ML091810122

Initial Exam 2008-302 Draft Simulator Scenarios

ML091810122
Person / Time
Site:	Browns Ferry
Issue date:	06/30/2009
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-259/08-302, 50-260/08-302, 50-296/08-302
Download: ML091810122 (229)

Text

AppendixD Scenario Outline Form ES-D-l DRAFT 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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. Valve 3-FCV-73-36 seal-in circuit has been disabled per step 7.6 of 3-SR-3.5.1.7 Turnover:

Continue with 3-SR-3.5.1. 7 which is in progress and is complete up to Step 7.4 [1] (HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure).

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 5.132) with no pre-conditioning limitations. Reactor Engineering will evaluate further power changes.

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-ATC 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

Appendix D Scenario Outline Form ES-D-l DRAFT Facility: BFN Scenario Number: HL TS-3-5 Op-Test Number: HL T 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. The 3B RFP was leaking at approximately 1 gallon every 30 minutes. 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.

Event Malfunction Event Event Number Number Type* Description 1 none R-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 for ATC, a loss of TS-SRO RPS "A" for ATC, a loss of RBCCW for BOP, a loss of C-SRO RWCU and FPC for BOP, a loss of SJAE for BOP and a Tech Spec reference and multiple component failures for SRO.

3 none C-ATC ATC will swap CRD pumps and restore RPS power.

C-BOP BOP will restore RBCCW, RWCU, FPC and re-start C-SRO SJAE. SRO will establish priorities for the above restoration activities.

4 none TS-SRO Low oil level is reported on 3B Core Spray pump.

5 imf hp01 C-BOP HPCI inadvertently initiates and injects to the RPV C-SRO without a valid initiation signal.

TS-SRO 6 imf tc07 100 C-ATC EHC leak. BOP must lock out EHC pumps and trip C-BOP Main Turbine. ATC reduces power and scrams C-SRO Reactor.

7 bat atws95east M-AII ATWS with fuel failure. SRO and crew respond per EOI-1, EOI-2 and C-5 imf th23 20

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

AppendixD Scenario Outline Form ES-D-l DRAFT 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 5.16 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 N/A N-BOP The crew will alternate EHC pumps using 3-01-47A.

N-SRO 2 None N-ATC ATC performs CRD Timer test per 3-01-85.

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

R-SRO 4 imf C-ATC Control Rod 46-39 uncouples during Control Rod rd05r4639 C-SRO movement, ATC responds per AOI. Tech Spec call for ITS-SRO SRO.

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

6 ior C-ATC ATC responds to loss of VFD cooling water system.

zdihs682a1a C-SRO off 7 ior zdihs719a C-BOP BOP responds to RCIC trip and performs HPCI PMT.

trip C-SRO SRO refers to Tech Specs.

ITS-SRO 8 imf ad01b 25 C-BOP BOP responds to stuck open MSRV which results in ITS-SRO rising SuppreSSion Chamber pressure due to a tailpipe break. SRO address Tech Specs for ADS valve failure and direct manual scram before DW pressure exceeds 2.45 psig.

9 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 DRAFT 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago for repair to the Gland Seal Exhauster. Expected return to service is in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 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 ad01f C-80P The operating crew will recognize and respond to a stuck C-SRO open SRV in accordance with 3-AOI-1-1.

4 none TS-SRO The operating crew will recognize and respond to an inoperable ADS valve and HPCI in accordance with Technical Specifications.

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

6 imf ed01 M-ALL The operating crew will recognize and respond to a loss of offsite power per 0-AOI-57-1A.

7 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)eactlvlty, {I)nstrument, (C)omponent, (M)aJor

Appendix D Scenario Outline Form ES-D-l DRAFT Facility: BFN Scenario Number: HL TS-3-8 Op-Test Number: HL T 0707 Examiners: Operators:

Initial Conditions: Unit 3 is at -1 % power with a unit startup in progress. Currently at step 5.0[68] of 3-GOI-1 00-1 A, Rod Group 17, control rod 30-11. 3C RFP is in service at 850 psig for level control. 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-BOP The operating crew will commence inerting the suppression chamber per 3-01-76.

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

3 none N-ATC Place 3C RFP in service per 3-01-3.

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)eactlvity, (I)nstrument, (C)omponent, (M)aJor

HLTS-3-2 REV 0 PAGE 1 OF63

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

REVISION o DATE January 19, 2008 PROGRAM BFN Operator Training - Hot License PREPARED BY: \

(Operations Instructor) Date

)

REVIEWED BY: \

(Operations Training Manager or Designee) Date CONCURRED: \

(Operations Superintendent or Designee) (Required for Exam Scenarios only) Date VALIDATION BY: \

(Operations SRO) (Required for Exam Scenarios only) Date Requires copy of 3-SR-3.S.1. 7 (current rev.) completed up to step 7.11 to be provided to crew at turnover

)

HLTS-3-2 REVO PAGE 2 OF 63 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF DATE PAGES REVIEWED BY NUMBER REVISION AFFECTED 0 INITIAL 1/19/08 All csf

HLTS-3-2 REV 0 PAGE 30F63

)

I. Program: BFN Operator Training II. Course: Hot License Training 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. Examination Objectives:

A. Terminal Objective

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

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

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 reactor power oscillations by scramming the reactor.

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

8. The operating crew will Emergency De-pressurize when in C1 before reactor water level reaches -180".

HLTS-3-2 REV 0 PAGE 4 OF 63

) 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:

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

)

)

HLTS-3-2 REV 0 PAGE50F63

) VIII. Console Operators Instructions A. Scenario File Summary

1. File: bat HLTS3-2 MF/RF/10R# DescriQtion a) trg e1 MODESW Sets trigger b) trg e2 adssrv1-22 Sets trigger c) ior zlohs 7416a[1] off Tag Out 3C RHR d) imf rh01c 3C RHR Pump trip e) ior ypobkrpmpcrh fail_power Control power for RHR 3C breaker f) mrf hw01 fast Advances all charts g) imf th33b (e1 0) 1 2:00 8 MSL break in OW h) imf th21 (e1 5:00) 0.510:00 Recirc. line break i) imf rd01a (e1 10:00) 3A CROP trip j) mmf cr02a (e1 0) 0 1:00 Reduces oscillations after the scram k) imf rd01b 38 CROP trip I) imf hp09 Failure of HPCI to auto isolate m) ior zlohs718a[1] on Fails 71-8 green light on n) ior ypovfcv718 fail_now Keeps the 71-8 valve closed

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

2. File: bat RRPAVI8

) MF/RF/10R# Description

1) imfth12a Inserts Vibration Alarm

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

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

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

)

HLTS-3-2 REV 0 PAGE 6 OF 63 B. Console Operators Manipulations ELAP. TIME PFK# DESCRIPTION/ACTION Simulator setup rst 28 "" 78 %Power MOC, use mid-power runback push button (snapshot 246)

Simulator setup F3 bat HLTS3-2 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 [11]

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 ROLE PLAY: When asked for local EHC pressure, (3-PI-047-0001(0002>> indicates 1625 psig. (3-01-47A section 6.3 step [4].

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

kOLE 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, HPCI suction pressure is 34 psig on 3-PI-73-28B (step 7.4[1.1]).

When HPCI is at rated pressure and F4 imf hp08 Steam leak into HPCI room flow 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 F6 imf ad01c 40 Fails SRV-1-22 open When RO cycles SRV then: F7 dmf ad01c SRV-1-22 closes When directed by Lead Instructor F8 bat RRPAVIB Recirc Pump A high vibration, seal failure, suction valve fails to close and power oscillations.

ROLE PLAY: When dispatched to check 3A Recirc Vibration, wait 2 minutes and report back swinging 10 to 14 mils.

HLTS-3-2 REVO PAGE 7 OF 63 C. Console Operators Manipulations ELAP. TIME PFK# DESCRIPTION/ACTION When cA' Recirc trips F9 dmf th12a Deletes vibration high alarm 4 min. after 3A recirc. pump trip F10 imf cr02a 75 3:00 Core power oscillations then: and F11 imf th22 (none 1 :30) 100 Bottom head leak Terminate the scenario when the following conditions are satisfied are at the direction of the Lead Examiner.

1. RPV water level +2" to +51"

2. Drywell sprayed

3. Emergency Depressurizarion completed

)

HLTS-3-2 REV 0 PAGE 8 OF 63 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.S.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 Depressurizes before reactor water level reaches -200".

)

)

HLTS-3-2 REVO PAGE 9 OF 63

x. Information to Floor Instructors:

A. Ensure recorders are inking and recording and ICS is active and updating.

B. Assign Crew Positions based on the required rotation.

1. SRO: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator C. Conducta shift turnover with the Unit Supervisor.

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

E. Terminate the scenario when the following conditions are satisfied are at the request of the floor/lead instructor/evaluator.

1. RPV water level +2" to +51"

2. Emergency Depressurizarion completed

HLTS-3-2 REV 0 PAGE 10 OF 63 XI. Simulator Event Guide Event 1: Alternate EHC Pumps TIME POSITION EXPECTED ACTION(S)

ATC/BOP Receive crew briefing and walk boards down SRO Directs BOP to alternate EHC pumps BOP

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

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

[3] START the non-operating EHC PUMP 3B(3A) using EHC HYD FLUID PUMP 3B(3A), 3-HS-47-2A(1A).

[4] CHECK the started EHC pump EHC HYD PUMP A(B) DISCH PRESS, 3-PI-047-0001 (0002), indicates between 1550 psig and 1750 psig, locally at the EHC

) skid. (AUO reports 1625 psig)

[5] IF the started EHC pump discharge pressure is NOT between 1550 psig and 1750 psig, THEN ADJUST the pressure compensator for the started EHC pump to adjust pump discharge pressure. REFER TO Step 8.6[1].

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

)

HLTS-3-2 REV 0 PAGE 11 OF 63

) XI. Simulator Event Guide Event 1: Alternate EHC Pumps TIME POSITION EXPECTED ACTION(S)

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

[10] CHECK the started EHC PUMP 3B(3A) MTR AMPS, 3-EI-47-2(1), indicates less than 140 amps.

[11] VERIFY EHC Pump 3B(3A), EHC PUMP SUCTION FILTER and EHC AUX PUMP SUCTION FILTERS, indicate CLEAN, locally at the EHC skid.

[12] [NERlC] VERIFY MANUAL FLOW CONTROL VALVE, 3-047-0588, is set at 2.0 turns clockwise. [INPO SOER 84-006]

BOP Swaps lens covers for EHC pumps based on new lineup

HLTS-3-2 REV a PAGE 12 OF 63 XI. Simulator Event Guide (Continued)

Event 2: Power Ascension TIME POSITION SRO ATC Raises reactor power in accordance with 3-GOI-100-12 and 3-01-68

[1] IF NOT in single loop operation, THEN ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS 15A{15B)/LOWER SLOW{MEDIUM) 3-HS-96-17A{17B), push-buttons, to achieve balanced jet pump flows. AND/OR ADJUST Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS-96-6A(16B) /LOWER SLOW(MEDIUM) 3-HS-96-18A(18B), pushbuttons, to achieve balanced jet pump flows.

[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-3-2 REV 0 PAGE 13 OF 63 XI. Simulator Event Guide (Continued)

Event 3a: HPCI Surveillence TIME POSITION EXPECTED ACTION(S)

SRO BOP [11] ALIGN HPCI System for a manual start by performing the following steps:

[11.1] 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.

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

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

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

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

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

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

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

HLTS-3-2 REVO PAGE 14 OF 63 XI. Simulator Event Guide (Continued)

Event 3a: HPCI Surveillence TIME POSITION EXPECTED ACTION(S)

BOP [12.4] PLACE HPCI AUXILIARY OIL PUMP 3-HS-73-47A to START.

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

[12.6] 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.

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

[12.8] OBSERVE that the following actions occurs:

o HPCI AUXILIARY OIL PUMP starts.

)

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

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

HLTS-3-2 REV 0 PAGE 15 OF 63

) XI. Simulator Event Guide (Continued)

Event 3a: HPCI Surveillence TIME POSITION EXPECTED ACTION(S)

D [NRC/C] HPCI PUMP MIN FLOW VALVE 3-FCV-73-30closes when HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 indicates approximately:::: 125 (:S 1250 gpm) flow. [Appendix R]

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

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

D HPCI AUXILIARY OIL PUMP stops as turbine speed rises.

[12.9] VERIFY Smooth operation of 3-FCV-73-18 and mark results below.

Yes _ _ __ No _ _ __

D IF the Answer above is "NO", THEN NOTIFY System Engineer to initiate a WO and proceed with test. (Otherwise N/A)

[12.10] VERIFY RESET the following annunciators:

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

D HPCI TURBINE TRIPPED 3-ZA-73-18 (3-XA-55-3F, window 11)

D HPCI TURBINE GLAND SEAL DRAIN PRESSURE HIGH 3-PA-73-46 (3-XA-55-3F, window 14)

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

[12.11] VERI FY system flow, discharge pressure, and turbine speed are stable prior to performing the next step.

)

HLTS-3-2 REV 0 PAGE 16 OF 63 XI. Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

BOP Responds to Reactor Bldg Hi Rad alarm per 3-ARP-9-3A window 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 area source of hi rad 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.

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 E. IF the TSC is manned and a "VALID" radiological condition exists, THEN REQUEST the TSC to evacuate non-essential personnel from affected areas.

)

HLTS-3-2 REV 0 PAGE 17 OF 63 XI. Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

F. MONITOR other parameters providing input to this annunciator frequently as these parameters will be masked from alarming while this alarm is sealed in.

G. IF a CREV initiation is received, THEN

1. VERIFY CREV A(B) Flow is 2': 2700 CFM, and :s; 3300 CFM as indicated on 0-FI-031-7214(7213) within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of the CREV initiation. [BFPER 03-017922]

2. IF CREV A(B) Flow is NOT 2': 2700 CFM, and :s; 3300 CFM as indicated on 0-FI-031-7214(7213) THEN PERFORM the following: (Otherwise N/A) [BFPER 03-017922]

a. STOP the operating CREV per 0-01-31.

b. START the standby CREV per 0-01-31.

')

J SRO

HLTS-3-2 REV 0 PAGE 18 OF 63 XI. Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

BOP Responds to HPCI Leak Detection Temp Hi alarm per 3-ARP-9-3F window 10 A. CHECK HPCI temperature switches on LEAK DETECTION SYSTEM TEMPERATURE, 3-TI-69-29 on Panel 3-9-21.

B. IF high temperature is confirmed, THEN C. CHECK following on Panel 3-9-11 and NOTIFY RADCON if rising radiation levels are observed:

1. HPCI ROOM EL 519 RX BLDG radiation indicator, 3-RI-90-24A.

2. RHR WEST ROOM EL 519 RX BLDG radiation indicator, 3-RI-90-25A.

D. DISPATCH personnel to investigate for leaks consistent with ALARA considerations in HPCI Turbine Area (EI519) and HPCI Steam Supply Area (EI550).

Recognizes HPCI not isolated when isolation lights are illuminated Notifies Unit Supervisor HPCI failed to isolate and 3-FCV-73-2 and 3-FCV-73-3 are still open.

)

HLTS-3-2 REV 0 PAGE 19 OF 63 XI. Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

SRO Directs HPCI manually isolated BOP Man. isolates HPCI steam supply by closing 3-FCV-73-2 and 3-FCV-73-3*** . . . . .1 ATC Receives EOI-3 entry on flood level in HPCI room 3-ARP-9-4c window 10 A. DISPATCH personnel to VISUALLY CHECK the HPCI room.

B. IF possible, THEN DETERMINE the source of the leak and the leak rate.

SRO Re-enters EOI-3 on flood level BOP Notifies Rad Con and Fire Protection Monitors for lowering temperature and radiation levels in HPCI area (after successful isolation)

HLTS-3-2 REVO PAGE 20 OF 63 XI. Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

SRO BOP Immediate Actions

[1] VERIFY automatic actions occur.

HPCI Turbine TRIPS.

HPCI STEAM LINE INBD ISOL VALVE, 3-FCV-73-2 CLOSES.

HPCI STEAM LINE OUTBD ISOL VALVE, 3-FCV-73-3 CLOSES.

HPCI STEAM LINE WARM-UP VALVE, 3-FCV-73-81 CLOSES.

HPCI PUMP MIN FLOW VALVE, 3-FCV-73-30 CLOSES.

)

HPCI SUPPR POOL INBD SUCT VLV, 3-FCV-73-26 CLOSES.

HPCI SUPPR POOL OUTBD SUCT VLV, 3-FCV-73-27 CLOSES.

HPCI TURBINE STOP VALVE, 3-FCV-73-18 CLOSES.

HLTS-3-2 REVO PAGE 21 OF 63 XI. Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION(S)

BOP Subsequent Actions

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

[2] DISPATCH an operator to the HPCI Turbine room to investigate.

[3] CHECK the following monitors for a rise in activity or area temperature:

AREA RADIATION, 3-RR-90-1, Point 23 (RM-90-24), Panel 3-9-2 AIR PARTICULATE RAD MON, 3-MON-90-50, Address 024 (3-RM-90-58),

Panel 3-9-2 RB & TB REFUELING ZONE EXH RAD MONITOR, 0-CONS-90-362, Address 08, 3-RM-90-250, Panel 1-9-44 LEAK DET SYS, TI-69-29, Panel 3-9-21, DEPRESS pushbutton to read TS-73-55A through 550.

HLTS-3-2 REV 0 PAGE 22 OF 63 XI. Simulator Event Guide (Continued)

Event 3b: HPCI Steam Line Break TIME POSITION EXPECTED ACTION{S)

BOP [4] VERIFY the following valves OPEN to drain the HPCI steam lines.*

MN STM LINE DRAIN INBD VLV, 3-FCV-1-55 OUTBD ISOLATION VLV, 3-FCV -56,

[S] IF the HPCI TURBINE EXH DRAIN POT LEVEL HIGH 3-LA-73-8 (3-XA-SS-3F, Window 33) annunciator is in alarm, THEN PERFORM the following:

[5.1] OPEN the HPCI TURB EXH CNDS POT LCV, 3-LCV-73-S.

[S.2] WHEN the annunciator HPCI TURBINE EXH DRAIN POT LEVEL HIGH*

resets, THEN CLOSE the HPCI TURB EXH CNDS POT LCV, 3-LCV-73-S.

SRO Determines unit in 14 day LCO (TS 3.5.1.C - HPCI inop. Verify RCIC OPERABLE by administrative means)

Determines unit in72 hour 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 when tagged (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to close and de-activate)

EXAMINER NOTE: When the valves are closed they are now considered OPERABLE because they are in the required position following an isolation signal, however the isolation logic is still INOPERATIVE.

)

HLTS-3-2 REV 0 PAGE 23 OF63 XI. Simulator Event Guide (Continued)

Event 4: SRV-1-22 Fails Open TIME POSITION EXPECTED ACTION(S)

CREW Recognizes SRVopen

• Main Steam Relief Valve Open alarm

• lowering generator output SRO BOP Immediate Action

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

SRVTAILPIPE 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 SRV-1-22 from acoustic monitor

[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 relief valve and reports SRV closed

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

)

HLTS-3-2 REVO PAGE 24 OF 63 XI. Simulator Event Guide (Continued)

Event 4: SRV-1-22 Fails Open (continued)

TIME POSITION EXPECTED ACTION(S)

BOP 4.2.3 Other Actions and Documentation

[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 Mode 4 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)

HLTS-3-2 REVO PAGE250F63 XI. Simulator Event Guide (Continued)

)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram TIME POSITION EXPECTED ACTIONS ATC Announces Recirc "3A" high vibration alarm 3-ARP-9-4A window 20 Consults ARP for Panel 9-4 A. CHECK temperatures for RECIRC PMP MTR 3A WINDING AND BRG TEMP recorder, 3-TR-68-58 on Panel 3-9-21 are below those listed for 3-XA-55-4A, Window 13.

B. CHECK for a rise in Drywellequip 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.

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

F. IF pump operation continues, THEN RECORD pump 3A seal parameters hourly on Attachment 1, Page 22 of this ARP.

HLTS-3-2 REV 0 PAGE 26 OF 63 XI. Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram TIME POSITION EXPECTED ACTIONS SRO Contacts Reactor Engineer ATC Announces Recirc A Seal Leakage Alarm 3-ARP-9-4A window 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, and control leakage lowers to:s 0.5 gpm.

Plugging of No.2 RO - No.2 seal pressure approaches no. 1 seal pressure and control leakage lowers to:s 0.5 gpm.

Failure of No.1 seal - No.2 seal pressure is greater than 50% of the pressure of No.1. The controlled leakage will be 2: 0.9 gpm.

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

')

HLTS-3-2 REV 0 PAGE 27 OF63 XI. Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram TIME POSITION EXPECTED ACTIONS ATC Identifies Seal Failure via Instrumentation Recognizes lowering pressure on Recirc Pump A #1 seal B. RECORD pump seal parameters hourly on Attachment 1, Page 28 of this procedure, unless other acceptable compensatory methods for recording these parameters is evaluated and approved by Engineering.

C. IF single seal failure is indicated, THEN INITIATE seal replacement as soon as possible. Continued operation is permissible if Dryweilleakrate is within T.S.

limits.

SRO Directs crew to watch for signs of increased leakage ATC Acknowledges Recirc Pump A seal leakoff high alarm; 3~ARP-9-4A window 18, informs SRO.

Recognizes lowering pressure on Recirc Pump A outboard seal; informs SRO Monitors drywell parameters; notes pressure and temperature increasing; informs SRO

)

HLTS-3-2 REV 0 PAGE 28 OF 63 XI. Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram TIME POSITION EXPECTED ACTIONS SRO When vibration report received or dual seal failure is reported, directs

'A' Recirc Pump tripped ATC 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 3AALTERNATE FEEDER, 3-HS-57-15.

4. CLOSE Recirculation Pump 3A suction valve.

- REPORT to SRO of failure of suction valve to close.

)

Directs AUO to close Recirc Pump suction valve locally at Board.

5. CLOSE Recirculation Pump 3A discharge valve.

6.

7. DISPATCH personnel to secure Recirculation Pump 3A seal water.

)

HLTS-3-2 REV 0 PAGE 29 OF 63 XI. Simulator Event Guide (Continued)

)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS ATC [2] Checks Power to flow map to verify in region 1 or 2 Informs SROof being in region 1 Checks APRMs and LPRMs for indication of power oscillations Informs SRO of Power Oscillations SRO Directs inserting emergency shove sheet control rods BOP Keeps SRO informed as drywell pressure approaches 2.45 psig

)

)

HLTS-3-2 REV 0 PAGE 30 OF 63 XI. Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS SRO EXAMINER NOTE: Venting may not be performed based on Drywell pressure.

BOP

[3] VENT Drywell as follows:

[3.1] CLOSE SUPPR CHBR INBD ISOLATION VLV 3-FCV-64-34 (PaneI3-g-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)

)

HLTS-3-2 REV 0 PAGE 31 OF 63 XI. Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS

[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, inOPEN (Panel 3-9-3).

[3.8] MONITOR stack release rates to prevent exceeding ODCM limits.

Directs Logs person to monitor release rates SRO Directs manual reactor scram prior to reaching 2.45psig DW pressure ATC Scrams the reactor

HLTS-3-2 REV 0 PAGE 32 OF 63 XI. Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS SRO ATC Carry out actions of 3-AOI-100-1 SRO SRO l~r_II'i~,',.~II.I"*

• 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-3-2 REV 0 PAGE 33 OF 63 XI. Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS

3. IF ... While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN.

PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.

4. IF ... While executing this procedure, the desired vent path is lost or can not be established, THEN. PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.

BOP 5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4 OR G-9, is to begin, THEN. BEFORE CAD is initiated, PERFORM Step 13 to secure the vent path.

NOTE: Venting may be accomplished using EITHER:

3-FIC-84~19, PATH B VENT FLOW CO NT, 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.

HLTS-3-2 REV 0 PAGE 34 OF 63 XI. Simulator Event Guide (Continued)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS

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-3-2 REV 0 PAGE 35 OF63 XI. Simulator Event Guide (Continued)

')

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CO NT, 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-84-19 CONTROL, in OPEN (Panel 3-9-55).

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

f. CONTINUE in this procedure at step 12.

)

HLTS-3-2 REV 0 PAGE 36 OF 63 XI. Simulator Event Guide (Continued)

)

Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)

TIME POSITION EXPECTED ACTIONS 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:

o Stable flow as indicated on controller, AND o 3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND o Release rates as determined below:

i. IF ... PRIMARY CONTAINMENT FLOODING per C-1, Alternate Level Control, is in progress THEN .. MAINTAIN release rates below those specified in Attachment 2.

ii. IF ...Severe Accident Management Guidelines are being executed, THEN .

.MAINTAIN release rates below those specified by the TSC SAM Team.

iii. IF ...Venting for ANY other reason than items i or ii above, THEN .

.MAINTAIN release rates below 00 Stack release rate of 1.4 x 107 J.lCi/s AND 0-SI-4.8.B.1.a.1 release fraction of 1.

BOP Contacts LOG AUO to monitor release rates

HLTS-3-2 REV 0 PAGE 37 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA TIME POSITION EXPECTED ACTION(S)

SRO - Directs RPV pressure controlled 800 to 1000 psig with one or more of the following:

- Directs RPV level be maintained between +2" to +51" with one or more of the following:

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

-CRD (App 5B)

BOP Controls pressure 800 to 1000 psig with one or more of the following:

1. IF ..... Drywell Control Air is NOT available, THEN ... EXECUTE EOI Appendix 8G, CROSSTIE CAD TO DRYWELL CONTROL AIR, CONCURRENTLY with this procedure.

2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE MSRVs and CONTROL RPV pressure using other options.

HLTS-3-2 REV 0 PAGE 38 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA POSITION EXPECTED ACTIONS BOP 3. OPEN MSRVs using the following sequence to control RPV pressure as directed by SRO:

a.1 3-PCV-1-179 MN STM LINE A RELIEF VALVE.

b. 2 3-PCV-1-180 MN STM LINE D RELIEF VALVE.

c. 3 3-PCV-1-4 MN STM LINE A RELIEF VALVE.

d. 4 3-PCV-1-31 MN STM LINE C RELIEF VALVE.

e. 5 3-PCV-1-23 MN STM LINE B RELIEF VALVE.

f. 6 3-PCV-1-42 MN STM LINE D RELIEF VALVE.

g. 7 3-PCV-1-30 MN STM LINE C RELIEF VALVE.

h. 8 3-PCV-1-19 MN STM LINE B RELIEF VALVE.

i. 9 3-PCV-1-5 MN STM LINE A RELIEF VALVE.

j. 10 3-PCV-1-41 MN STM LINE D RELIEF VALVE.

k. 11 3-PCV-1-22 MN STM LINE B RELIEF VALVE.

I. 12 3-PCV-1-18 MN STM LINE B RELIEF VALVE.

m. 13 3-PCV-1-34 MN STM LINE C RELIEF VALVE.

HLTS-3-2 REV 0 PAGE 390F63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA POSITION EXPECTED ACTIONS BOP Recognizes MSIV closures and reports to SRO.

BOP Controls RPV level +2 to +51 with one or more of the following:

BOP

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-3-2 REV 0 PAGE 40 OF63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA POSITION EXPECTED ACTIONS

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 3Aor 3B.

b. IF ..... CRD Pump 3B is available, THEN ... VERIFY RUNNING CRD Pump 3Aor 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.

BOP Reports 38 CRD pump tripped

HLTS-3-2 REV 0 PAGE 41 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTIONS BOP 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:

D 3-THV-085-0527, CRD PUMP DISCH THROTTLING (RB NE, e1565')

D 3-BYV-085-0551, CRD PUMP TEST BYPASS (RB NE, el 565').

SRO Directs determining the cause of the isolation Directs H2 0 2 Analyzers placed in service BOP Places H20 2 Analyzers in service

1. Place Analyzer isolation bypass keylock switches to bypass.

2. Select DW or Supp Chmbrand momentarily pullout select switch handle to start sample pumps.

HLTS-3-2 REV 0 PAGE 42 OF63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

SRO BOP Places SP cooling in service per App 17A

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 38 RHRSW OUTLET VLV 3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV 3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.

HLTS-3-2 REV 0 PAGE 43 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

d. IF ..... Directed by SRO, THEN ... PLACE the following keylock switches in MANUAL OVERRIDE:

3-XS-74-122, RHR SYS I LPCI2/3 CORE HEIGHT OVRD.

3-XS-74-130, RHR SYS II LPCI2/3 CORE HEIGHT OVRD.

e.IF ..... LPCIINITIATION Signal exists, THEN ... MOMENTARILY PLACE the following in select:

3-XS-74-121, RHR SYS I CTMT SPRAY/CLG VLV SELECT.

3-XS-74-129, RHR SYS II CTMT SPRAY/CLG VLV SELECT.

HLTS-3-2 REV 0 PAGE 44 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP f. IF ..... 3-FCV-74-53(67), RHR SYS 1(11) LPCIINBD 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 CLG/TEST VLV, to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR SYS 1(11) FLOW:

Between 7,000 and 10,000 gpm for one-pump Operation. OR At or below 13,000 gpm for two-pump operation.

j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE (VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),

Compartment 4E(4E), if required).

HLTS-3-2 REV 0 PAGE 45 OF63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

k. MONITOR RHR Pump NPSH using Attachment 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.

ATC/BOP Monitors containment parameters SRO and directs the following:

Verify all available OW coolers in service SRO Directs cooldown ATC/BOP Verify all available DW coolers in service ATC/BOP Commences a cooldown as directed SRO Determines cannot maintain suppression chamber pressure less than 12 psig and directs suppression chamber sprayed

HLTS-3-2 REV 0 PAGE 46 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

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 by EOI-2 to spray the Suppression Chamber irrespective of adequate core cooling, THEN ... BYPASS LPCI Injection Valve Timers as necessary using EOI Appendices 16F and 16G.

3. IF ..... Directed by SRO to spray the Suppression Chamber using Standby Coolant Supply, THEN ... CONTINUE in this procedure at Step 7.

4. IF ..... Directed by SRO to spray the Suppression Chamber using Fire Protection, THEN ... CONTINUE in this procedure at Step 8.

HLTS-3-2 REV 0 PAGE 47 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

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) 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) 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 VLV.

g. OPEN 3-FCV-74-58(72), RHR SYSI(II) SUPPR CHBR SPRAY VALVE.

HLTS-3-2 REV 0 PAGE480F63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP h. IF ..... RHR System 1(11) is operating ONLY in Suppression Chamber Spray mode, THEN ... CONTINUE in this procedure at Step 5.k.

i. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE (VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),

Compartment 4E(4E), if required).

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 1,350 and 4,500 gpm flow:

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

. 3-FCV-23-46, RHR HX 38 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.

HLTS-3-2 REVO PAGE 49 OF 63 XI. Simulator Event Guide (Continued)

(

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP 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 as follows:

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

b. VERIFY CLOSED 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE

c. IF ..... RHR operation is desired in ANY other mode, THEN ... EXIT this EOI Appendix.

d. STOP RHR Pumps 3A and 3C (3B and 3D).

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

HLTS-3-2 REV 0 PAGE 50 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

SRO When SC pressure exceeds 12 psig or if SRO determines cannot maintain OW temp. <280 then directs the following:

- Ensures Recirc. pumps shutdown

- OW blowers secured ATC Trips Recirc. pumps BOP Secures OW blowers Requests 16F & 16G be performed Sprays the DW using RHR 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 LPCllnjection Valve Timers as necessary using EOI App.endices 16F and 16G.

HLTS-3-2 REV 0 PAGE 51 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP 3. VERIFY Recirc Pumps and Drywell Blowers shutdown.

4. IF ..... Directed by SRO to spray the Drywell using Standby Coolant supply, THEN ... CONTINUE in this procedure at Step 8.

5. IF ..... Directed by SRO to spray the Drywell using Fire Protection, THEN ...

CONTINUE in this procedure at Step 9.

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.

HLTS-3-2 REV 0 PAGE 52 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

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

f. OPEN the following valves:

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

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

g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE (VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),

Compartment 4E(4E), if required).

HLTS-3-2 REV 0 PAGE 53 OF63 XI. Simulator Event Guide (Continued)

( EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP 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 1,350 and 4,500 gpm RHRSW flow:

• 3-FCV-23-34, RHRHX 3A RHRSW OUTLET VLV

• 3-FCV-23-46, RHR HX 38 RHRSW OUTLET VLV

• 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.

HLTS-3-2 REV 0 PAGE 54 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

SRO Directs OW sprays/SC sprays be stopped when that area reaches 0 psig BOP Stops DVV/SC sprays when that area reaches 0 psig Monitors containment parameters SRO Monitors RPV water level, determines level is lowering. Re-enters EOI-1 at

+2" RPV level Directs performance of App 7B (SLC)

ATC Calls Rx Bldg AUO to perform App 7B Crew Monitors Drywelll PSC I and RPVwater level SRO Directs ADS inhibited ATC Closes RFP discharge valves Reports 3A CROP tripped

HLTS-3-2 REV 0 PAGE 55 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

BOP Inhibits ADS SRO After entering C1 align all available injection systems for injection.

-Containment sprays terminated When water revel reaches TAF (-162") and before - 200 directs the following:

Enters C2 Six ADS valves opened hi"'iM RPV level returned +2" to +51" BOP When directed by US terminates Containment Sprays and lines up RHR for LPCI BOP Opens and verifies open 6 ADS valves SRO Directs restoring Rx level with Condensate, Core Spray, or RHR SRO Classifies event as Site Area Emergency (1.1-S1)

ATC/BOP Restores RPV water level +2" to +51" using:

-RHR

-Core Spray

-Condensate

HLTS-3-2 REV 0 PAGE 56 OF63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

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-3-2 REV 0 PAGE 57 OF63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

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-3-38, 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

HLTS-3-2 REV 0 PAGE 58 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

6. VERIFY OPEN the following RFP suction valves:

3-FCV-2-83, RFP 3A SUCTION VALVE 3-FCV-2-95, RFP 38 SUCTION VALVE 3-FCV-2-108, RFP 3C SUCTION VALVE.

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-3-2 REV 0 PAGE 59 OF 63 c XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S}

1. VERIFY OPEN the followihg valves:

3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VLV 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 IINBD INJECTVALVE, as necessary to control injection at or below 4000 gpm per pump.

5. MONITOR Core Spray Pump NPSH using Attachment 1.

HLTS-3-2 REVO PAGE 60 OF 63 XI. Simulator Event Guide (Continued)

EVENT 6: MSIV CLOSURE/LOCA (continued)

TIME POSITION EXPECTED ACTION(S)

. . .1_ _111**

1. IF ..... Adequate core cooling is assured AND It becomes necessary to bypass LPCI Injection Valve Timers to control injection, THEN ... EXECUTE EOI Appendix 16F concurrently with this procedure

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 DW SPRAY INBD VLV 3-FCV-74-60, RHR SYS I DW SPRAY OUTBD 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 VLV.

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.

7. IF ..... RPV pressure is below 230 psig, THEN ... VERIFY CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE.

HLTS-3-2 REV 0 PAGE 61 OF 63 XII. Crew Critical Tasks

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

2) Emergency depressurizes RPV based upon not being able to maintain reactor water level above -162, but before reaching - 200"

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

HLTS-3-2 REV 0 PAGE 62 OF 63 XIII. SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS-3-2

~ Total Malfunctions Inserted; List: (4-8)

1) HPCI steam line break

2) RBCCW 3A pump trips

3) 3A Recirc. high vibration

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

5) Failure of ADS/SRV 1-22

6) Drywell Leak

7) CRD pump 3B fails to start

8) CRD pump 3A trips

9) RCIC 71-8 fails to open L 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 L. Abnormal Events; List: (1-3)

1) SRV fails open

2) HPCI steam line break L Major Transients; List: (1-2)

1) Loss of all high pressure makeup

2) Drywell Leak

...l... EOls used; List: (1-3)

1) EOI-1

2) EOI-2

3) EOI-3 L EOI Contingencies Used; List: (0-3)

1) C1

2) C2 90 Run Time (minutes) 45 EOI Run Time (minutes); 50 % of Scenario EOI Run Time

...L Crew Critical Tasks (2-5)

Yes Technical Specifications Exercised (yes/no) - Technical Requirements Manual

XIV. Shift Turnover Information Equipment out of service/LCOs: 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 2 is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> into a seven day LCO.

Appendix R LCO addressed and in LCO tracking.

Operation/Maintenance for the Shift: Unit 3 is at 79% power, Alternate EHC Pumps per section of 01 47A. Increase reactor power to 85% using Recirc flow (GOI~ 100-12,step 5.132) with no pre-conditioning limitations. Reactor Engineering will evaluate any further power changes.

Continue with 3-SR-3.5.1. 7 which 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 II RHR has been placed in Torus cooling and 3-SR-3.6.2.1.1 needs to be started 5 minutes before starting HPCI. Units 1 & 2 are at 100% power ..

Unusual Conditions/Problem Areas: 3-FCV-73-36 seal-in circuit has been disabled per step 7.6 of 3-SR-3.5.1.7

(

c.

BFN HPCI Main and Booster Pump Set 3-SR-3.S.1.7 Unit 3 Developed Head and Flow Rate Test at Rev. 0047 Rated Reactor Pressure Page 47 of 101 Date 7.4 HPCI Main Pump and Booster Pump Testing (continued)

[11] RECORD following data:

Indicated Acceptable Parameter/Indicator Value Range HPCI SYSTEM FLOW gpm  ;::: 5,000 gpm 3-FIC-73-33 or ICS HPCI PUMP DISCH PRESS  ;:::

psig 3-PI-73-31A (Step 7.4[1.3])

HPCI TURBINE SPEED rpm  ;::: 2,400 rpm 3-SI-73-51

.HPCI TURB EXH PRESS psig ~ 40 psig 3-PI-73-21A REACTOR WIDE RANGE  ;::: 950 psig psig PRESS A 3-PI-3-54 ~ 1040 psig

_ _ (AC)

[12] RECORD following data:

Indicated Acceptable Parameter/Indicator Value Range HPCI PUMP SUCT Press psig  ;::: 10 psig 3-PI-73-28A

BFN HPCI Main and Booster Pump Set 3-SR-3.S.1.7 Unit 3 Developed Head and Flow Rate Test at Rev. 0047 Rated Reactor Pressure Page 48 of 101 Date 7.4 HPCI Main Pump and Booster Pump Testing (continued)

CAUTION The HPCI pump set differential pressure is very sensitive to minor turbine speed and pump set flow adjustments. Therefore, it is anticipated that the UO will be required to make minor speed and flow rate adjustments in order to properly establish the ASME OM Code operating point.

[13] PLACE HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 in MANUAL as follows:

DEPRESS the MANUAL operation mode transfer switch on 3-FIC-73-33.

[14] ADJUST HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 MANUAL operation lever, until approximately 3800 rpm on HPCI TURBINE SPEED 3-SI-73-51.

[15] ADJUST HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 MANUAL operation lever, to achieve 3790 to 3810 rpm turbine speed, using hand held tachometer.

RECORD final turbine speed below:

HPCI Turbine Speed (M&TE) rpm

[16] VERIFY HPCI test condition flow rate as follows:

[16.1] IF ICS is utilized to obtain HPCI flow rate data, THEN CHECK that no gross instrument channel failures have occurred by noting that ICS-displayed HPCI flow rate is within 100 gpm of flow rate indicated on H PCI SYSTEM FLOW/CONTROL 3-FIC-73-33. (Otherwise N/A)

BFN HPCI Main and Booster Pump Set 3-SR-3.S.1.7 Unit 3 Developed Head and Flow Rate Test at Rev. 0047 Rated Reactor Pressure Page 49 of 101 Date 7.4 HPCI Main Pump and Booster Pump Testing (continued)

[16.2] THROTTLE 3-FCV-73-35, using HPCI PUMP CST TEST VL V, 3-HS-73-35A to obtain either of the following:

• An ICS display reading of 4950 to 5050 gpm.

• 495 to 505 (4950 to 5050 gpm) as indicated on HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33

[17] ALLOW HPCI pump set to operate until steady-state conditions are achieved, THEN VERIFY conditions of Steps 7.4[15] and 7.4[16] are met.

NOTE The indicator on 3-PI-73-31 B may oscillate due to pump generated pressure pulses.

Should this condition exist, an average between the predominate high and low readings should be recorded as the indicated value.

[18] OBTAIN the HPCI pump data as follows:

[19] On Panel 3-LPNL-25-0050 PERFORM the following:

[19.1] OBSERVE 3-PI-73-31 B, while performing the following to verify unobstructed instrumentation.

CLOSE and OPEN PANEL ISOL VLVTO 3-PI-73-31B, 3-PISV-73-9013 several times.

[19.2] IF required to stabilize 3-PI-73-31 B indicator, THEN THROTTLE PANEL ISOL VLVTO 3-PI-73-31B, 3-PISV-73-9013, as required to stabilize 3-PI-73-31 B.

(Otherwise N/A)

BFN HPCI Main and Booster Pump Set 3-SR-3.5.1.7 Unit 3 Developed Head and Flow Rate Test at Rev. 0047 Rated Reactor Pressure Pa~e 50 of 101 Date 7.4 HPCI Main Pump and Booster Pump Testing (continued)

NOTE HPCI pump discharge pressure has no required range because it is a function of pump speed and flow.

[20] COMPLETE following table entries stipulated below:

Indicated Required Parameterllndicator Value Value HPCI SYSTEM FLOW gpm 4,950-3-FIC-73-33 or ICS 5,050 gpm HPCI MAIN PUMP DISCH psig SEE NOTE PRESS 3-PI-073-0031 B ABOVE (HPCI RM)

HPCI TURBINE SPEED rpm 3790-3810 HAND-HELD rpm TACHOMETER HPCI TURB EXH PRESS psig ~ 40 psig 3-PI-73-21A REACTOR WIDE RANGE psig  ;:::: 950 psig PRESS A 3-PI-3-54

~ 1040 psig HPCI PUMP SUCTION psig  ;:::: 10 psig PRESS 3-PI-073-0028B (HPCI RM)

_ _(AC)

(\~

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT SURVEILLANCE PROCEDURE 3-SR-3.S.2.1.1 SUPPRESSION CHAMBER WATER TEMPERATURE CHECK REVISION 3 QUALITY RELATED PREPARED BY: Keith Smith RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: TONY ELMS

~~--~-----------------------------

EFFECTIVE DATE: 08/06/2003 LEVEL OF USE: CONTINUOUS USE

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT3 TEMPERATURE CHECK Rev 0003 PAGES AFFECTED: 4, 6, 11, REVISION DESCRIPTION: IC PER 03-011119-000 Page 4 Added step 3.6, explaining the reason the Suppression Pool Cooling should be minimized.

Page 6, Step 7.5, added reference to step 3.6.

Page 11, Added, steps 7.11 and 7.12, to remove the suppression pool cooling. This is to minimize the time that suppression pool temperature is in service.

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT3 TEMPERATURE CHECK Rev 0003 c Page 1 of 15

1.0 INTRODUCTION

1.1 Purpose This procedure is performed to monitor the Suppression pool average temperature in conformance with the requirements specified in Technical Specifications 3.6.2.1.

1.2 Scope This procedure documents the surveillance requirements for suppression pool average temperatures and verification of frequency for different LCO requirements of Suppression pool average temperatures. This procedure monitors suppression pool average temperature while performing testing that adds heat to the suppression pool and also while not performing testing that adds heat to the suppression pool. This procedure is performed in conjunction with 3-SR-2 to fully satisfy SR 3.6.2.1.1.

1.3 Frequency Surveillance Requirement 3-SR-3.6.2.1.1 is to be performed every 5 minutes when performing testing that adds heat to the suppression pool.

LCO 3.6.2.1 A.1 for Suppression pool average temperature ,>95 of but:::; 110°F, and not performing testing that adds heat to the suppression pool, requires verification of temperature once per hour LCO 3.6.2.1.A.2 for Suppression pool average temperature ,>95 of but:::; 110°F, and not performing testing that adds heat to the suppression pool, has a required action to Restore suppression pool average temperature to :::; 95°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

LCO 3.6.2.1.0.2 for Suppression pool average temperature,>11 0 of but:::; 120°F, requires verification that suppression pool average temperature :::; 120°F Once per 30 minutes.

1.4 Applicability MODES 1,2, and 3.

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERATURE CHECK Rev 0003 Page 2 of 15 2.0 References 2.1 Technical Specifications.

Section 3.6.2.1 Suppression Pool Average Temperature Section 3.6.2.2 Suppression Pool Water Level Section 3.6.2.6 Drywell to Suppression Chamber Differential pressure 2.2 FSAR Section 5.2 Section 14.6 2.3 Plant Instructions 3-EOI-2, Primary Containment Control.

3-01-71, RCIC System Operating Instruction.

3-01-73, HPCI System Operating Instruction.

3-01-74, RHR System Operating Instruction.

3-SR-2, Instrument Checks and Observations.

SPP-S.1, Conduct of Testing.

2.4 Plant Drawings 3-47E61 0-64-1, Mechanical Control Diagram - Primary Containment.

3-47E61 0-64-3, Mechanical Control Diagram - Primary Containment.

2.5 Other Documents GE SIL No.1 06 R2, Suppression Pool Temperature Monitoring and Control.

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT3 TEMPERATURE CHECK Rev 0003 Page 3 of 15 3.0 Precaution and Limitations 3.1 The following instrumentation shall be used for performance of this Surveillance Procedure:

3.1.1 Suppression pool temperature:

• At Panel 3-9-3, SUPPR POOL BULK TEMP, 3-TI-64-161, and SUPPR POOL BULK TEMP, 3-TI-64-162.

• At Panel 25-32, SUPPR POOL TEMPERATURE, 3-TI-64-558.

3.1.2 Suppression pool level:

• At Panel 3-9-3, SUPPR POOL WATER LEVEL, 3-Ll-64-54A,

• SUPPR POOL WATER LEVEL, 3-Ll-64-66.

3.1.3 Drywell to suppression chamber differential pressure:

• At Panel 3-9-3, DW/SUPPR CHBR DIFF PRESS, 3-PDI-64-137, or

• DW/SUPPR CHBR DIFF PRESS, 3-PDI-64-138.

3.1.4 Suppression Chamber Air Temperature:

At Panel 3-9-3, Suppression Chamber Temperature/Pressure, 3-XR-64-52 (Red Pen).

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERATURE CHECK Rev 0003

( Page 4 of 15 3.2 Drywell to Suppression chamber differential pressure may fall below 1.1 psid during heat addition.

3.3 [NER/C] If RHR Suppression Pool Cooling is not in service, a potential for thermal stratification during ECCS component and relief valve testing exists. Monitoring the suppression pool using 3-TI-64-55B and 3-XR-64-52 (Red Pen) can give indication of potential thermal stratification. Increases in the difference between bulk temperature and these indicators may require Suppression Pool Cooling to obtain a valid temperature reading. [GE SIL 106 R2]

3.4 Tech Specs 3.6.2.1 requires entry into an LCO if Suppression Pool temperature is:

• Greater than 95°F with no testing being performed which adds heat to the Suppression Pool.

or

• Greater than 105°F with testing being performed which adds heat to the Suppression Pool.

3.5 When Suppression Pool temperature is greater than 95°F but less than 105°F, while performing testing that adds heat to the Suppression pool, then the Tech Spec LCO 3.6.2.1 may be entered after removing the heat source from to the Suppression pool. (i.e. HPCI, RCIC and SRV's.)

Tech Spec requires stopping any tests that is adding Heat to the Suppression Pool if Suppression Pool Temp is greater than 105°F.

3.6 Suppression Pool Cooling should be minimized per 3-01-74. This is based upon water hammer on pump restart during a Station Blackout and a DBA LOCA, caused by draining portion of the system while in Suppression Pool Cooling. Therefore the time Suppression Pool Cooling is in service goes against the Safety Analysis time allowance.

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERATURE CHECK Rev 0003 Page 5 of 15

(

DATE ____________

INITIALS 4.0 PREREQUISITES 4.1 This copy of 3-SR-3.6.2.1.1 is verified the most current revision.

4.2 This procedure should be performed by the UO or his designee.

5.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED None.

6.0 ACCEPTANCE CRITERIA 6.1 Responses which fail to meet the following acceptance criteria shall constitute unsatisfactory surveillance procedure results and require immediate notification of the Unit Supervisor at the time of failure.

6.1.1 When performing testing that adds heat to the suppression pool, verify suppression pool average temperature is within the applicable limits. The pool temperature shall be verified < 105°F and logged every 5 minutes until the heat addition is terminated.

6.1.2 Suppression pool average temperature shall be restored to ::; 95°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of exceeding 95 of when not performing testing that adds heat to the suppression pool.

6.1.3 Suppression pool average temperature shall be verified::; 110°F once per hour when suppression pool average pool temperature> 95 of but::; 110°F.

6.1.4 Suppression pool average temperature shall be verified::; 120°F once per 30 minutes when Suppression pool average temperature >11 OaF but::; 120°F 6.2 Steps which determine the above criteria are deSignated by (AC) next to the initials blank.

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT3 TEMPERATURE CHECK Rev 0003 Page 6 of 15 DATE ____________

INITIALS 7.0 PROCEDURE STEPS 7.1 All Precautions and Limitations in Section 3.0 have been reviewed.

7.2 All Prerequisites listed in Section 4.0 have been satisfied.

7.3 RECORD the date and time started, reason for test, and plant conditions on Attachment 1, Surveillance Procedure Review Form.

7.4 MONITOR suppression pool average temperature, suppression pool level, and drywell to suppression chamber differential pressure.

7.5 VERIFY suppression pool cooling is in service per 3-01-74.

(REFER TO step 3.6.)

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT3 TEMPERATURE CHECK Rev 0003 Page 7 of 15 DATE ____________

INITIALS NOTE:

Steps 7.6, 7.7, 7.8, 7.9, 7.10 shall be performed concurrently during the performance of this procedure.

7.6 IF any test that adds heat to the Suppression Pool is being performed, THEN:

MONITOR Suppression Pool Average Temperature as follows:

(Otherwise NtA this section.)

7.6.1 On Attachment 2, using Suppression Pool Average Temperatures 3-TI-64-161 and 3-TI-64-162. (Use additional copies of Attachment 2 as necessary.)

• INITIATE and RECORD Data in Table 1.1 every five minutes during heat addition.

VERIFY suppression pool average temperature :s; 105°F by initialing on Attachment 2. _ _ _ (AC) 7.6.2 IF Suppression Pool average temperature:2 105°F, THEN PERFORM the following: (Otherwise NtA.)

7.6.2.1 SUSPEND all testing that adds heat to the suppression pool immediately. _ _ _ (AC) 7.6.2.2 RECORD the date and time on Attachment 2 Step C.

ENTER Tech Spec LCO.

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERATURE CHECK Rev 0003 Page 8 of 15 DATE ____________

INITIALS NOTES:

1) Steps 7.6, 7.7, 7.8, 7.9, 7.10 shall be performed concurrently during the performance of this procedure.

2) Section 7.7 may be marked N/A if Suppression Pool Cooling is in service and table 1.2 on Attachment 2.

7.7 IF any test that adds heat to the Suppression Pool is being performed, THEN:

[NER/C] MONITOR for thermal stratification.

(N/A this section if suppression pool cooling is in service.)

7.7.1 On Attachment 2,

( INITIATE and RECORD data in Table 1.2 every 15 minutes, (Use additional copies of Attachment 2's as necessary.)

[GE SIL 106 R2]:

• Suppression Pool Temperature using 3-TI-64-55B on Panel 3-25-32.

• Suppression Chamber Air Temperature using 3-XR-64-52 Red Pen on Panel 3-9-3.

7.7.2 COMPARE the four temperature readings taken on table 1.1 (step 7.6.1) and table 1.2 (step 7.7.1), that corresponds to the 15 minute time interval of step 7.7.1 on Attachment 2.

7.7.3 IF any instrument reading deviates more than 10°F from another instrument reading, THEN INFORM the Unit Supervisor that temperature stratification (localized heating) may be occurring.

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERATURE CHECK Rev 0003 Page 9 of 15 DATE ____________

INITIALS NOTES:

1) Steps 7.6, 7.7, 7.8, 7.9, 7.10 shall be performed concurrently during the performance of this procedure.

2) Step 7.8.1 will be met if section 7.6 is being performed and monitoring every 5 minutes as required.

7.8 WHEN Suppression Pool average temperature becomes> 95°F, THEN PERFORM the following: (N/A this section and Attachment 2 Step A and Step B, if 95°F average Suppression Pool temperature was never exceeded.)

7.8.1 On Attachment 2, Table 1.1 Suppression Pool Average Temperatures 3-TI-64-161 and 3-TI-64-162.

(Use additional copies of Attachment 2 as necessary.).

• INITIATE and RECORD the Suppression Pool Average Temperatures data Once per hour.

And VERIFY suppression pool average temperature :-:; 11 OaF by initialing on Attachment 2. _ _ _ (AC) 7.8.2 RECORD on Attachment 2 the condition that applies

• IF NO testing is being performed that adds heat to the Suppression Pool, THEN RECORD the time and date on Attachment 2 Step A when the Suppression Pool average temperature becomes greater than 95°F and ENTER Tech Spec LCO.

(Otherwise N/A this step and N/A Attachment 2 Step A)

• IF testing that does add heat to the Suppression Pool is being performed, THEN RECORD the time and date that the test is secured on Attachment 2 Step B and ENTER Tech Spec LCO.

(Otherwise N/A this step and N/A Attachment 2 Step B.)

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERA TURE CHECK Rev 0003 Page 10 of 15 DATE ____________

INITIALS NOTE:

Steps 7.6, 7.7, 7.8, 7.9, 7.10 shall be performed concurrently during the performance of this procedure.

7.9 WHEN Suppression pool average temperature is greater than 110°F, THEN:

PERFORM the following: (Otherwise N/A this section and N/A Attachment 2 Step E.)

7.9.1 RECORD Time/Date Suppression pool average temperature exceeds 110°F on Attachment 2 Step E.

7.9.2 VERIFY suppression pool average temperature:s; 120°F Once per 30 minutes and Log on Attachment 2 .

7.9.3 PLACE Reactor in MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. _ _ _ (AC)

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT3 TEMPERATURE CHECK Rev 0003 Page 11 of 15 OATE ____________

INITIALS NOTE:

Steps 7.6, 7.7, 7.8, 7.9, 7.10 shall be performed concurrently during the performance of this procedure.

7.10 WHEN Suppression Pool average temperature is restored to less than 95°F, THEN PERFORM the following: (N/A this section and Attachment 2, Step 0, if 95°F average Suppression Pool temperature was never exceeded.)

7.10.1 RECORD the time and date on Attachment 2, Step O.

7.10.2 CALCULATE time above 95°F by using times recorded in Steps 7.10.1 and the condition that applies in step 7.8.2:

Time above 95°F- - - - - -

7.10.3 VERIFY time above 95°F is less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(REFER TO Attachment 2.) _ _ _ (AC) 7.11 WHEN desired Suppression Pool Temperature is achieved as determined by the Unit Supervisor, THEN SECURE Suppression Pool Cooling per 3-01-74. (REFER TO step 3.6.)

(N/A if suppression Pool Cooling will remain in service for another test.)

7.12 IF Suppression Pool Cooling is to remain in service, THEN RECORD in Post Test Remarks and Narrative Logs the reason system will remain in service. (Otherwise N/A.)

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERATURE CHECK Rev 0003 Page 12 of 15 DATE ____________

INITIALS 7.13 COMPLETE Attachment 1, Surveillance Procedure Review Form up to Unit Supervisor Review.

7.14 NOTIFY Unit 3 Operator this procedure is complete.

7.15 NOTIFY Unit Supervisor that this procedure is complete and provide status of any Corrective Actions or unsatisfactory performance.

( 8.0 ILLUSTRATIONS/ATTACHMENTS 8.1 Attachment 1 - Surveillance Procedure Review Form.

8.2 Attachment 2 - Suppression Pool Average Temperature Log.

END OF TEXT

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERATURE CHECK Rev 0003 Page 13 of 15 ATTACHMENT 1 (Page 1 of 1)

SURVEILLANCE PROCEDURE REVIEW FORM REASON FOR TEST: DATEITIME STARTED_ _ _ _ _ __

--- Scheduled Surveillance DATE/TIME COMPLETED_ _ _ _ __

_ _ _ System Inoperable (Explain in Remarks) PLANT CONDITIONS _ _ _ _ _ __

_ _ _Maintenance (WO No. )

_ _ _Other (Explain in Remarks)

PRE-TEST REMARKS: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

PERFORMED BY:

Initials Name (Print) Name (Signature)

(Test Dir/Lead Perf)

(Test Dir/Lead Perf)

Delays or Problems (If yes, explain in POST-TEST REMARKS)? Yes No Acceptance Criteria Satisfied? __Yes No If the above answer is no, the Unit Supervisor shall determine if an LCO exists. LCO __Yes No UNIT SUPERVISOR_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date_ _ _ _ __

=============================================================

INDEPENDENT REVIEWER (SRO) _ _ _ _ _ _ _ _ _ _ _ Date_ _ _ _ __

=============================================================

SCHEDULING COORDINATOR'---_ _ _ _ _ _ _ _ _ _ _ Date_ _ _ _ __

=============================================================

POST-TEST REMARKS: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERA TURE CHECK Rev 0003 Page 14 of 15 ATTACHMENT 2 (Page 1 of 2)

SUPPRESSION POOL AVERAGE TEMPERATURE LOG Table 1.1 Table 1.2 3-XR-64-52 3-TI-64-161 3-TI-64-162 INITIALS 3-TI-64-55B (Red Pen)

(Suppr Pool (Suppr Pool (AC) (Suppr Pool (Suppr Chamb TIME Ave Temp) Ave Temp) Note 2 TIME Temp) Air Temp) INITIALS NOTES:

1) The SRO shall be notified if any temperature difference differs by more than 10 a F.

2) Initials verifies the following:

• Temperature less than 105°F when performing tests which adds heat to the suppression pool.

• Temperature less than 110°F when NOT performing tests which adds heat to the suppression pool.

• If temperature is >11 O°F verify temperature is less than 120°F and be in mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> per section 7.9.

BFN SUPPRESSION CHAMBER WATER 3-SR-3.6.2.1.1 UNIT 3 TEMPERATURE CHECK Rev 0003 Page 15 of 15 ATTACHMENT 2 (Page 2 of 2)

SUPPRESSION POOL AVERAGE TEMPERATURE LOG Record the time and Date for the following conditions as required from the appropriate steps.

A) [Step 7.8.2] Time/Date Suppression Pool average temperature exceeded 95°F while not performing any tests that adds heat to the suppression pool. (N/A if not applicable.) /

Time Date B) [Step 7.8.2] Time/Date when the testing that adds heat to the Suppression Pool is secured with the average Suppression Pool temperature greater than 95°F. (N/A if not applicable.) /

Time Date C) [Step 7.6.2.2] Time/Date Suppression Pool average temperature exceeded 105°F while performing testing that adds heat to the suppression pool. (N/A if not applicable.) /

Time Date D) [Step 7.10.1] Time/Date Suppression Pool average temperature restored below 95°F. (N/A if not applicable.) /

Time Date E) [Step 7.9.1] Time/Date Suppression pool average temperature exceeded 110 of. (N/A if not applicable. ) /

Time Date

HLTS-3-5 Revision 0 Page 1 of 24 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 Have Off-Site power availability SR available.

DATE  : October 8, 2008 PROGRAM  : BFN Operator Training PREPARED BY: I (Operations Instructor) Date REVIEWED BY: I

( Lead Examiner or Designee) Date REVIEWED BY: I (Operations Training Manager or Designee) Date CONCURRED I (Operations Superintendent or Designee) Date VALIDATION I BY (Operations SRO:

Required for Exam Scenarios Only) Date

HLTS-3-5 Revision 0 Page 2 of 24

(

NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION DESCRIPTION DATE PAGES REVIEWED BY NUMBER OF AFFECTED REVISION 0 INITIAL 10108/2008

HLTS-3-5 Revision 0 Page 3 of 24 I. Program: BFN Operator Training II. Course: Examination Guide III. Lesson

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 Lesson: 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> V. Examination Objectives A. Terminal Objectives

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, abnormal, annunciator and emergency procedures.

4. Use step text procedural compliance (WANO).

HLTS-3-5 Revision 0 Page 4 of 24

8. 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 respond to an un-isolable EHC Leak and manually scram the reactor.

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

HLTS-3-5 Revision 0 Page 5 of 24 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 Sheet C. Stopwatch D. Hold Order / Caution tags E. Annunciator window covers F. Steam tables

HLTS-3-5 Revision 0 Page 6 of 24 VIII. Console Operators Instructions A. Scenario File Summary MF/RF/IOR# Description File: bat HLTS 3-5

a. bat atws95east ATWS

b. imf th23 (e1 1:00) 20 4:00 Fuel failure File bat HLTS 3-5-1

a. mrf dg01 a open Open 3EA DG logic breaker

b. mrf dg04a stop locally stop 3EA DG File bat SGT_Stop

a. mrf pc01 a stop

b. mrf pc01 b stop

c. mrf pc01 c stop

HLTS-3-5 Revision 0 Page 7 of 24 VIII. Console Operators Instructions G. Console Operators Manipulations ELAPTIME IC/MF/RF DESCRIPTIONIACTION Sim. Setup IC-26 73% power MOC (Snap 247)

Sim. Setup See Scenario Summary (bat HLTS3-5)

Sim. Setup manual Verify 3A CRD pump OOS and 3B CRD pump liS 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 HL TS3-5-3)

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

CREV:

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

Instrument Room:

HLTS-3-5 Revision 0 Page 8 of 24 VIII. Console Operators Instructions

8. Console Operators Manipulations ELAPTIME 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 (mrf th18b 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: 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-3-5 Revision 0 Page 9 of 24 VIII. Console Operators Instructions C. Console Operators Manipulations 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-3-5 Revision 0 Page 10 of 24 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-3-5 Revision 0 Page 11 of 24

x. Information to Evaluators:

A. Ensure recorders are inking and recording and ICS is active and updating.

B. Assign Crew Positions based on the required rotation.

1. SRO: Shift Manager/Unit Supv.

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator C. Conduct a shift turnover with the Shift Manager and provide the Shift Manager with a copy of the Shift Turnover.

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

E. Terminate the scenario when the following conditions are satisfied are at the request of the floor/lead instructor/evaluator.

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-3-5 Revision 0 Page 12 of 24 XI. Simulator Event Guide EVENT 1: Place- 38 RFP back in service and increase Rx power with control rod withdrawal and Recirc flow increase.

POSN TIME EXPECTED ACTIONS SRO Directs placing 38 RFP back in service per 3-01-3 section 5.7 BOP Piaces2B RFP back in service iaw 3-01-3 section 5.7

• Closes 3-FCV-6-125, LP above seat drains

• Closes 3-FCV-6-126, LP below seat drains

• Closes 3-FCV-6-127, HP above seat drains

• Closes 3-FCV-6-128, HP below seat drains

• Closes 3-FCV-6-129, 1st stage drains Calls AUO to close 3-6-155 and 3-6-156 ATC Performs peer check of RFP return to service 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: 3B RFP returned to service and all remaining control rods have been withdrawn.

HLTS-3-5 Revision 0 Page 13 of 24

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~

XI. Simulator Event Guide EVENT 2: Loss of 4KV Shutdown Board "3EA" (Bus Lockout)

POSN TIME EXPECTED ACTIONS CREW Identifies/Reports a loss of 4KV SID Board "3EA" BOP Recognizes 3EA DIG starts and fails to load BOP Attempts to load DG by placing O-HS-211-A-22A in close and recognizes failure to close ATC Recognizes 3B CRD pump trip Crew Identifies loss of power to RHR 3A, CS 3A, and RHRSW A3.

Crew Identifies loss of power to 3A RBCCW pump and closure of 70-48 sectionalizing valve.

Crew Identifies loss of operating SJAE.

Crew Identifies RWCU pumps tripped due to NRHX high temperature.

Crew Identifies loss of Fuel Pool Cooling Pump 3A.

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

HLTS-3-5 Revision 0 Page 14 of 24 XI. Simulator Event Guide EVENT 3: System Restoration following 4KV SO Board 3EA loss POSN TIME EXPECTED ACTIONS SRO Directs placing 3A CRD pump in service per 3-AOI- 85-3 ATC Places 3-FIC-85-11in Man. and Minimum Starts 3A CRD pump 3-HS-85-1A in start Adjusts 3-FIC-85-11 to establish Delta-P, Flow Places 3-FIC-85-11 in Auto 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 BOP Verifies all SGT starts and Refuel Ventilation isolates BOP Directs AUO to shutdown DG "3EA" per 01-82 SRO Directs SBGT and Ventilation restored to normal after BOP transfers 3A SID bd to alt and restores RPS BOP Utilizes 3-AOI-64-2D to restore ventilation.

Takes 3-HS-64-3A to off then back to either SLOW A or SLOWB ATCI Restores RBCCW and re-opens 70-48 per 3-01-70.

BOP ATCI Restores RWCU to operation per 3-01-69.

BOP BOP Restores SJAE per 3-01-66 BOP Restores Fuel Pool Cooling per 3-01-78 Event Terminus: Tech. Specs addressed and systems returned to normal

HLTS-3-5 Revision 0 Page 15 of 24 XI. Simulator Event Guide EVENT 4: Low Oil Level on 38 Core Spray pump POSN TIME EXPECTED ACTIONS SRO Recognizes Tech Spec operability issue with low oil level on 38 Core Spray pump.

SRO Addresses Tech Spec section 3.S.1.H.1 and determines that 3.0.3 must be entered immediately.

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

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

SRO 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-3-5 Revision 0 Page 16 of 24 XI.. Simulator Event Guide EVENT 5: Inadvertent HPCI initiation without a valid signal POSN TIME EXPECTED ACTIONS BOP Recognizes and responds to an inadvertent HPCI initiation and reports itto the SRO.

BOP 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.

SRO Addresses Tech Spec section 3.5.1.D and determine that HPCI must be returned to service in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with 3A RHR and 3A Core Spray INOPERABLE.

SRO Directs Instrument Mechanics to investigate the HPCI initiation logic.

HLTS-3-5 Revision 0 Page 17 of 24 XI. Simulator Event Guide EVENT 6: EHC LEAK! SCRAM POSN TIME EXPECTED ACTIONS BOP Recognizes and reports "EHC Reservoir Level Low "Alarm BOP Responds per ARP 3-XA-55-7B BOP Monitors EHC pump for fluctuations in amperage and pressure SRO Dispatches AUO's to add fluid and find leak SRO Contact Environmental to help contain EHC fluid SRO Directs Radwaste to lockout floor and equipment drain sumps ATC! Reports low EHC pressure BOP SRO Directs ATC to insert manual Scram and enter AOI-100-1 Directs BOP to trip turbine and lockout EHC pumps ATC Inserts Manual Scram and takes actions per 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

HLTS-3-5 Revision 0 Page 18 of 24 XI. Simulator Event Guide Event 7: ATWS I FUEL FAILURE POSN EXPECTED ACTIONS 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 SRMsIIRMs 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 tripped SRO Directs ADS inhibited BOP Inhibits ADS SRO Directs appendix 4 to lower water level until level < -50" ATC Lowers RFP speed to 600 RPM or until level reaches -50" BOP Performs Appendix 4, locks out HPCI

HLTS-3-5 Revision 0 Page 19 of 24 XI. Simulator Event Guide Event 7: ATWS I FUEL FAILURE (continued)

POSN EXPECTED ACTIONS SRO Directs Appendix 1F, 2, and 1D be performed SRO Directs 8A, 8E be performed BOP Recognizes turbine trip and loss of Bypass valves as accumulators depressurize SRO Directs reactor pressure maintained less than 1073 psig with one or more of the following:

- MSRV's

- Main steam line drains

- RFP's BOP Reports Torus temp >95 and or drywell pressure above 2.45 psig (if applicable)

SRO Enters EOI-2 and directs all available SIP cooling placed in service per Appx. 17A and directs venting per Appx. 12 Reports TB High Rad'n alarm and evacuates appropriate BOP areas Reports OG Pretreatment Rad High Alarm BOP Maintains reactor pressure less than 1073 with one or more of the following:

- MSRV's

- Main Steam Line drains (App 11 D)

- RFP (App 11 F)

ATC DirectsAUO to close 3-85-586 per Appendix 1D if necessary SRO Directs SLC Injection before Torus Temperature reaches 110 deg F ATC Injects SLC per Appx. 3A

HLTS-3-5 Revision 0 Page 20 of 24 XI. Simulator Event Guide Event 7: ATWS I FUEL FAILURE (continued)

POSN EXPECTED ACTIONS 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 BOP Places suppression pool cooling in service per appendix 17A ATC When 3-85-586 closed or scram reset, Bypasses RWM, Drives rods utilizing EMERGENCY IN in a spiral manner per Appendix 1D ATC Resets scram, Verifies SDV vents and drains open, Monitors SDV High level alarms ATC After SDV drained the BUO directs the 3-85-586 valve opened, and inserts another manual scram after all the accumulators have recharged per appendix 1F ATC 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%.

HLTS-3-5 Revision 0 Page 21 of 24 XI. Simulator Event Guide Event 7: ATWS I FUEL FAILURE (continued)

POSN EXPECTED ACTIONS SRO Directs RPV level restored and maintained + 2" to + 51" RWL SRO Directs termination of SLC injection if the system was initiated ATC Maintains RPV level within band as directed by SRO SRO Declares a Site Area Emergency per EPIP-1 EAL 1.2-S

HLTS-3-5 Revision a Page 22 of 24 XI. Simulator Event Guide 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 deg F Torus temperature per RC/Q.

HLTS-3-5 Revision 0 Page 23 of 24 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS-3-5

~ Total Malfunctions Inserted; List: (4-8)

1. Loss of 4KV Shutdown Board

2. Inadvertent HPCI initiation

3. EHC Leak

4. ATWS

5. Fuel Failure

_1_ Malfunctions That Occur After EOI Entry; List: (1-4)

1. 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 L EOls 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); 46.6 % of Scenario EOI Run Time

~ Crew Critical Tasks Yes Technical Specifications Exercised (yes/no)

Revision 0 Page 24 of 24 SHIFT TURNOVER SHEET Equipment Out of Service/LCOs 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. The 38 RFP was leaking at approximately 1 gallon every 30 minutes.

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 Recirc flow per 3-GOI-100-12 step 5 [17.5]

Unusual Conditions/Problem Areas Remnants of Hurricane Hermon will pass thru this area today, severe weather is possible.

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Browns Ferry Nuclear Plant Unit 3 Surveillance Procedure 3-SR-3.8. 7.1 Weekly Check of Power Availability to Required AC and DC Power Distribution Subsystems Revision 0011 Quality Related Level of Use: Continuous Use Effective Date: 11-04-2007 Responsible Organization: OPS, Operations Prepared By: Michael S. Rice Approved By: John T. Kulisek

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit 3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 2 of 14 Current Revision Description Pages Affected: All Type of Change: XP conversion Tracking Number: 013 PCRs: 07000440 This procedure has been converted from word 95 to word 2003 (XP) using Rev 10.

(PCR 07000440)

Minor editorial changes throughout. No rev bars.

Added step 7.0[3] to notify the Unit Operator the test is about to commence to provide consistency with other procedures.

Added SR key number to Attachment 1 for scheduling.

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit 3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 3 of 14 Table of Contents

1.0 INTRODUCTION

.......................................................................................................... 4 1.1 Purpose ........................................................................................................................ 4 1.2 Scope ............................................................................................................................ 4 1.3 Frequency ..................................................................................................................... 4 1.4 Applicability ................................................................................................................... 4

2.0 REFERENCES

............................................................................................................. 5 2.1 Technical Specifications ............................................................................................... 5 2.2 UFSAR .......................................................................................................................... 5 2.3 Plant Instructions .......................................................................................................... 5 2.4 Plant Drawings .............................................................................................................. 5 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 6 4.0 PREREQUiSiTES ......................................................................................................... 7 5.0 SPECIAL TOOLS AND RECOMMENDED EQUIPMENT ............................................ 7 6.0 ACCEPTANCE CRITERIA ........................................................................................... 7 7.0 PROCEDURE STEPS .................................................................................................. 8 8.0 ILLUSTRATIONS/ATTACHMENTS ........................................................................... 13 : Surveillance Procedure Review Form ..................................................... 14

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit 3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 4 of 14

1.0 INTRODUCTION

1.1 Purpose This procedure is performed to verify indicated power availability to required AC and DC electrical power distribution subsystems presented in Unit 3 Technical Specification (Bases) Table B 3.8.7-1 in conformance with the requirements specified in Technical Specification Surveillance Requirements (SR) 3.8.7.1 and 3.8.8.1.

1.2 Scope This procedure verifies the AC and DC electrical power distribution subsystem is functioning properly, with the buses energized. The verification of proper voltage availability on the buses ensures the required power is readily available for motive as well as control functions for critical system loads connected to these buses.

This procedure and 2-SR-3.8.7.1 fully satisfies Unit 3's SR 3.8.7.1 and 3.8.8.1.

1.3 Frequency Once every seven days.

1.4 Applicability Modes 1, 2, 3, 4, and 5, during movement of irradiated fuel assemblies in the secondary containment.

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit 3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 5 of 14

2.0 REFERENCES

2.1 Technical Specifications Section 3.8.7, Distribution Systems - Operating.

Section 3.8.8, Distribution Systems - Shutdown.

2.2 UFSAR Section 8.4, Normal Auxiliary Power System.

Section 8.S, Standby A-C Power Supply and Distribution.

Section 8.6, 2S0 - VDC Power Supply and Distribution.

2.3 Plant Instructions OPDP-1, Conduct of Operations.

SPP-8.1, Conduct of Testing.

2.4 Plant Drawings 0-1SESOO-1, Key Diagram of Standby Auxiliary Power System.

3-1SESOO-3, Key Diagram of Normal & Standby Auxiliary Power System.

0-4SE701-1, Wiring Diagram, Battery Bd 1, Panels 1-7, Single Line.

0-4SE702-1, Wiring Diagram, Battery Board 2, Panels 1-7, Single Line.

0-4SE703-1, Wiring Diagram, Battery Board 3, Panels 1-7, Single Line.

0-4SE709-1, Wiring Diagram, Shutdown Bds 2S0V Btry & Chgr, Single Line.

3-4SE709-2, Wiring Diagram, Shutdown Bds 2S0V Btry & Chgr, Single Line.

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 6 of 14 3.0 PRECAUTIONS AND LIMITATIONS A. This procedure may be performed in any plant operating condition subject to the approval of the Unit Supervisor (US).

B. This procedure will require the performer to obtain various readings from local indications since all required readings are NOT available from any Control Room.

C. 480V Shutdown Board, 480V Diesel Auxiliary Board, SGT Board, 480V RMOV Board D or E voltages that appear to exceed 500 volts requires EM assistance in verifying the A0 to B0, B0 to C0, and C0 to A0 voltages using a multi meter. Measured voltages exceeding 508 volts requires notification of Site Engineering.

D. When the voltage for an electrical board appears to be outside its allowable range, the event should be recorded in the post-test remarks and a Work Order should be generated to have Electrical Maintenance verify the board voltage.

BFN Weekly Check of Power Availability to 3-SR-3.B. 7.1 Unit3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 7 of 14 Date _ _ __

4.0 PREREQUISITES

[1] VERIFY this copy of the Surveillance Procedure is verified the most current revision.

[2] VERIFY one (1) operator is available to perform this surveillance procedure.

[3] VERIFY Electrical Maintenance personnel are informed that this Surveillance Procedure is to be performed in order to obtain 480V SGT SO voltage.

5.0 SPECIAL TOOLS AND RECOMMENDED EQUIPMENT

[1] Analog or Digital Multimeter (N/A if NOT used) 10 Number: ____Cal Due Date: _ _ __

6.0 ACCEPTANCE CRITERIA A. Responses which fail to meet the acceptance criteria stated in Section 6.0 shall constitute unsatisfactory surveillance procedure results and require immediate notification of the Unit Supervisor at the time of failure and documentation in accordance with SPP-8.1, Conduct of Testing.

1. AC and DC electrical power distribution subsystem is functioning properly, as verified by the buses energized and proper voltage is available on the buses.

S. Steps which determine the above criteria are designated by (AC) next to the initials blank.

BFN Weekly Check of Power Availability to 3-SR-3.B.7.1 Unit 3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page B of 14 Date _ __

7.0 PROCEDURE STEPS

[1] VERIFY the following initial conditions:

• All Precautions and Limitations in Section 3.0 have been reviewed.

• All Prerequisites listed in Section 4.0 are satisfied.

[2] OBTAIN permission from the Unit Supervisor (US) to perform this procedure.

US

[3] NOTIFY Unit Operator (UO) that this test is about to commence.

[4] RECORD the date and time started, reason for test, and plant conditions on Attachment 1, Surveillance Procedure Review Form.

NOTES

1) The following steps can be performed in any convenient order.

2) Specific voltmeters are NOT listed to allow the performer maximum flexibility when obtaining readings. However, Control Room indications should be used whenever possible.

[5] VERIFY proper voltage available for the following boards and RECORD voltages:

A. 4KV SD BD A VOLTAGE (See Step 7.0[6])

Voltage_ _ _ (3950 - 4400 VOLTS)

B. 4KV SD BD B VOLTAGE (See Step 7.0[6] and 7.0[7])

Voltage _ _ _ (3950 - 4400 VOLTS)

C. 4KV SD BD D VOLTAGE (See Step 7.0[7])

Voltage_ _ _ (3950 - 4400 VOLTS)

D. 4KV SD BD 3EA VOLTAGE Voltage _ _ _ (3950 - 4400 VOLTS) _ _(AC)

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit 3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 9 of 14 Date - - -

7.0 PROCEDURE STEPS (continued)

E. 4KV SO BO 3EB VOLTAGE Voltage_ _ _ (3950 - 4400 VOLTS) _ _ (AC)

F. 4KV SO BO 3EC VOLTAGE Voltage _ _ _ (3950 - 4400 VOLTS) _ _ (AC)

G. 4KV SO BO 3EO VOLTAGE Voltage_ _ _ (3950 - 4400 VOLTS) _ _ (AC)

CAUTION 480V Shutdown Board, 480V Diesel Auxiliary Board, SGT Board, 480V RMOV Board 0 or E voltages that appear to exceed 500 volts requires EM assistance in verifying the A0 to

( B0, B0 to C0, and C0 to A0voltages locally using a multimeter. Measured voltages exceeding 508 volts requires notification of Site Engineering.

NOTE IF EM measures voltage locally at a 480 volt board due to indicating greater than 500 volts, only the highest reading 0 to 0 voltage need be recorded.

H. 480V SO BO 1A VOLTAGE Voltage_ __

• VERIFY Voltage ~ 440 VOLTS _ _ (AC)

• VERIFY Voltage ~ 508 VOLTS I. 480V SO BO 3A VOLTAGE Voltage _ __

• VERIFY Voltage ~ 440 VOLTS _ _ (AC)

• VERIFY Voltage~ 508 VOLTS

BFN Weekly Check of Power Availability to 3-SR-3.B.7.1 Unit 3 Required AC and DC Power Rev. 0011

( Distribution Subsystems Page 10 of 14 Date 7.0 PROCEDURE STEPS (continued)

J. 480V SO BO 3B VOLTAGE Voltage

• VERIFY Voltage ~ 440 VOLTS (AC)

• VERIFY Voltage ~ 508 VOL TS K. 480V RMOV BO 3A VOL TAGE Voltage

• VERIFY Voltage ~ 440 VOL TS (AC)

L. 480V RMOV BO 3B VOLTAGE Voltage

(

• VERIFY Voltage ~ 440 VOL TS (AC)

M. 480V RMOV BO 3D VOLTAGE Voltage

• VERIFY Voltage ~ 440 VOL TS (AC)

• VERIFY Voltage ~ 508 VOLTS N. 480V RMOV BO 3E VOLTAGE Voltage

• VERIFY Voltage ~ 440 VOL TS (AC)

• VERIFY Voltage ~ 508 VOL TS O. 480V SGT BO VOLTAGE Voltage

• VERIFY Voltage ~ 440 VOL TS (AC)

• VERIFY Voltage ~ 508 VOL TS

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit 3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 11 of 14 Date 7.0 PROCEDURE STEPS (continued)

P. 480V OSL AUX BO A VOLTAGE Voltage

• VERIFY Voltage?:: 440 VOL TS (Ae)

• VERIFY Voltage:::; 508 VOL TS Q. 480V OSL AUX BO B VOL TAGE Voltage

• VERIFY Voltage?:: 440 VOL TS (Ae)

• VERIFY Voltage:::; 508 VOL TS R. 480V OSL AUX BO 3EA VOL T AGE Voltage

• VERIFY Voltage?:: 440 VOL TS (Ae)

• VERIFY Voltage:::; 508 VOLTS S. 480V OSL AUX BO 3EB VOL TAGE Voltage

• VERIFY Voltage?:: 440 VOLTS (Ae)

• VERIFY Voltage:::; 508 VOL TS T. 250V Unit DC BO 1 (Battery BO 1) VOLTAGE Voltage (248 - 280 VOL TS) (AC)

U. 250V Unit DC BO 2 (Battery BO 2) VOLTAGE Voltage (248 - 280 VOL TS) (AC)

V. 250V Unit DC BO 3 (Battery BO 3) VOL TAGE Voltage (248 - 280 VOL TS) (Ae)

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 12 of 14 Date _ __

7.0 PROCEDURE STEPS (continued)

W. 250V DC RMOV BD 3A VOLTAGE Voltage _ _ _ (248 - 280 VOLTS) _ _ (Ae)

X. 250V DC RMOV BD 3B VOLTAGE Voltage_ _ _ (248 - 280 VOLTS) _ _ (Ae)

Y. 250V DC RMOV BD 3C VOLTAGE Voltage_ _ _ (248 - 280 VOLTS) _ _ (Ae)

Z. 250V SD BD DC DISTRIBUTION PANEL SB-A VOLTAGE (See Step 7.0[8])

Voltage._ _ _ (248 - 280 VOLTS)

AA. 250V SD BD DC DISTRIBUTION PANEL SB-B VOLTAGE (See Step 7.0[8] and 7.0[9])

Voltage_ _ _ (248 - 280 VOLTS)

BB. 250V SD BD DC DISTRIBUTION PANEL SB-D VOLTAGE (See Step 7.0[9])

Voltage_ _ _ (248 - 280 VOLTS)

CC. 250V SD BD DC DISTRIBUTION PANEL SB-3EB VOLTAGE Voltage_ _ _ (248 - 280 VOLTS) _ _(Ae)

[6] CHECK 4KV SD BD A OR 4KV SD BD B VOLTAGE is satisfactory (See Steps 7.0[5]A and 7.0[5]B). (AC)

[7] CHECK 4KV SD BD D OR 4KV SD BD B VOLTAGE is satisfactory (See Steps 7.0[5]B and 7.0[5]C). (Ae)

[8] CHECK 250V SD BD DC DISTRIBUTION PANEL A OR 250V SD BD DC DISTRIBUTION PANEL B VOLTAGE is satisfactory (See Steps 7.0[5]Z and 7.0[5]AA). (Ae)

[9] CHECK 250V SD BD DC DISTRIBUTION PANEL D OR 250V SD BD DC DISTRIBUTION PANEL B VOLTAGE is satisfactory (See Steps 7.0[5]AA and 7.0[5]BB). (Ae)

BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit 3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 13 of 14 Date _ __

7.0 PROCEDURE STEPS (continued)

[10] COMPLETE Attachment 1, Surveillance Procedure Review Form, up to Unit Supervisor Review.

[11] NOTIFY the Unit Supervisor (US) this surveillance procedure is complete and PROVIDE status of any Corrective Actions or unsatisfactory performances.

8.0 ILLUSTRATIONS/ATTACHMENTS Attachment 1 - Surveillance Procedure Review Form.

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BFN Weekly Check of Power Availability to 3-SR-3.8.7.1 Unit3 Required AC and DC Power Rev. 0011 Distribution Subsystems Page 14 of 14 Attachment 1 (Page 1 of 1)

Surveillance Procedure Review Form REASON FOR TEST: DATEITIME STARTED o Scheduled Surveillance DATEITIME COMPLETED o System Inoperable (Explain in Remarks) PLANT CONDITIONS o Maintenance (WO No. )

o Other (Explain in Remarks)

PRE-TESTREMARKS: _____________________________________________

PERFORMED BY:

Initials Name (Print) Name (Signature)

(Test Dir/Lead Perf)

(Test Dir/Lead Perf)

Delays or Problems (If yes, explain in POST-TEST REMARKS)? DYes DNo Acceptance Criteria Satisfied? DYes DNo If the above answer is no, the Unit Supervisor shall determine if an LCO exists. LCO DYes DNo UNIT SUPERVISOR Date INDEPENDENT REVIEWER Date - - - - - - - - - - - - -

SCHEDULING COORDINATOR ------------------------ Date- - - - - - - - - - - - -

POST-TEST REMARKS:

The SR Key number is a Cross Reference only and is not part of the procedure. Key # 39581

HLTS-3-6 Revision 0 Page 1 of 33 SIMULATOR EVALUATION GUIDE TITLE: ALTERNATE EHC PUMPS, 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 o DATE October 9,2008 PROGRAM BFN Operator Training THIS SCENARIO REQUIRES STOPWATCH, PROVIDE WO PMT AND ROD PULL SHEET TO CANDIDATES AT TURNOVER. (PMT & Turnover at end of this Evaluation Guide)

PREPARED BY: \ _ _ __

(Operations Instructor) Date REVIEWED BY: \ _ _ __

( BFN Lead Examiner or Designee) Date REVIEWED BY: \ _ _ __

(Operations Training Manager or Designee) Date CONCURRED: \ _ _ __

(Operations Superintendent or Designee) Date VALIDATION BY: \----

(Operations US) (Required for Exam Scenarios only) Date

HLTS-3-6 Revision 0 Page 2 of 33 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION DATE PAGES REVIEWED/REVISED NUMBER OF CHANGES AFFECTED BY 0 INITIAL 09/08/08 All Spadoni

HLTS-3-6 Revision 0 Page 3 of 33 I. Program: BFN Operator Training II. Course: Examination Guide III.

Title:

ALTERNATE EHC PUMPS, 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 Lesson: 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> V. Examination 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)

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

4. Use step text procedural compliance (WANO).

HLTS-3-6 Revision 0 Page 4of33

) 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 crew will respond to an uncoupled control rod (46-39)

4. The operating crew will respond to Spurious RWCU isolation.

5. The operating crew will 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 crew will spray the Suppression Chamber to maintain containment pressure less than 2.45 psig and the RPV will be depressurized when Suppression Chamber level cannot be maintained above 11.5 feet..

)

HLTS-3-6 Revision 0 Page 5 of33 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.

A. SOER 94-01 B. SOER 96-01 VII. Training Materials:

A. Calculator (If required)

B. Control Rod Insertion Sheet (If required)

C. Stopwatch (If required)

D. Hold Order / Caution tags (If required)

E. Annunciator window covers (If required)

F. Steam tables (If required)

F. LCO/Appendix R Tracking Log G. Calculator H. Spray Cleaner I. Rags J. Markers

HLTS-3-6 Revision 0 Page 6 of 33 VIII. Console Operator Instructions A. Scenario File Summary 1 File bat HLTS 3-6 MF/RF/IOR# Description a) trg e1 3ARHRSTART Assigns trigger to 3A RHR pump switch b) trg e2 3A2VFDCOOL Sets trigger e2 to 3a2 cooling water pump handswitch c) imffw02a 3A Condensate Booster Pump Trip d) imf rh01 b Prevents 3B RHR pump manual start e) imf rh01d Prevents 3B RHR pump manual start f) ior zlohs0256a[1] off Green light off for 3A Condensate Booster Pump g) ior zlohs0256a[2] off White light off for 3A Condensate Booster Pump h) ior ypovfcv74100 faiLpower_now FCV 74-100 tag out i) imf rd05r4639 46-39 Rod uncoupled j) imf rd01b CRD Pump Tagout k) ior zlohs852a [1] off CRD Pump Tagout I) ior zdihs852a stop CRD Pump Tagout m) ior zlohs7334a[2] off HPCI tagout n) ior zlohs7344a[1] off HPCI tagout

0) mrf th18b trip Open breaker for 3A VFD 3A2 cooling water pump p) trg e1 = imf pc14 50 Trigger e2 initiates a leak in the suppression chamber when 3A RHR pump is started.

q) trg e2= mrf th18b close Trigger e2 allows 3A2 VFD cooling pump to start manually.

r) Imf rp06 Auto scram failure

HLTS-3-6 Revision 0 Page 7 of 33 VIII. Console Operator Instructions B. Scenario File Summary

2. File: bat HL TS3-6-1 MF/RF/IOR# Description a) dor zlohs 7334a[2] Deletes override for red light b) dor zlohs7344a[1] Deletes override for green light

3. File: batapp08e MF/RF/IOR# Description a) mrf rp14a Bypass Group 6 inboard low level/high drywell pressure interlocks b) mrf rp14b Bypass Group 6 outboard low level/high drywell pressure interlocks

)

HLTS-3-6 Revision 0 Page 8 of 33 VIII. Console Operator Instructions B. Console Operator Manipulations ELAPSED TIME PFK DESCRIPTION/ACTION Sim. Setup IC-26, 70% power (SNAP 258)

Sim. Setup See scenario summary bat HLTS3-6 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 recouple rod 34-19 per 3-AOI-85-2 When rod is allows recoupling control rod inserted to 46 (dmf rd05r3419)

When requested by RWCU isolation examiner (ior zdihs691 [2] close)

Just before role play Return 69-1 Norm below (dor zdihs691 [2])

)

HLTS-3-6 Revision 0 Page 9 of 33 VIII. Console Operator Instructions (Continued)

B. Console Operator Manipulations 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 closed the 3*HS*69*1 valve.

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.

ELAPSED TIME DESCRIPTION/ACTION When asked to (mrf an01 e reset) - allows control room reset 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-3-6 Revision 0 Page 10 of 33 VIII. Console Operator Instructions (Continued)

C. Console Operator Manipulations ELAPSED TIME DESCRIPTION/ACTION When requested to Allow PMT for HPCI valves turn on breakers for (bat HLTS3-6-1) 73-34 and 73-44 When directed by Opens MSRV 1-19 to 25% with the Chief Examiner: tailpipe 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-3-6 Revision 0 Page 11 of 33 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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-3-6 Revision 0 Page 12 of 33

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

1. SRO  : Unit Supervisor

2. ATC  : Board Unit Operator

3. BOP  : Desk Unit Operator B. Review the shift briefing information with the operating crew. Provide SRO with a copy of Shift Turnover Sheet, Reactivity Plan, and pull sheet for scenario.

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

D. Ensure recorders are inking and 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"

HLTS-3-6 Revision 0 Page 13 of 33

) XI. Simulator Event Guide Event 1: Alternate EHC Pumps

. TIME POSITION EXPECTED ACTION(S)

ATC/BOP Receive crew briefing and walk boards down SRO Directs BOP to alternate EHC pumps BOP Alternates EHC Pumps in accordance with 3-01-47A section 6.3

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

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

[3] START the non-operating EHC PUMP 3B(3A) using EHC HYD FLUID PUMP 3B(3A), 3-HS-47-2A(1A).

[4] CHECK the started EHC pump EHC HYD PUMP A(B) DISCH PRESS, 3-PI-047-0001(0002), indicates between 1550 psig and 1750 psig, locally at the EHC skid. (AUO reports 1625 psig)

[5] IF the started EHC pump discharge pressure is NOT between 1550 psig and 1750 psig, THEN ADJUST the pressure compensator for the started EHC pump to adjust pump discharge pressure. REFER TO Step 8.6[1].

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

HLTS-3-6 Revision 0 Page 14 of 33

)

XI. Simulator Event Guide Event 1: Alternate EHC Pumps TIME POSITION EXPECTED ACTION(S)

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

[10] CHECK the started EHC PUMP 3B(3A) MTR AMPS, 3-EI-47-2(1), indicates less than 140 amps.

[11] VERIFY EHC Pump 3B(3A), EHC PUMP SUCTION FILTER and EHC AUX PUMP SUCTION FILTERS, indicate CLEAN, locally at the EHC skid.

[12] [NERlC] VERIFY MANUAL FLOW CONTROL VALVE, 3-047-0588, is set at 2.0 turns clockwise. [INPO SOER 84-006]

BOP Swaps lens covers for EHC pumps based on new lineup

HLTS-3-6 Revision 0 Page 15 of 33 XI. Simulator Event Guide Event 2: PERFORM CRD TIMER TEST POSN TIME EXPECTED ACTIONS CREW Accepts shift turnover SRO Directs ATC to perform CRD Timer Test per 3-01-85 section 8.14.

ATC REVIEW all Precautions and Limitations in Section 3.2 and 3.3.

PLACE WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3A/S6, in TEST AND HOLD for at least two seconds.

CHECK the white indicating light above the WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3A/S6 illuminates.

CHECK the red indicating light above the WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3A/S6 illuminates after approximately two seconds.

CHECK CONTROL ROD SELECT BLOCK TIMER MALFUNCTION annunciator(3-XA-55-5A, Window 21) in alarm.

PLACE WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3A/S6 in RESET.

CHECK all Reactor Manual Control System WITHDRAW AUXILIARY TIMER TEST, 3-HS-85-3A/S6 indicating lights are extinguished.

RESET CONTROL ROD SELECT BLOCK TIMER MALFUNCTION annunciator (3-XA-55-5A, Window 21).

HLTS-3-6 Revision 0 Page 16 of 33 XI. Simulator Event Guide Event 2: PERFORM CRD TIMER TEST (Continued)

POSN TIME EXPECTED ACTIONS ATC NOTE:

The following steps will allow the RMCS timer to be operationally checked without the possibility of moving a control rod.

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-85-23A.

SELECT a peripheral control rod by depressing the appropriate CRD ROD SELECT push-button, 3-XS-85-40.

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.

IF while performing this section Rod Motion is observed, THEN IMMEDIATELY RELEASE CRD CONTROL SWITCH 3-HS 48 and CONTACT System Engineer.

RAISE the CRD DRIVE WTR HDR DP, 3-PDI-85-17A to between 250 psid and 270 psid, using CRD DRIVE WATER PRESS CONTROL VL V, 3-HS-85-23A.

HLTS-3-6 Revision 0 Page 17 of 33 XI. Simulator Event Guide Event 2: PERFORM CRD TIMER TEST (Continued)

POSN TIME EXPECTED ACTIONS ATC FURTHER tests or checks shall not be performed without direction of the Unit Supervisor.

REPEAT step 8.14.11 as required to determine that the RMCS timer is operating as required. IF the RMCS timer is not operating as required, THEN GENERATE a WOo IF the RMCS timer is operating as required, THEN RAISE the CRD DRIVE WTR HDR DP, 3-PDI-85-17A to between 250 psid and 270 psid, using CRD DRIVE WATER PRESS CONTROL VL V, 3-HS-85-23A.

BOP Peer Checks manipulations

HLTS-3-6 Revision 0 Page 18 of 33 Event 3: RAISE POWER USING CONTROL RODS POSN TIME EXPECTED ACTIONS SRO Directs ATC to withdraw rods per movement sheet ATC Withdraws rods per movement sheet BOP Peer Checks rod withdrawals

HLTS-3-6 Revision 0 Page 19 of 33 XI. Simulator Event Guide Event 4: CONTROL ROD 34-19 UNCOUPLED POSN TIME EXPECTED ACTIONS CREW Recognizes symptoms of an uncoupled rod SRO Directs ATC to respond to uncoupled rod per 3-AOI-85-2 SRO Notifies Reactor Engineer of uncoupled rod per 3-AOI-85-2 and requests permission to proceed with recoupling rod 34-19.

Refers to Tech. Specs. 3.1.3 and declares rod INOP while uncoupled.

ATC Performs actions to recouple rod per 3-AOI-85-2, section 4.2.3 IF the control rod drive is at position 48 and with Reactor Engineer concurrence, THEN NOTCH INSERT the control rod drive to position 46 to attempt to couple the control rod.

RESET associated annunciators.

NOTCH WITHDRAW the control rod drive to position 48.

PERFORM a coupling check.

SRO Determines rod is operable

HLTS-3-6 Revision 0 Page 20 of 33 XI. Simulator Event Guide Event 5: RWCU ISOLATION POSN TIME EXPECTED ACTIONS Crew Recognizes RWCU Isolation, responds per the ARP 3-ARP-9-4B 3-XA-55-4B win 10 (RWCU flow low) & win 24 RWCU demin abnor 3-XA-55-8C WIN 33 Motor tripout SRO Enters 3-AOI-64-2a SRO Contacts Rx Engineer for heat balance SRO Notify Chemistry and RadCon SRO Evaluate Tech. Spec. (TRM TSR 3.4.1) Monitor conductivity every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (not in mode 4 or 5)

Chemistry, sampling required (If not returned to service)

SRO Directs restoration of system after cause is determined BOP Restores RWCU per 3-01-69

-Verifies RWCU Filters are in Hold

-Opens 3-FCV-69-1

-Opens 3-FCV-69-8

-Opens 3-FCV-69-12 for pump startup

-Start one RWCU pump and open 3-FCV-69-12 to achieve> 56 gpm

-Start the second RWCU pump and attain -300 gpm flow

-coordinate with RB AUO and place demins in service BOP Notifies Chemistry BOP Notifies Rx. Engineer

HLTS-3-6 Revision 0 Page 21 of 33 XI. Simulator Event Guide Event 6: VFD COOLING WATER PUMP FAILURES

[VARIABLE FREQ DRIVE]

POSN TIME EXPECTED ACTIONS ATC Announces Recirc Drive 3A Coolant Flow Low. Informs SRO 3A VFD Cooling Water Pump 3A1 has tripped and 3A2 failed to start.

SRO Directs ATC to refer to ARP.

ATC Consults ARP, starts Recirc Drive 3A2 Cooling Water pump.

3-ARP-9-4A 3-XA-55-4A WIN 12 Verifies flow on ICS, resets annunciators SRO Directs Outside US 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 3A1 or 3A2 failed to re-start.

SRO Directs trip of 3A Recirc Pump and entry into 3-AOI-68-1A ATC Removes 3A Recirc pump ATC When Region I of the Power to Flow Map is entered IMMEDIATELY take actions to INSERT control rods to less than 95.2% load line.

XI. Simulator Event Guide

HLTS-3-6 Revision 0 Page 22 of 33 XII. Simulator Event Guide Event 6: VFD COOLING WATER PUMP FAILURES

[VARIABLE FREQ DRIVE]

POSN TIME EXPECTED ACTIONS ATC Raises core flow to greater than 45%.

ATC Inserts control rods to exit regions ATCI Close Recirc Pump discharge valve on tripped pump.

BOP ATC MAINTAIN operating Recirc pump flow less than 46,600 gpm.

Refer to 3-01-68.

ATC Maintains operating jet pump loop flow greater than 41 x 1061bm/hr 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

HLTS-3-6 Revision 0 Page 23 of 33 XIII. Simulator Event Guide Event 7: INADVERTANT TRIP OF RCIC TURBINE POSN TIME EXPECTED ACTIONS BOP Announces RCIC Turbine tripped refers to ARP 3-XA-55-3B win 14.

SRO Dispatches field personnel to investigate and troubleshoot RCIC turbine trip.

SRO Declares RCIC Inop per TS 3.5.3.A, 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> LCO due to inop HPCI Mode 3 required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Reactor Pressure

<150 psig within 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />.

SRO SRO requests status of HPCI SRO Directs BOP to perform PMT for 3-FCV-73-34 and 44.

BOP Performs timing of 3-FCV-73-34 and 44 per WO

1. CLOSE and TIME 3-FCV-73-34using HPCI PUMP DISCHARGE VALVE,3-HS-73-34A and RECORD the stroke time below:

3-FCV-73-34 CLOSING TIME (SEC)

NORMAL MEASURED MAXIMUN N/A 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 NORMAL MEASURED 15.6 - 21.0

3. VERIFY the stroke time recorded is less than or equal to the maximum value listed.

HLTS-3-6 Revision 0 Page 24 of 33

)

EVENT 7 INADVERTANT TRIP OF RCIC TURBINE (Continued)

POSN TIME EXPECTED ACTIONS BOP 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 MEASURED MAXIMUM 16.6 - 22.4 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 MEASURED MAXIMUM

~.8 -17.4 -

26.7

7. VERIFY the stroke time recorded is less than or equal to the maximum value listed.

8. PMT COMPLETE SRO Reviews PMT, declares HPCI operable. RCIC now in 14 day LCO.

)

HLTS-3-6 Revision 0 Page 25 of 33 XIV. Simulator Event Guide Event 8: MSRV tailpipe break in Suppression Chamber POSN TIME EXPECTED ACTIONS BOP Recognizes MSRV 1-19 is open. Performs immediate actions of 3-AOI-1-1.

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 ATC to enter 3-AOI-64-1 and vent the Suppression Chamber.

ATC Initiates Suppression Chamber venting in accordance with 3-AOI-64-1.

SRO Determines that Drywell pressure will exceed 2.45 psig and directs manual scram. (conservative decision making)

Crew Recognizes that an automatic scram did not occur at 2.45 psig.

11~.RlllplllilJ{~:11 SRO Directs ATC to initiate a manual reactor scram ATC Inserts a manual scram; Places mode switch in shutdown verifies all rods in makes scram report BOP Continues actions per 3-AOI-1-1 for MSRV 1-19.

SRO Enters EOI-1 on low level and directs:

-Verifications of group isolations and initiations

-entry into AOI-1 00-1

-verifies Turbine Bypass valves controlling pressure

HLTS-3-6 Revision 0 Page 26 of 33

)

xv. Simulator Event Guide Event 8: MSRV tailpipe break in Suppression Chamber POSN TIME EXPECTED ACTIONS SRO Enters EOI-2 and re-enters EOI-1 when drywell pressure exceeds 2.45 psig .

BOP Verifies Diesel generators start BOP Directs AUO to monitor DIG SRO Directs the following:

• All available drywell cooling in service

• Venting per App 12

)

• H2/02 Analyzers placed in service BOP Verifies all drywell blowers in service BOP Vents per Appendix 12 BOP Places H2/0 2 Analyzers in service using keylock bypass switches.

BOP Monitors containment parameters and reports rate of rise of suppression chamber pressure and drywell pressure SRO Determines venting and plant cooldown will not maintain suppression chamber pressure <12 psig and:

SRO Directs BOP to initiate Suppression Pool Sprays in accordance with 3-EOI-Appendix 17C.

BOP Initiates Suppression Pool Sprays in accordance with 3-EOI-Appendix 17C.

)

HLTS-3-6 Revision 0 Page 27 of 33

)

XI. Simulator Event Guide Event 9: Un-isolable leak in Suppression Chamber POSN TIME EXPECTED ACTIONS 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.

SRO Enter 3-EOI-3 flowchart.

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.

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.

HLTS-3-6 Revision 0 Page 28 of 33 XI. Simulator Event Guide Event 9: Un-isolable leak in Suppression Chamber (continued)

SRO Direct ATCIBOP to perform 3-EOI-Appendix 18 to add water to the Suppression Pool.

ATCI Address 3-EOI-Appendix 18 to add water to the Suppression BOP Pool.

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 Pull-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.

SRO Anticipate Emergency Depressurization and direct the RPV be rapidly depressurized using Main Turbine Bypass Valves.

~!~~iIJialll,sl~ (conditional)

ATCI Open Main Turbine Bypass Valves using the Bypass Valve BOP manual Jack.

SRO When Suppression Pool level approaches or exceeds 11 .5 feet, direct Emergency Depressurization using MSRVs in accordance with 3-EOI-C2.

HLTS-3-6 Revision 0 Page 29 of 33 XI. Simulator Event Guide Event 9: Un-isolable leak in Suppression Chamber (continued)

POSN TIME EXPECTED ACTIONS BOP Opens six ADS valves to initiate Emergency Depressurization.

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.

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-$ (PSP Curve).

HLTS-3-6 Revision 0 Page 30 of 33 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.

2. Prevent HPCI operation with Suppression Pool level below 12.75 feet.

3. Emergency Depressurize the RPV within 5 minutes of Suppression Pool level dropping below 11.5 feet.

HLTS-3-6 Revision 0 Page 31 of33 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS-7

~ 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

7) RCIC Trip

8) Recirc Drive 3A Cooling water pump trip

9) RHR 3B and 3D manual start failure

10) Auto scram failure 4 Malfunctions That Occur After EOI Entry; List: (1-4)

1) Suppression Chamber leak

2) RHR 3B and 3D manual start failure

3) Auto scram 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) Suppression Chamber leak

~ EOls 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) 35 EOI Run Time (minutes); 44 % of Scenario EOI Run Time

~ Crew Critical Tasks (2-5)

Yes Technical Specifications Exercised (yes/no)

Revision 1 Page 32 of 33 SHIFT TURNOVER SHEET Equipment Out of Service/LCOs Unit at 70% power due to 3A Condensate Booster Pump out of service for oil leak. 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. 3B CRD pump is tagged for bearing replacement.

Operations/Maintenance for the Shift: Alternate EHC Pumps per section 6.2 of 3-01 47A.

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 5.16 of 3-GOI-1 00-12). When HPCI clearance is picked up, perform PMT per WO (copy attached) prior to making HPCI operable. HL T class in the plant performing JPM's.

Unusual Conditions/Problem Areas Reactor Engineer expects Xenon to build-in over next few hours.

Revision 1 Page 33 of 33 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 MEASURED MAXIMUM N/A 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 IMEASURED MAXIMUM 15.6 - 21.0 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 MEASURED 16.6 - 22.4

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 MEASURED MAXIMUM 12.8-17.4 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: _ _ _ _ _ _ _ _ __

HLTS-3-7 Revision 0 Page 1 of 22 SIMULATOR EVALUATION GUIDE TITLE ROD SCRAM, SRV FAILURE, LOSS OF OFFSITE POWER, STEAM LINE BREAK WITHIN DRYWELL, FAILURE OF DIESELS REVISION o DATE October 9, 2008 PROGRAM BFN Operator Training - HLT PREPARED BY: I (Operations Instructor) Date REVIEWED BY: I (LOR Lead Instructor or Designee) Date REVIEWED BY: I (Operations Training Manager or Designee) Date CONCURRED I (Operations Superintendent or Designee) Date VALIDATION : I BY (Operations SRO: Required for Exam Scenarios Only) Date LOGGED-IN: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _--.-,;I _ _ __

(Librarian) Date TASKS LIST UPDATED: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I _ _ __

Date

HLTS-3-7 Revision 0 Page 2 of 22 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION DATE PAGES REVIEWED BY NUMBER OF AFFECTED REVISION 0 09/08/08 All Spadoni

HLTS-3-7

( Revision 0 Page 30f22 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. Examination 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 skillsto 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.

B. Enabling Objectives:

1. The operating crew will recognize and respond to a control rod scram in accordance with 3-AOI-85-5.

2. The operating crew will recognize and respond to a stuck open SRV in accordance with 3-AOI-1-1.

3. The operating crew will recognize and respond to an inoperable ADS valve and HPCI in accordance with Technical Specifications.

4. The operating crew will recognize and respond to a steam line break per the ARPs and EOls. .

5. The operating crew will recognize and respond to a loss of offsite power and diesel generator failures per O-AOI-57-1A.

HLTS-3-7 Revision 0 Page 4 of 22 VI.

References:

The procedures used in the simulator are controlled copies and are used in development and performance of simulator scenarios.

Scenarios are validated priorto 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 Sheet C. Stopwatch D. Hold Order / Caution tags E. Annunciator window covers F. Steam tables

HLTS-3-7

( Revision 0 Page 5 of 22 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat HLTS 3-7 MF/RFIIOR# 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 BSCRAMLIGHT Assigns trigger #3 to the B Manual scram button light.

4) bat tohpci Tags out HPCI lights

5) imfdg01a Fails DG 'A' from auto starting

6) imf dg03d Fails DG 'D' output breaker from automatically 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 ad01f malfunction

11) imf ad02f (e2 :02) Initiates malfunction when trigger #2 fires

12) trg e3 = mrf rd1 Of2239 scram Modifies remote function to scram rod 22-39 when "B" manual scram pushbutton is pushed.

HLTS-3-7 Revision 0 Page 6 of 22

2. File: bat tohpci MF/RF/IOR# Description

1) ior ypovfcv7316 faiLnow 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_cn_po Removes power from gland exhauster

3. File: bat HL TS3-7-2 MF/RFIIOR# Description

1) imf ed06b Loss of CSST B

2) imf th33a (none 5:00) 5 10:00 Steam line break

3) imf ed01 (none 9:00) Loss of offsite power

(~ 4) imf th22 (none 14:00) 100 10:00 Rx bottom head drain leak

4. File: bat eecw

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: batapp07b

1) mrf s101 on Aligns SLC to Test Tank for injection to vessel

6. File: bat eecw-1 MF/RFIIOR# 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

HLTS-3-7 Revision 0 Page 70f22 VIII. Console Operator Instructions B. Console Operator Manipulations ELAP TIME DESCRIPTION/ACTION Sim. Setup 100% power, MOC manual Close FCV 73-3,81; Aux. oil pump and Gland Exhauster in pull to lock.

manual Tag 73-2 & 3,81, & 16, Aux. Oil Pump, Gland Seal Exhauster.

See scenario summary (bat HLTS3-7)

ELAPTIME DESCRIPTION/ACTION Whenever B half scram is mrf rd1 0r2239 norm reset ROLE PLAY: If requested to check on cause of scrammed control rod, wait 5 minutes and report that fuse 5A-F19A (18-39) is blown. Fuse has been replaced.

ROLE PLAY: When requested for R.E. guidance, suggest lowering power with recirc to 90% and notch withdraw control rod 22-39 back to notch 14 Two minutes after rod is stuck open SRV 1-34 (imf ad01f 50) withdrawn back to position 48 ROLE PLAY: 3 minutes after requested, report fuse 3E-F6J is blown in panel 25-32.

HLTS-3-7

( Revision 0 Page 8 of 22 If requested to replace fuse Re-opens SRV Then: Restores power to MSRV 1-19 After Tech Spec addressed LOSP (bat HLTS3-7-2) for ADS valve failure and shutdown commenced ROLE PLAY: Reactor Engineer directs inserting emergency rods while he loads RWM.

ROLE PLAY: As the Incident Commander contact the 8M on C88T spraying (no fire just spraying).

When requested to restore Opens 67-50,67-51 and 67-53 from 25-EECW to RBCCW, Air 32 (bat eecw)

Compressor wait 3 minutes ROLE PLAY: Report EECW valves reset at 25-32 NOTE: After bat eecw Allows valves to reclose if another signal entered then comes in (bat eecw-1)

When asked to reset Resets, restarts Control Air compressors Control Air Compressor A, D, and G (bat ca) wait 7 min When asked to Reset RPS Resets RPS circuit protectors (bat wait 5 min rpsreset)

If requested to perform Aligns SLC to Test Tank (bat app07b)

Appendix 7b, wait 20 minutes Terminate the scenario when the following conditions are satisfied or when requested by Chief Examiner:

1. Reactor Water level restored between +2 to +51"

2. Cooldown begun

HLTS-3-7 Revision 0 Page 9 of 22 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 fue 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 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. Shortly after the loss of offsite power, a steam line breaks inside containment causing a drywell pressure/temperature increase.

HLTS-3-7 Revision 0 Page 10 of 22

x. Information to Evaluators:

A. Ensure recorders are inking and recording and ICS is active and updating.

B. Assign Crew Positions based on the required rotation.

1. SRO: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator C. Conduct a shift turnover with the Shift Manager and provide the Shift Manager with a copy of the Shift Turnover.

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

E. Terminate the scenario when the following conditions are satisfied are at the request of the floor/lead instructor/evaluator.

1. Reactor water level restored at +2" to +51"

2. Drywell sprayed

3. Cooldown begun

HLTS-3-7 Revision 0 Page 11 of 22 XI. Simulator Event Guide EVENT 1: ROD SCRAM POSITION TIME EXPECTED ACTIONS ATC Performs 3-SR-3.3.1.1.8(11)

ATC Reports Control Rod Drift alarm and control rod 22-39 has scrammed Identifies drifting rod on full core display SRO Directs actions per SR and doesn't reset scram for at least 10 seconds When determined that a blown fuse exists, directs replacement ATC Does not reset scram for 10 seconds.

SRO 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 Notch withdraws control rod 22-39 to position 14

HLTS-3-7 Revision 0 Page 12 of 22 XI: Simulator Event Guide EVENT 2: SRV FAILURE WITH HPCI OUT OF SERVICE POSITION EXPECTED ACTIONS BOP Announces alarm "Main Steam" Relief valve open Identifies open SRV as 1-34 via acoustic monitor SRO Refers to 3-AOI-1-1 and directs actions BOP Cycles SRV 1-34 Announces that SRV 1-34 indicates closed Reports loss of green light on SRV 1-34 SRO Directs outside SRO to check fuses.

SRO Reviews Tech. Spec 3.5.1.H and enters LCO 3.0.3 SRO Directs crew to begin preparation for shutdown Contacts Reactor Engineer BOP Reviews 3-GOI-1 00-12A SRO Contacts ODS to inform him of required SID

HLTS-3-7 Revision 0 Page 13 of 22 XI. Simulator Event Guide EVENT 3: LOSS OF 161 KV LINE POSITION TIME EXPECTED ACTIONS Crew Identifies Trinity 161 KV line loss 8/D/U Respond to CSST ARPs 9-8 & 9-26 O-GOI-300-4 SM/SRO Directs clearing of breaker switch misalignments, trip of associated MODs. Refers to O-GOI-300-4.

Crew Responds to Fire Alarm on CSST SRO Contacts outside SRO to check switchyard and dispatches Fire Protection to switchyard SRO Contacts Southwest Dispatcher regarding 161 KV

( problem

HLTS-3-7

( Revision 0 Page 14 of 22 XI. Simulator Event Guide EVENT 4: LOSPWITH DIESEL FAILURES and STEAM LINE BREAK POSITION EXPECTED ACTIONS ATC Announces Rx Scram, provides scram report Crew Identifies loss of offsite power SRO Enters EOI-1 Directs 0-AOI-57-1A be performed Directs pressure be maintained 800-1000 psig using MSRVs Directs level be maintained above -162 (+2 to +51" with RCIC)

BOP Announces failure of 'A' Diesel Generator to start and failure of 'D' Diesel Generator to tie to shutdown board BOP Starts 'A' Diesel and verifies/ties to SID Bd; Manually tie 'D' Diesel to Shutdown Bd.

BOP Controls Rx pressure as directed BOP When RCIC is used for level control identifies controller failure and takes manual control SRO Direct entry into AOI-1 00-1

HLTS-3-7 Revision 0 Page 15 of 22 XI. Simulator Event Guide EVENT 4: LOSP WITH DIESEL FAILURES and STEAM LINE 8REAK(Cont)

POSITION EXPECTED ACTIONS ATC Directs RPS MG sets, EECW & Control air restored ATC Starts/verifies R8CCW pumps in service ATC Start Diesel Fire pump SRO -Contacts Operations Duty Specialist (ODS) of loss of all Offsite Power

-EAL 5.1-U (Declare NOUE)

CREW Prior to starting RHR, all motor breakers on associated 8d must be tripped SRO Directs Appendix 58 and may direct App. 78 ATC Starts/aligns 18 CRD pump per App. 58 and may begin App. 78 (SLC)

SRO At 2.45 psig in the drywell, enters EOI'- 2.

Directs H2/02 Sample pumps be returned to service SRO Cautions crew of loading restrictions prior to start of RHR SRO Directs venting per Appx.12

HLTS-3-7 Revision 0 Page 16 of 22 XI. Simulator Event Guide EVENT 4: LOSP WITH DIESEL FAILURES and STEAM LINE BREAK(Cont)

POSITION TIME EXPECTED ACTIONS BOP Vents the Suppression Chamber per Appx. 12 SRO Directs Suppression Pool Sprays placed in service per Appx.17C before suppression chamber pressure reaches 12 psig BOP Sprays the Suppression Chamber per Appx. 17C ATC Directs restart of 'A', 'D', 'G' control air compressor Directs reset of EECW lockouts on panel 25-32 BOP Identifies rise in Drywell Pressure and Temp.

SRO Directs all available DW Blowers in Service ATC Places all blowers in service Crew Monitors DWP and DWT SRO Directs cooldown be started ATC Starts cooldown at <100 degrees F

HLTS-3-7 Revision 0 Page 17 of 22 XI. Simulator Event Guide EVENT 4:* LOSP WITH DIESEL FAILURES and STEAM LINE BREAK(Cont)

POSITION EXPECTED ACTIONS BOP Reports Suppression Chamber pressure is 12 psig SRO Directs Drywell Blowers stopped Directs Recirc Pumps Tripped Directs Drywell Sprayed per Appx. 17B CREW Recognize load shed and failure of "D" DG to re-tie to board CREW Verify that SBGT A and B re-start after 40 seconds CREW Recognize Unit priority re-trip and failure of "D" DG to re-tie again BOP Injects with RHRlCS to maintain RPV water level above -162 when pressure is low enough.

HLTS-3-7 Revision 0 Page 18 of 22 XII. Crew Critical Tasks TASKS SAT/UNSAT

1. Maintains RPV water level above TAF

(-162") .

2. Spray the drywell after Suppression Pool Pressure exceeds 12 psig or Before Drywell temperature exceeds 280 degrees F.

3. Restore electrical power to at least 1 train of SGT = must have 2 SGT trains operating

HLTS-3-7 Revision 0 Page 19 of 22 XIII. Scenario Verification Data EVENT TASK NUMBER KIA RO SRO CONTROL MANIPULATION

1. U-085-AB-05 201003A2.03 3.4 3.7 B6 S-085-AB-05

2. U-OO 1-AB-0 1 239002A2.02 4.1 4.2 S-OO 1-AB-0 1 295013 3.3 3.5 S-000-AD-27

3. U-57A-AB-03 295003 3.5 3.6 A10 S-57A-AB-03 U-068-AL-13 202001A2.10 3.5 3.9

(~ 4. U-57A-AB-01 A10,B14 S-57A-AB-01 A9, A13 U-000-EM-01 295031 4.1 4.2 S-000-EM-01 U-000-EM-02 295025 3.8 3.9 S-000-EM-02 U-000-EM-03 295006 3.9 4;0 S-000-EM-03 295018 3.2 3.3 U-000-AB-04 295019 3.0 3.0 S-OOO-AB-03 S-000-EM-06 295026 3.6 3.8 U-000-EM-07

5. U-000-EM-05 295024 3.7 3.7 A6 S-000-EM-05 U-000-EM-04 295028 3.5 3.8 S-000-EM-04 S-000-EM-21 2.4.38 2.2 4.0 S-000-EM-23

HLTS-3-7 Revision 0 Page 20 of 22 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS-14 JL Total Malfunctions Inserted; List: (5-8)

1) Indvidual Rod Scram

2) SRV Failure (open)

3) SRV Fuse Failure

4) LOSP

5) 'A' DG Failure

6) 'D' DG Failure

7) Steam Line Break

8) RCIC Failure 4 Malfunctions That Occur After EOI Entry; List: (1-2)

1) 'A' DG Failure

2) 'D' DG Failure

3) Steam Line Break

4) RCIC Failure 2 Abnormal Events; List: (2-4)

1) Control Rod Scram

2) SRV Open (AOI) 2 Major Transients; List: (1-2)

1) LOSP

2) Steam Line Break (Small LOCA)

~ EOls used; List: (1-2)

1) EOI-1

2) EOI-2

!L EOI Contingencies Used; List: (0-2)

None 63 Run Time (minutes) 52 EOI Run Time (minutes); 83 % of Scenario EOI Run Time

~ Crew Critical Tasks (2-3)

Yes Technical Specifications Exercised (yes/no)

( Revision 8 Page 22 of 22 SHIFT TURNOVER SHEET Equipment Out of Service/LCOs HPCI was tagged out 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago for repair to the Gland Seal Exhauster.

Expected back in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

Revision 8 Page 22 of 22 BFN CONTROL ROD COUPLING INTEGRITY CHECK 3-SR-3.1. 3.5 (A)

UNIT 3 REV 0014 Page 12 of 359 ATTACHMENT 2 (Page 1 of 2)

Date----~~~------

TODAY CONTROL ROD MOVEMENT DATA SHEET RWM-'- ROD Rod Movement Completed GP NUMBER FROM TO INITIALS UO (AC) 2 2nd (AC) /

Peer Check 3 n/a 22-39 00 14 REMARKS4:

NOTES:

(1) RWM Group may be marked "N/A" if not applicable (i.e., when above the LPSP) .

(2) Fo~ all rod moves to position "48", this signoff verifies coupling integrity was checked in accordance with 3-0I-85.

(3 ) Second-party verification by a second UO, RE, or STA is required ONLY when the RWM is inoperable or bypassed with core thermal power < 10%. A Peer Checker (not requlred in emergencies) may lnitial when second party is not required. "N/A" lf not applicable.

(4) Record the rod number and any problems encountered, as applicable.

Reviewed by: US /TODAY Issued by RE /TODAY unit Supervisor Date Reactor Engineer Date

(

(

l

Browns Ferry Nuclear Plant Unit 3 Surveillance Procedure 3-SR-3.3.1.1.8(11 )

Reactor Protection System Manual Scram Functional Test Revision 0005 Quality Related Level of Use: Continuous Use Effective Date: 09-22-2008 Responsible Organization: OPS, Operations Prepared 8y: Michael S. Rice @ 6934 Approved 8y: John T. Kulisek

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit3 Scram Functional Test Rev.OOOS

( Page 2 of 18 Current Revision Description Pages Affected: All Type of Change: XP Conversion & DCN Tracking Number: 007 PCRs: 08000148 DCN: 51657 This procedure was converted from Word 95 to Word 2003 using Rev 4.

Minor editorial changes (no rev bars)

Deleted hand grenage icon from P&L section. This is no longer used in Operations Procedures.

Added computer pOints SOE178 and SOE179 to the procedure. These were added in DCN 51657. Placing the Reactor Scram Reset Switch to the Reset GP 1/4 position will reset the SOE178 and SOE179 computer points if tripped. Changes made ensure the computer pOinsts operate as designed. See drawings 3-730E915-6 and 3-730E915RH-11, 12, & 18. (PCR 08000148)

Added SR key number to Attachment 1 for Scheduling.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 3 of 18 Table of Contents

1.0 INTRODUCTION

.......................................................................................................... 4 1.1 Purpose ........................................................................................................................ 4 1.2 Scope ............................................................................................................................ 4 1.3 Frequency ..................................................................................................................... 4 1.4 Applicability ................................................................................................................... 4

2.0 REFERENCES

............................................................................................................. 5 2.1 Technical Specifications ............................................................................................... 5 2.2 Final Safety Analysis Report ......................................................................................... 5 2.3 GE Drawings ................................................................................................................. 5 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 6 4.0 PREREQUiSiTES ......................................................................................................... 7 5.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED ............................................ 7 6.0 ACCEPTANCE CRITERIA ........................................................................................... 7 7.0 PROCEDURE STEPS .................................................................................................. 8 7.1 Initial Requirements and Notifications ........................................................................... 8 7.2 RPS Manual Scram Channel A Functional Test ......................................................... 10 7.3 RPS Manual Scram Channel B Functional Test ......................................................... 13 7.4 Completion and Notifications ...................................................................................... 16 8.0 ILLUSTRATIONS/ATTACHMENTS ........................................................................... 16 : Surveillance Procedure Review Form ..................................................... 17 : Control Room Components Affected by Surveillance Procedure Performance ........................................................................... 18

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit3 Scram Functional Test Rev. 0005 Page 4 of 18

1.0 INTRODUCTION

1.1 Purpose This surveillance procedure performs a functional test of the manual scram push-buttons in conformance with the requirements specified in Technical Specification Table 3.3.1.1-1 (Function 11). This procedure meets the requirements of SR 3.3.1.1.14. This procedure, also, partially satisfies the requirements of SR 3.10.3.1 and 3.10.4.1.

1.2 Scope This surveillance procedure completely satisfies the manual scram functional test requirements of Technical Specification 3.3.1.1.

This procedure provides overlap testing 3-SR-3.3.1.1.12 by verifying Scram Solenoid Group A and B Logic Reset lights extinguish with the associated RPS channel trip. This partially satisfies SR 3.3.1.1.14, Logic System Functional Test.

1.3 Frequency Once every 92 days.

1.4 Applicability The SR requirements of this procedure are applicable in Modes 1 and 2. Mode 5 is also applicable with any control rod withdrawn from a core cell containing one or more fuel assemblies.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 5 of 18

2.0 REFERENCES

2.1 Technical Specifications Section 3.3.1.1, 3.10.3 and 3.10.4 2.2 Final Safety Analysis Report Section 7.2, Reactor Protection System 2.3 GE Drawings 3-730E915-6, Elementary Diagram Reactor Protection System 3-730E915 Sh. 7, Elementary Diagram Reactor Protection System 3-730E915RF Sh. 11, Elementary Diagram Reactor Protection System 3-730E915RF Sh. 12, Elementary Diagram Reactor Protection System 3-730E915-13, Elementary Diagram Reactor Protection System

(

3-730E915 Sh. 14, Elementary Diagram Reactor Protection System 3-730E915 Sh. 17, Elementary Diagram Reactor Protection System 3-730E915RF Sh. 18, Elementary Diagram Reactor Protection System

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 6 of 18 3.0 PRECAUTIONS AND LIMITATIONS A. If any control rod actually scrams during performance of this test, wait at least 10 seconds before resetting the scram to ensure that the scram has gone to completion.

B. Corrective Actions shall be handled in accordance with SPP-8.1, Conduct of Testing.

C. The following annunciators should alarm during the performance of this test:

REACTOR CHANNEL A MAN SCRAM (3-XA-SS-SB, window 8)

REACTOR CHANNEL B MAN SCRAM (3-XA-SS-SB, window 9)

D. The following Integrated Computer System (ICS) points should alarm during the performance of this test:

Point SOE033 Point SOE034 Point SOE178 Point SOE179 E. The Critical Step warning designates a step or series of steps for an activity which requires additional focus, attention, and increased awareness. The Operator performing these steps for the activity needs to ensure the Unit Supervisor and other Control Room staff are aware of the evolution. PEER checks are required for this activity and short briefs need to be made prior to performing the evolution. Included in the briefs are worst case scenario and contingencies.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 7 of 18 Date 4.0 PREREQUISITES

[1] VERIFY this copy of 3-SR-3.3.1.1.8(11) is the most current revision.

[2] VERIFY no other tests or maintenance are in progress which could initiate any of the logic in the Reactor Protection System.

5.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED None 6.0 ACCEPTANCE CRITERIA A. Responses which fail to meet the acceptance criteria stated in this section shall constitute unsatisfactory SR results and require immediate notification of the Unit Supervisor at the time of failure.

1. Control Rod Logic Reset Solenoid Group A indicating lights (4) on Panel 3-9-5 are extinguished when Reactor Scram A push-button on Panel 3-9-5 is depressed.

2. Control Rod Logic Reset Solenoid Group B indicating lights (4) on Panel 3-9-5 are extinguished when Reactor Scram B push-button on Panel 3-9-5 is depressed.

B. Steps which verify acceptance criteria are designated by (AC) next to the initial blanks.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit3 Scram Functional Test Rev.OOOS Page 8 of 18 Date 7.0 PROCEDURE STEPS 7.1 Initial Requirements and Notifications

[1] VERIFY Precautions and Limitations in Section 3.0 have been reviewed.

[2] VERIFY Prerequisites listed in Section 4.0 are satisfied.

[3] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

• Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

• System A Back-Up Scram Valve lights 3-IL-99-5A/AB illuminated.

• System B Back-Up Scram Valve lights 3-IL-99-5A/CD illuminated.

• Reactor Scram A push-button extinguished.

• Reactor Scram B push-button extinguished.

• Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) reset.

• Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) reset.

[4] CHECK the following Unit 3 ICS points indicate NOTTRIP using the SOE status display on any available ICS workstation or ICS alarm printer:

• SOE033

• SOE034

• SOE178

• SOE179

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev.OOOS Page 9 of 18 Date 7.1 Initial Requirements and Notifications (continued)

[5] OBTAIN permission from the Unit Supervisor to perform this test. [LER 259/89023]

US

[6] [NRC/C] NOTIFY the Unit Operator (UO) before commencing this instruction. [LER 259/82032]

[7] PERFORM the following:

[7.1] DISCUSS with the UO the effects this procedure has on plant equipment/status.

[7.2] INFORM UO that the Integrated Computer System (ICS) will be affected during performance of this procedure and that ICS alarms may be received.

[7.3] GIVE copy of Attachment 2, Control Room Components Affected by Surveillance Procedure Performance, to the UO as a reminder that this channel is in test.

[8] RECORD the start date, start time, reason for the test, plant conditions, and any pre-test remarks on Attachment 1, Surveillance Procedure Review Form.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 10 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test II Start of Critical Step(s)

[1] MOMENTARILY DEPRESS Reactor Scram A push-button, Panel 3-9-5.

II End of Critical Step(s)

[2] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group A indicating lights (4) extinguished. _ _ (AC)

• One System A Back-Up Scram Valve light 3-IL-99-5A/AB and System B Back-Up Scram Valve light 3-IL-99-5A/CD extinguished.

• Reactor Scram A push-button illuminated.

• Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) in alarm.

[3] VERIFY the following ICS pOints indicate TRIP:

• SOE033

• SOE178

[4] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 1/4 position.

[5] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group A lights 1 and 4 illuminated, and lights 2 and 3 extinguished.

• Both System A Backup Scram Valve lights 3-IL-99-5A/AB illuminated.

• One System B Backup Scram Valve light 3-IL-99-5A/CD illuminated, and one System B Backup Scram Valve light 3-IL-99-5A/CD extinguished.

• Annunciator REACTOR CHANNEL A MAN SCRAM (XA-55-5B, window 8) will NOT reset.

• Reactor Scram A push-button illuminated.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 11 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test (continued)

[6] VERIFY ICS point SOE178 indicates NOTTRIP.

II Start of Critical Step{s)

[7] MOMENTARILY DEPRESS Reactor Scram A push-button.

II End of Critical step(s)

[8] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group A lights 1 and 4 extinguished.

• One System A Backup Scram Valve light 3-IL-99-5NAB extinguished.

[9] VERIFY the following ICS points indicate TRIP:

• SOE033

• SOE178

[1 0] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5 to Reset Gp 2/3 position.

[11] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group A lights 2 and 3 illuminated, and lights 1 and 4 extinguished.

• Both System B Backup Scram Valve lights 3-IL-99-5NCD illuminated.

• One System A Backup Scram Valve light 3-IL-99-5NAB on System A Backup Scram Valve light illuminated, and one System A Backup Scram Valve light 3-IL-99-5NAB extinguished.

• Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) will NOT reset.

• Reactor Scram A push-button illuminated.

[12] VERIFY ICS point SOE033 indicates NOTTRIP.

[13] VERIFY ICS point SOE178 indicates TRIP.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit3 Scram Functional Test Rev. 0005 Page 12 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test (continued)

[14] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 1/4 position.

[15] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

• Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

• System A Back-Up Scram Valve lights 3-IL-99-5A/AB illuminated.

• System B Back-Up Scram Valve lights 3-IL-99-5A/CD illuminated.

• Reactor Scram A push-button extinguished.

(

• Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) reset.

[16] VERIFY the following computer points indicates NOTTRIP.

• ICS pOint SOE033

• ICS point SOE034

• ICS point SOE178

• ICS point SOE179

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit3 Scram Functional Test Rev. 0005 Page 13 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test II Start of Critical Step(s)

[1 ] MOMENTARILY DEPRESS Reactor Manual Scram B push-button, Panel 3-9-5.

i End of Criti'c~I'$tep($)

[2] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group B indicating lights (4) extinguished. _ _ (AC)

• One System B Backup Scram Valve light 3-IL-99-5A/CD and one System A Backup Scram Valve light 3-IL-99-5A/AB extinguished.

• Reactor Scram B push-button illuminated.

• Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) in alarm.

[3] VERIFY the following ICS points indicate TRIP:

• SOE034

• SOE179

[4] MOMENTARILY PLACE the Scram Reset switch, Panel 3-9-5 to Reset Gp 1/4 position.

[5] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group Blights 1 and 4 illuminated and lights 2 and 3 extinguished.

• Both System B Backup Scram Valve lights 3-IL-99-5A/CD illuminated.

• One System A Backup Scram Valve light 3-IL-99-5A/AB illuminated and one System A Backup Scram Valve light 3-IL-99-5A/AB extinguished.

• Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) will NOT reset.

• Reactor Scram B push-button illuminated.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 14 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test (continued)

[6] VERIFY ICS point SOE179 indicates NOTTRIP.

II Start of Critical Step(s)

[7] MOMENTARILY DEPRESS Reactor Scram B push-button.

II End of Critical Step(s)

[8] VERIFY the following on Panel 3-9-S:

• Control Rod Logic Reset Solenoid Group Blights 1 and 4 extinguished.

• One System B Backup Scram Valve light 3-IL-99-SA/CD extinguished.

[9] VERIFY the following ICS points indicate TRIP:

• SOE034

• SOE179

[1 0] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-S, to Reset Gp 2/3 position.

[11] VERIFY the following on Panel 3-9-S:

• Control Rod Logic Reset Solenoid Group Blights 2 and 3 illuminated, and lights 1 and 4 extinguished.

• Both System A Backup Scram Valve lights 3-IL-99-SA/AB illuminated.

• One System B Backup Scram Valve light 3-IL-99-SA/CD illuminated and one System B Backup Scram Valve light 3-'1 L-99-SA/CD extinguished.

• Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-SS-SB, window 9) will NOT reset.

• Reactor Scram B push-button illuminated.

[12] VERIFY ICS point SOE034 indicates NOTTRIP.

[13] VERIFY ICS point SOE179 indicates TRIP.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 15 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test (continued)

[14] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 1/4 position.

[15] VERIFY the following on Panel 3-9-5:

• Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

• Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

• System A Back-Up Scram Valve lights 3-IL-99-5A/AB illuminated.

• System B Back-Up Scram Valve lights 3-IL-99-5A/CD illuminated.

• Reactor Scram B push-button extinguished.

(

• Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) reset.

[16] VERIFY the following computer points indicates NOTTRIP.

• ICS point SOE033

• ICS point SOE034

• ICS point SOE178

• ICS point SOE179

(

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit 3 Scram Functional Test Rev. 0005 Page 16 of 18 Date 7.4 Completion and Notifications

[1] NOTIFY the Unit Operator that this test is complete and PROVIDE status of any Corrective Actions or unsatisfactory test results.

[2] COMPLETE Attachment 1, Surveillance Procedure Review Form up to Unit Supervisor's review.

[3] NOTIFY the Unit Supervisor that this test is complete and PROVIDE status of any Corrective Actions or unsatisfactory test results.

8.0 ILLUSTRATIONS/ATTACHMENTS Attachment 1: Surveillance Procedure Review Form Attachment 2: Control Room Components Affected By Surveillance Instruction Performance

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit3 Scram Functional Test Rev.OOOS Page 17 of 18 Attachment 1 (Page 1 of 1)

Surveillance Procedure Review Form REASON FOR TEST: DATEITIME STARTED D Scheduled Surveillance DATEITIME COMPLETED D System Inoperable (Explain in Remarks) PLANT CONDITIONS D Maintenance (WO No. _ _ _ _ _ __

D Other (Explain in Remarks)

PRE-TESTREMARKS: ___________________________________________

PERFORMED BY:

Initials Name (Print) Name (Signature)

(Test Dir/Lead Perf)

(Test Dir/Lead Perf)

Delays or Problems (If yes, explain in POST-TEST REMARKS)? DYes DNo Acceptance Criteria Satisfied? DYes DNo If the above answer is no, the Unit Supervisor shall determine if an LCO exists. LCO DYes DNo UNIT SUPERVISOR Date INDEPENDENT REVIEWER (OPS) Date _ _ _ _ _ __

SCHEDULING COORDINATOR Date- - - - - - - - - - - -

POST-TEST REMARKS:

The SR Key number is a Cross Reference only and is not part of the procedure. Key # 30811

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11 )

Unit3 Scram Functional Test Rev.OOOS Page 18 of 18 Attachment 2 (Page 1 of 1)

Control Room Components Affected by Surveillance Procedure Performance UNID DESCRIPTION LOCATION 3-XA-55-5B Annunciator REACTOR CHANNEL A MAN SCRAM Panel 3-9-5 Window 8 3-XA-55-5B Annunciator REACTOR CHANNEL B MAN SCRAM Panel 3-9-5 Window 9 ICS point SOE033 ICS point SOE034 N/A INDICATING LIGHTS SCRAM SOLENOID Panel 3-9-5 GROUP A LOGIC RESET N/A BACK-UP SCRAM VALVE INDICATING LIGHTS Panel 3-9-5 The purpose of this sheet is to give the Unit Operator a log of the local alarms and indications in the main control room that will be affected by performance of this surveillance procedure.

This sheet is for operator information only and the photocopy of this sheet given to Unit Operator should be discarded upon notification that the instruction is complete.

HLTS-3-8 Revision 0 Page 1 of 24 SIMULATOR EVALUATION GUIDE TITLE UNIT 3 - 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 o DATE October 12,2008 PROGRAM BFN Operator Training - HLT PREPARED BY: I (Operations Instructor) Date REVIEWED BY: I (LOR Lead Instructor or Designee) Date REVIEWED BY: I (Operations Training Manager or Designee) Date CONCURRED I (Operations Superintendent or Designee) Date VALIDATION : I BY (Operations SRO: Required for Exam Scenarios Only) Date LOGGED-IN: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
_ _ __

(Librarian) Date TASKS LIST UPDATED: - - - - - - - - - - - - - -_____~/ ___-

Date

HLTS-3-8 Revision 0 Page 2 of 24 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION DATE PAGES REVIEWED BY NUMBER OF AFFECTED REVISION 0 INITIAL ISSUE 10/12/08 All

HLTS-3-8 Revision 0 Page 3 of 24 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, ATWS, Steam Line Break in Containment, Drywel/ Spray Failure, Emergency Depressurization.

IV. Length of Scenario: 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> V. Examination 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.

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.

HLTS-3-8 Revision 0 Page 4 of 24

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 respond to EOI-1 and EOI-2 entry conditions for failure to scram and dryweilleak.

HLTS-3-8 Revision 0 Page 5 of 24 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: (Only list those items needed for this scenario which are not normally available in the simulator.)

A. Calculator (If needed, otherwise omit)

B. Control Rod Insertion Sheet (if different then the standard sheet, otherwise omit)

c. Stopwatch (If needed, otherwise omit)

D. Hold Order I Caution tags (If needed, otherwise omit)

E. Annunciator window covers (If needed due to lit alarms, otherwise omit)

F. Steam tables (If needed, otherwise omit)

HLTS-3-8 Revision 0 Page 6 of 24 VIII. Console Operator Instructions A. Scenario File Summary

1. File: bat HLTS 3-8 MF/RF/IOR# Description

a. bat atws100 Hydraulic ATWS

b. mrf eg02 resA prevents the standby stator water cooling pump to auto start

c. ior zdixs927as4b null Prevents "8" side IRM bypass joystick from working

d. imf nm05g 100 Fails IRM "G" high

e. ior zdihs7475a null prevents drywell spray on Loop 2

f. ior an:xa557a22 alarm off Prevents ann. for stator cooling trouble

g. imf rp09c fails "8" RPS manual channel.

HLTS-3-8 Revision 0 Page 7 of 24 VIII. Console Operator Instructions A. Scenario File Summary

3. File: batapp01F MF/RF/IOR# Description

a. mrf rp13a byp Auto Scram bypasses mrf rp13b byp mrf rp13e byp mrf rp13d byp

4. File: batapp02 MF/RF/IOR# Description

a. mrf rp12a test Auto ARI bypassed mrf rp12b test

HLTS-3-8 Revision 0 Page 8 of 24 VIII. Console Operator Instructions B. Console Operator Manipulations ELAP. TIME DESCRIPTION/ACTION Sim. Setup ~ 1%, Start-up (IC-8)

Sim. Setup Inserts Batch file (bat HLTS 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 Fails CRD Flow Control Valve valve is open 10- (imf rd02a) 15 % and C RFP is in service for 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 Swaps CRD Flow Control Valve by board operator (imf rd05 b) to place 3-XS 11 to "B" valve ROLE PLAY: When asked for stabilizing flow (step [11], report 6 gpm

HLTS-3-8 Revision 0 Page 9 of 24 VIII. Console Operator Instructions B. Console Operator Manipulations ELAP. TIME DESCRIPTION/ACTION 2 minutes after Fails H2/02 analyzer CRD flow control valve returned to service and after torus is being inerted When directed by imf ed07a. 480V Unit Board 3A lead examiner failure ROLE PLAY: As OSUS report that there is an overcurrent lockout on 3A 480V Unit Board.

When directed by imf nm05C Fails "C" IRM high lead examiner After Tech. Specs. imf nm05b 100 3:00 addressed for IRM Slowly fails IRM "B" high "C"

After 5 control imf th33c 10 12:30 Starts steam rods inserted per leak in drywell 01-85 If Requested to Defeats auto scram signals perform Appx. 1F (bat app01f) wait 6 minutes If requested to Defeats ARI (bat app02) perform Appx.2, wait 6 minutes

HLTS-3-8 Revision 0 Page 10 of 24 VIII. Console Operator Instructions C. Console Operator Manipulations ELAP. TIME DESCRI PTION/ACTION If requested to bypasses -122 MSIV isolation and perform Appx 8A Group 6 2.45 and +2 inch isolation and 8E (bat app08ae)

Before Orywell Fails power to Loop1 drywell spray Sprays are valve attempted (ior ypovfcv7460 faiLpower_now)

Terminate the scenario when the following conditions are satisfied are at the request of the floorllead instructor/evaluator.

1. Emergency Depressurization completed

2. Water level restored +2" to +51"

3. Reporting requirements completed

HLTS-3-8 Revision 0 Page 11 of 24 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 A TWS. The crew will respond per AOI-100-1 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-3-8 Revision 0 Page 12 of 24 X. Information to Floor Instructor:

A. Ensure recorders are inking and recording and ICS is active and updating.

8. Assign Crew Positions based on the required rotation.

1. SRO: Unit Supervisor

2. ATC: Board Unit Operator

3. BOP: Desk Unit Operator C. Conduct a shift turnover with the Shift Manager and provide the Shift Manager with a copy of the Shift Turnover.

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

E. Terminate the scenario when the following conditions are satisfied are at the request of the floor/lead instructor/evaluator.

1. Emergency Depressurization completed

2. Water level restored +2" to +51"

3. Reporting requirements completed

HLTS-3-8 Revision 0 Page 13 of 24 XI. Simulator Event Guide Event 1: Containment Inerting and rod withdrawal POSITION EXPECTED ACTIONS SAT/UNSAT/COMMENTS SRO Directs power increase re-commenced with control rods per GOI-100-1A Directs steam loads transferred from aux boilers to nuclear steam ATC Place "C" RFP in service per 01-3 ATC Withdraw control rods per 01-85 BOP Commence inerting the suppression Chamber per 01-76 section 5.1

HLTS-3-8 Revision 0 Page 14 of 24 XI. Simulator Event Guide Event 2: CRD flow control valve failure POSITION EXPECTED ACTIONS SAT/UNSAT/COMMENTS ATC Recognizes and reponds to FCV 85-11 A failing closed SRO Directs actions per AOI-85-3 ATC Directs AUO to line up "8" FCV per 01-85 section 6.3 ATC Places Flow controller to balance match flow then place in manual ATC Raises manual adjust pot to raise flow

( then places controller to balance then Auto ATC Directs AUO to remove 85-11A from service.

SRO Recognizes that CRD temps are >350 and declares them slow per T.S. 3.1.4-1 and TI-393

HLTS-3-8 Revision 0 Page 15 of 24 XI. Simulator Event Guide Event 3: H2/02 Analyzer Failure POSITION EXPECTED ACTIONS SAT/UNSAT/COMMENTS BOP Responds to Annunciator for H2/02 analyzer malfunction BOP Recognizes failure of the "B" Analyzer and swaps the "A" analyzer to Suppression Chamber SRO Refers to Tech. Spec. 3.6.3.2 and TRM 3.6.2 and determines no action required

HLTS-3-8 Revision 0 Page 16 of 24 XI. Simulator Event Guide Event 4: IRM FAILURE POSITION EXPECTED ACTIONS SAT/UNSAT/COMMENTS ATC Recognizes 1/2 scram and IRM "e" failed high SRO Recognizes that IRM "G" already bypassed and cannot bypass IRM "e" SRO 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

HLTS-3-8 Revision 0 Page 17 of 24 Event 5: Loss of 480V Unit Board 3A CREW Recognize loss of 480V Unit Board 3A Recognize trip of 3A Bus Duct Cooling fan and starts 3B Bus Duct cooling Fan Recognize failure of 3B Stator Water Cooling pump to auto start and manually starts 3B Stator Water Cooling Pump.

Verifies/Starts 3B EHC pump SRO Dispatches Outside Unit Supervisor to check on 3A 480V Unit Board

HLTS-3-8 Revision 0 Page 18 of 24 Event 6: "B" IRM Failure Upscalel Scram/ATWS POSITION EXPECTED ACTIONS SAT/UNSAT/COMMENTS ATC Recognizes IRM "B" failing upscale and attempts to range up.

ATC Reports failure to range to US SRO Directs manual scram ATC Manually scrams reactor Reports failure to scram and initiates a channel of ARI ATC ATC Reports all rods NOT inserted ATC Reports power < 5%

SRO Recognizes that no entry conditions exist for EOls and directs BUO to take actions per AOI-1 00-1.

SRO Directs RPV water level be controlled +2" to +51" BOP Controls water level +2" to +51" with RFPs, HPCI, RCIC 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 01-85 SRO Declares Alert (1.2.A)

HLTS-3-8 Revision 0 Page 19 of 24 Event 7: Steam Leak in Drywell Crew Identifies drywell pressure/temperature rise SRO 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 .

SRO Verifies appropriate group isolations SRO Enters C5 and directs ADS inhibited and Appendices 8A and 8E performed SRO Verifies Diesel generators start BOP Directs AUO to monitor D/G SRO Directs the following:

• All available drywell cooling in service

• Venting per App 12

• "A" H2/0 2 Analyzers placed in service BOP Verifies all drywell blowers in service BOP Vents per Appendix 12 BOP Places "A" H2/02 Analyzers in service using keylock bypass switches

HLTS-3-8 Revision 0 Page 20 of 24 BOP 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:

SRO Directs Torus Sprays be placed in service per Appendix 17C

HLTS-3-8 Revision 0 Page 21 of 24 BOP Places Torus sprays in service per Appendix 17C SRO When PSC pressure exceeds 12 psig or if determines drywell temperature to exceed 280 degrees F

• verifies in Safe Region of DW spray curve verifies SP level <18 feet SRO Directs drywell blowers and Recirc pumps removed from service SRO Directs drywell sprays initiated per Appx.17b BOP Attempts to spray drywell and determines neither loop of drywell sprays are operable.

SRO Determines that conditions are such that the drywell temperature cannot be maintained below 280 F and Emergency Depressurization is Required SRO Directs all injection into the RPV be stopped and prevented except from CRD, SLC, and RCIC per Appx. 4 BOP/ATC Stops and prevents injection from HPCI, Core Spray, RHR, and Cond/FW per Appx. 4 SRO Enters C2 and directs 6 ADS valves opened BOP Opens 6 ADS valves SRO Directs injection re-commenced not before 190 psig BOP/ATC Re-commences injection at 190 psig with either condensate or RHR

HLTS-3-8 Revision 0 Page 22 of 24 SRO Directs RPV level restored to 2-51 inches with either condensate or RHR 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 SRO Directs SLC injection prior to 110 F per Appx. 3A if not sub-critical (conditional)

ATC Injects SLC per Appx. 3A

HLTS-3-8

( Revision 0 Page 23 of 24 XII. Crew Critical Tasks (If an evaluated scenario)

Task SAT/UNSAT

1. Inhibit ADS

2. Emergency depressurize before drywell temperature exceeds 280 of

3. Stop and prevent injection per Appx 4 prior to emergency depressurizing.

4. Maintain RPV level above -180 inches

5. Inject SLC prior to 110°F (conditional)

(

HLTS-3-8 Revision 0 Page 25 of 24 SCENARIO REVIEW CHECKLIST SCENARIO NUMBER HLTS3-8 L 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

_1_ Malfunctions That Occur After EOI Entry; List: (1-4)

1) 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)

~ Major Transients; List: (1-2)

1) ATWS

2) MSL Leak in drywell

3) Emergency Depressurization L EOls used; List: (1-3)

1) EOI-1

2) EOI-2

~ EOI Contingencies Used; List: (0-3)

1) C2

2) C5 70 Run Time (minutes) 28 EOI Run Time (minutes); 40 % of Scenario EOI Run Time 4 Crew Critical Tasks

~ Technical Specifications Exercised (yes/no)

Revision 0 Page 25 of 25 SHIFT TURNOVER SHEET Equipment Out of Service/LCOs "G" IRM bypassed 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 30-11 Place "3C" RFP in service at 850 psig for level control.

38 CRD pump tagged for bearing replacement Unusual Conditions/Problem Areas Potential for icing of lines due to freezing rain