATWS

5) Steam leak in drywell

6) Drywell spray valve failures

7) 3A Unit Board failure 2 Malfunctions that occur after EOI entry: List (1-4)

1) Steam leak in drywell

2) Drywell spray valve failure

~ Abnormal Events: List (1-3)

1) CRD flow control valve (AOI-85-3)

2) ATWS (AOI-100-1)

3) ARPs (480V Unit Board 3A)

-L Major Transients: List (1-2)

1) ATWS

2) MSL Leak in drywell

-L EOl's used: List (1-3)

1) EOI-1

2) EOI-2

-L EOI Contingencies used: List (0-3)

1) C2

2) C5 70 Run Time (minutes) 28 EOI Run Time (minutes): 40 % of Scenario Run Time

~ Crew Critical Tasks: (2-5)

YES Technical Specifications Exercised (Yes/No) - TRM

SHIFT TURNOVER SHEET Equipment Out of Service/LCO's:

"G" IRM bYlIassed Operations/Maintenance for the Shift:

Commence Inerting the Suppression Chamber per 01-76 Section 5.1. Continue start-up.

) Currently at step 5.0[68] of GOI-100-1A. Rod Group 17, control rod 22-03. Place "3C" RFP in service at 850 psig for level control. 38 CRD pump tagged for bearing replacement.

Chest Warming is in progress.

Unusual Conditions/Problem Areas:

Potential for icing of lines due to freezing rain

ML091810124

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