Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML102510316
Person / Time
Site:	Beaver Valley
Issue date:	08/05/2010
From:	D'Antonio J; Operations Branch I
To:	; FirstEnergy Nuclear Operating Co
	Hansell S
Shared Package
ML100560049	List: IR 05000412/2010301; ML101040650; ML102180301; ML102510196; ML102510217; ML102510235; ML102510316; ML102520175; ML102520178; ML102520182; ML102650433; ML102650445; ML102650459; ML111680038; ML111680049;
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RTL#A5.640U 112-ADM-130l.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 KJA

REFERENCE:

004A4.07 3.9/3.7 TASK ID: 0071-011-01-013 004A4.12 3.8/3.3 JPM APPLICATION: ~ REQUALIFICATION rxI INITIAL EXAM D TRAINING D FAULTEDJPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requa! Ex am D BVT 0 Simulate 0 Simulator 0 Initial Exam D NRC 0 Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 10 Minutes Actual minutes Critical: rxI No Time: Time:

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Approximately 226 gallons of primary makeup water added to the RCS at a rate of75 gpm.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform a Reactor Coolant System dilution.

INITIAL CONDITIONS:

The plant is 100% power, with all systems in NSA.

The Control Rods are fully withdrawn.

Tavg is 1°F below Tref.

Current RCS boron concentration is 1030 ppm.

lAW the current reactivity placard, 226 gallons of dilution water will be needed to raise Tavg 1°F.

INITIATING CUE: Your supervisor directs you to dilute the RCS 226 gal in accordance with 20M-7.4.AR, "Blender Operation in Mode I", at a rate of75 gpm to raise Tavg 1°F. All procedure required initial conditions are satisfied. It is NOT desired to take manual control ofVCT Level and Pressure. It is desired to use the "DILUTE" Mode.

REFERENCES:

20M-7.4.AR, "Blender Operation in Mode 1", Revision 7 Reactivity Plan (Placard) to coincide with 226 gals/oF.

TOOLS: None HANDOUT: 20M-7.4.AR, "Blender Operation in Mode 1", Revision 7

RTL#A5.640U 1/2-ADM-1301.F04 Page 5 of 10 Revision 1 CANDIDATE DmECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

o Read:

TASK: You are to perform a Reactor Coolant System dilution.

INITIAL CONDITIONS:

The plant is 100% power, with all systems in NSA.

The Control Rods are fully withdrawn.

Tavg is 1°F below Tref

Current RCS boron concentration is 1030 ppm.

lAW the current reactivity placard, 226 gallons of dilution water will be needed to raise Tavg 1°F.

INITIATING CUE:

Your supervisor directs you to dilute the RCS 226 gal in accordance with 20M-7.4.AR, "Blender Operation in Mode I", at a rate of75 gpm to raise Tavg 1°F. All procedure required initial conditions are satisfied. It is NOT desired to take manual control ofVCT Level and Pressure. It is desired to use the "DILUTE" Mode.

o At this time, ask the evaluator any questions you have on this JPM.

o When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

o Point to any indicator or component you verify or check and announce your observations.

o After determining the Task has been met announce" I have completed the JPM".

Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-1301.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NlJMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 STEP I STANDARD

( "c" Denotes CRITICAL STEP) __ (Indicate "s" FOR SAT or "U" FOR UN SAT):::}

SIMULATOR SETUP:

Initialize to a MOL 100% power IC. Reduce Tavg

~Ol F below Tref.

Adjust [2CHS*FCY114A] pot setting to 568 units EVALUATOR CUE:

Provide candidate with a copy of20M-7.4.AR, "Blender Operation in Mode 1". When candidate is ready to begin JPM, PLACE the simulator in RUN.

START TIME: _ _ _ _ _ __

1. Review procedure. 1.1 Reviews procedure provided.

COMMENTS:

2. At the discretion of the RO and 2.1. NIA _. Initiating cue states that it is NOT desired to SM/US, take control ofYCT take manual control of YCT level and pressure.

Level and Pressure.

EVALUATOR CUE:

IF necessary, remind the candidate to refer to initiating cue.

COMMENTS:

RTL#A5.640U 1/2-ADM-130LF04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-089 I JPM REVISION: 7 JPM TITLE: RCS Dilution I STEP STANDARD

. ("C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU I 3.C Place Boric Acid Blender 3.1C Places Boric Acid Blender Makeup Control Switch to Control Switch to Stop STOP.

3.2 Verifies green light - LIT and red light NOT LIT.

COMMENTS 4.C Set [2CHS*FCV114A] to 4.1C Adjusts [2CHS*FCVl14A] pot setting to 468 units desired flow rate. based on the following formula:

75gpm =4.68 16gpm EVALUATOR NOTE:

Pot should be set at 468 units +/-2 units.

COMMENTS:

5.C Set Total Makeup From Blender 5.1C Adjusts [2CHS-FQIS168] to 226 (Green LED)

Flow Totalizer.

S.2C Depresses [2CHS-FQIS168] RESETPB.

5.3 Verifies [2CHS-FQIS168] is reading ZERO (Red LED).

CONIMENTS:

i

RTL#A5.640U 112-ADM-130l.F04 Page 8 oflO Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 I STEP STANDARD I I U "e" Denotes CRITICAL STEP) I_ --<!ndicate "S" FOR SAT or "U" FOR UNSAT)=> .~

6. Ensure [2CHS-FQIS 113], 6.1. Verifies that [2CHS-FQIS ll3J, Boric Acid Flow To Boric Acid Flow To Blender Blender is set to ZERO (Red and green LED).

is set to zero.

COMMENTS:

7.C Place makeup Mode Selector 7.1C Places the makeup Mode Selector switch in DILUTE.

switch in Dilute or Alternate Dilute. EVALUATOR NOTE:

Initiating cue stated that it is desired to use the I "DILUTE" mode.

I COMMENTS:

8.C Initiate dilution. S.IC Places Boric Acid Blender Makeup Control Switch to START.

8.2 Verifies green light - NOT LIT and red light LIT.

COMMENTS:

RTL#A5.640U 112-ADM-130l.F04 Page 9 oflO Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 STEP I( "e" Denotes CRITICAL ~TEP) I. STANDARD ~ndicate "S" FOR SAT or "U" FOR UNSA!):::::>

ISIU J

9. Verify proper operation. 9.1 Verifies [2CHS*FCV114B] green light NOT LIT and red light - LIT.

9.2 Verifies [2CHS-FRl13] is reading ~ 75 gpm.

COMMENTS EVALUATOR NOTE: The candidate may elect to NtA JPM Steps # 10 & 11 because they are only necessary for large amounts ofPG water or frequent

10. Operate pressurizer heaters to dilutions.

equalize boron concentration.

10.1 Places control switch for 2RCS*H2A, B, D, or E to ON.

10.2 Verifies green light - NOT LIT and red light - LIT.

EVALUATOR CUE:

Ifnecessary, role-play the Unit Supervisor and direct candidate to energize one additional backup heater group.

COMMENTS:

I

RTL#AS.640U 1I2-ADM-1301.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "Sft FOR SAT or "U" FOR UNSAT):=)

11. Verify at least one RCP in 11.1 Checks at least one RCP in operation and notes this operation at least once per hour must be done at least once per hour.

during dilution and document in narrative log. 11.2 Indicates this check must be logged in the Narrative Log.

EVALUATOR CUE:

Another operator will make the appropriate log entry.

COMMENTS:

12. When the dilution or series of 12.1 Verifies Total Makeup From Blender Flow Totalizer dilutions is complete, Perform [2CHS-FQISI68] reaches 226 gal.

the following to place the makeup control systems in 12.2 Places Boric Acid Blender Makeup Control Switch automatic operations: to STOP.

Place the Boric Acid Makeup Blender Control Switch in 12.3 Verifies green light - LIT and red light - NOT LIT.

STOP. COMMENTS:

EVALUATOR NOTE:

It is not desired to set-up the blender for AUTOMATIC operation.

EVALUATOR CUE:

That Completes this JPM STOP TIME: ----------------

RTL#A5.640U 112-ADM-1301. F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-S60 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation JPMREVISION: 3 KJA

REFERENCE:

006A4.0S 3.9/3.8 TASK ID: 0531-002-05-013 006A4.07 4.4/4.4 JPM APPLICATION: IZl REQUALIFICATION IZl INITIAL EXAM o TRAINING

[g] FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

0 Perform 0 Plant Site [J Annual Requal Ex am D BVT 0 Simulate 0 Simulator !~ Initial Exam 0 NRC 0 Classroom !~ OJT/TPE 0 Other:

[J Training

[J Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 10 Minutes Actual minutes Critical: IZl No Time: Time:

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Cold Leg Recirculation established.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform the task, Transfer from Hot Leg to Cold Leg Recirculation.

INITIAL CONDITIONS:

The plant has experienced a large break LOCA 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago with all systems having functioned as designed.

The EOP's have been implemented normally to this point and the SI headers are currently split as expected.

The plant is currently in Hot Leg recirculation and has been for 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

A transfer from Hot Leg to Cold Leg Recirculation is required.

Charging High Head Safety Injection Pump [2CHS*P21C] is cleared for pump repairs.

INITIATING CUE: Your supervisor has directed you to transfer recirculation of the RCS from the Hot Legs to the Cold Legs using EOP ES-1.S, "Transfer from Hot Leg Recirculation to Cold Leg Recirculation".

REFERENCES:

Unit 2 EOP ES-1.5, "Transfer from Hot Leg Recirculation to Cold Leg Recirculation", Issue 1C, Rev 6 TOOLS: Shorting Bars HANDOUT: Unit 2 EOP ES-1.5, "Transfer from Hot Leg Recirculation to Cold Leg Recirculation", Issm, 1C, Rev 6

RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of 10 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perform the task, Transfer from Hot Leg to Cold Leg Recirculation.

INITIAL CONDITIONS:

The plant has experienced a large break LOCA 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago with all systems having functioned as designed.

The EOP's have been implemented normally to this point and the SI headers are currently split as expected.

The plant is currently in Hot Leg recirculation and has been for 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

A transfer from Hot Leg to Cold Leg Recirculation is required.

Charging High Head Safety Injection Pump [2CHS*P21C] is cleared for pump repairs.

INITIATING CUE: Your supervisor has directed you to transfer recirculation of the RCS from the Hot Legs to the Cold Legs using EOP ES-l.S, "Transfer from Hot Leg Recirculation to Cold Leg Recirculation".

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM" .

o Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#AS.640U 1I2-ADM-130l.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-560 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation JPM REVISION: 3

, STEP STANDARD I ( "e" Denotes CRITICAL STEP) Indicate "s" FOR SAT or "U" FOR UNSAT)=>

SIMULATOR SETUP:

Insert a Large Break LOCA and perform E-O, E-l, ES 1.3 and ES-1.4 actions. (Note this takes several hours of setup work) To setup for ES-1.S and associated fault which trips [2CHS*P21B] when 2SIS*MOV8888B is opened perform the following:

Select Event Trigger

Enter Event #

Enter in Event Tab XA20058R == 1 Ensure 2CHS*21C is on clearance (Yellow Tagged)

START TIME: _ _ _ _ _ __

1. Review procedure. 1.1 Reviews EOP ES-l.S.

COMMENTS:

2.1 Recirc Spray Pumps - no 2.1 Verifies 2RSS*P21C & D ammeters, flow indicators signs of cavitation. and pressure indications all STABLE.

2.2 Align RSS Pumps for Cold 2.2 Verifies [2RSS*P21C & D] BOTH Red lights - LIT Leg Recirculation: Verify White lights - NOT LIT.

[2RSS*P21C & DJ running.

COMMENTS:

EVALUATOR CUE:

A Shorting Bar will be needed in the next step. When requested, Role-play the Shift Manager and supply the shorting bar.

RTL#A5.640U 112-ADM-130I.F04 Page 7 oflO Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-560 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation JPM REVISION: 3 STEP

( "e" Denotes CRITICAL STEP) \

STANDARD

~ndicate "s" FOR SAT or "U" FOR UNSAT)=>

IStu 3.C Insert Shorting Bar and close 3.1 Contacts Shift manager and requests a shorting bar.

[2SIS*MOV8889].

(ES-1.5 steps 2.b & c) 3.2C Inserts into [2SIS*MOV8889] jacks.

3.3C Places [2SIS*MOV8889] CS to CLOSE.

3.4 Verifies Green light - LIT and Red light - NOT LIT.

COMMENTS:

4.C Close [2SIS*MOV8887A & 4.1 C Places [2SIS*MOV8887 A and B] CS to CLOSE.

B].

(ES-l.5 step 2.d) 4.2 Verifies Green lights LIT and Red lights - NOT LIT.

COMMENTS:

S.C Open [2SIS*MOV8888A & S.lC Places [2SIS*MOV8888A and B] CS to OPEN.

B].

5.2 Verifies Green lights - NOT LIT and Red lights (ES-l.S step 2.e) LIT.

EVALUATOR NOTE:

[2CHS*P21B] is triggered to trip when 2SIS*MOV8888B control switch is placed to OPEN.

COMMENTS:

RTL#A5.640U 1I2-ADM-130 1.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-560 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation JPM REVISION: 3 I

STEP

("C" Denotes CRITICAL STEP)

ISTANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I Stu I

6. Verify flow indicated on 6.1. Verifies flow indicated on [2SIS*FI945 & 946].

[2SIS*FI945 & 946].

COMMENTS:

(ES-1.5 step 2.f)

FAULT STATEMENT:

Alternate path begins here: Only ONE CHS Pump

[2CHS*P21A] is available.

7. Verify two Charging Pumps 7.1 Verifies [2CHS*P21A] White light NOT LIT and runmng. Red light - LIT.

(ES-1.5 step 3.a and RNO a) 7.2 Verifies [2CHS*P21B] White light - LIT and Red light - NOT LIT.

7.3 Determines that neither of the other Charging Pumps can be started and continues with RNO response.

EVALUATOR CUE: If an NLO is dispatched to check charging pump status, role play and acknowledge request. Cue candidate to continue on in the procedure.

COMMENTS:

L~ ____________________ ~ ___________________________________ ~_~

RTL#A5.640U 112-ADM-130l.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE

]PM NUMBER: 2CR-560

]PM TITLE: Transfer from Hot Leg to Cold Leg Recirculation

]PM REVISION: 3 I STANDARD UNSAT)~ \ Stu I STEP

("e" Denotes CRITICAL STEP) Jlndicate "s" FOR SAT or "U" FOR 8.C Stop the running Charging 8.IC Places [2CHS*P2IA] CS to STOP.

Pump.

8.2 Verifies White light - LIT and Red light NOT LIT.

(ES-1.5 step 3.a RNO a.I)

COMrvIENTS:

EVALUATOR CUE:

Shorting Bars will be needed in the next two steps.

When requested, Role-play the Shift Manager and supply the shorting bars.

9.C Insert Shorting Bars and close 9.1 Contacts Shift manager and requests a shorting bar.

[2SIS *MOY869 A].

9.2C Inserts into [2SIS*MOY869A] jacks.

(ES-l.S step 3.c & d) 9.3C Places [2SIS*MOY869A] CS to CLOSE.

9,4 Verifies Green light - LIT and Red light - NOT LIT.

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORN[ANCE MEASURE JPM NUMBER: 2CR-560 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation JPM REVISION: 3

\ STEP \ STANDARD

( "e" Denotes CRITICAL STEP) ---.i!ndicate "S" FOR SAT or "U" FOR UNSA 10.c Open [2SIS-MOV836]. 10.1 Contacts Shift manager and requests a shorting bar.

(ES-1.5 step 3.e & t) 10.2C Inserts into [2SIS-MOV836] jacks.

10.3C Places [2SIS-MOV836] CS to OPEN.

10.4 Verifi(lS Green light - NOT LIT and Red light LIT.

COMMENTS:

11. C Start previously running 1LIC Places [2CHS*P21A] CS to START.

Charging Pump.

11.2 Verifies White light - NOT LIT and Red light (ES-1.5 step 3.g) LIT.

COMMENTS:

12. Verify flow indicated on 12.1 Verifies flow indicated on [2SIS*FI940].

[2SIS *FI940].

COMMENTS:

(ES-1.5 step 3.h)

EVALUATOR CUE:

That completes this JPM.

STOPTIME: ______________

RTL#AS.640U 1I2-ADM-130l.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-056 JPM TITLE: Place Exc{~ss Letdown in Service JPM REVISION: 7 KIA

REFERENCE:

004A4.06 3.6/3.1 TASK ID: 0071-019-01-013 004A.4.08 3.8/3.4 004A2.07 3.4/3.7 JPM APPLICATION: C8J REQUALIFICATION r2J INITIAL EXAM D TRAINING D F AUL TED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator [J Initial Exam D NRC D Classroom D OJT/TPE 0 Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 10 Minutes Actual minutes Critical: C8J No Time: Time:

JPM RESULTS:

D SAT D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: :~amt")SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#AS.640U 1I2-ADM-130LF04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Excess letdown flow established. Normal charging and letdown secured. Excess letdown heat exchanger outlet temperature ~140<J<.

RECOMMENDED Simulator ST ARTING LOCATION:

DIRECTIONS: You are to place Excess Letdown in Service.

INITIAL CONDITIONS: The plant is operating at 25% power during a plant startup. All systems are operating normally except for a leak on the CCP supply line to the non-regenerative heat exchanger. Isolation of this leak will require that normal charging and letdown be secured. Normal letdown is in servIce.

INITIATING CUE: The Unit Supervisor directs you to place excess letdown in service to the VCT and secure normal charging and letdown in accordance with 20M-7.4.G, "Excess Letdown Heat Exchanger Operation". Establish Excess Letdown from the "A" RCS loop. You are to maintain excess letdown heat exchanger outlet temperature :S;140<J< and report when task is complete.

REFERENCES:

20M-7.4.G, Revision 6, "Excess Letdown Heat Exchanger Operation" TOOLS: None HANDOUT: 20M-7.4.G, Revision 6, "Excess Letdown Heat Exchanger Operation"

RTL#A5.640U 1/2~ADM*1301.*F04 Page 5 of 10 Revision 1 CANDIDATE DIRECTION SHEET

TillS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to place Excess Letdown in Service.

INITIAL CONDITIONS: The plant is operating at 25% power during a plant startup. All systems are operating normally except for a leak on the CCP supply line to the non-regenerative heat exchanger. Isolation of this leak will require that normal charging and letdown be secured. Normal letdown is in service.

INITIATING CUE: The Unit Supervisor directs you to place excess letdown in service to the VCT and secure nonna! charging and letdown in accordance with 20M-7.4.G, "Excess Letdown Heat Exchanger Operation". Establish Excess Letdown from the "A" RCS loop. You are to maintain excess letdown heat exchanger outlet temperature :'S140OP and report when task is complete.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce If I have completed the JPM" .

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION: 7 I STEP

("C" Denotes CRITICAL STEP)

ISTANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=>

SIMULATOR SETUP:

Initialize to any 25% power IC set.

EVALUATOR NOTE: Provide the candidate a copy of20M-7.4.G. When candidate is ready to begin, place simulator in RUN.

START TIME: _ _ _ _ _ __

1. Reviews 20M-7.4.G, "Excess 1.1 Reviews 20M-7.4.G.

Letdown Heat Exchanger Operation." COMMENTS:

2. Verify Open (2CCP*AOV170), 2.1 Verifies 2CCP*AOV170 OPEN.

Shield Tank & Ex LIDN CLRS i 2.2 Verifies Green light - NOT LIT and Red light - LIT.

WTR Supply Iso1. VIvo COMMENTS:

3. Verify Open (2CCP* AOV105), 3.1 Verifies 2CCP* AOVI05 OPEN.

Excess Letdown Cooler Inlet 3.2 Verifies Green light - NOT LIT and Red light - LIT.

VIvo COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-056 I JPM TITLE: Place Excess Letdown in Service JPM REVISION: 7 I STEP I STANDARD

("e" Denotes CRITICAL STEP) (Indicate liS" FOR SAT or "un FOR UNSAT)=> i Stu I EVALUATOR CUE: Role play the US and inform the candidate that the reactor plant vents and drains system are aligned to receive letdown.

4.C Position (2CHS*HCV389), Ex 4.1C Positions (2CHS*HCV389) to P.D.T. Tank position.

L TDN Hx Disch Diverting Valve to Pri Drn TFR TK 4.2 Verifies Red Valve position light (PR! DRN TRF position. TK) LIT and Red Valve position light (VCT)

NOT LIT COMMENTS:

EVALUATORIINSTRUCTOR CUE:

When asked, role play the US and inform the candidate that MCC-2-l7 Cub 5D, Loop A Drain Isolation Valve (2RCS*MOV557 A) is ON after having the instructor SELECT REMOTE: Select LOA-LOV304, Click RACKIN to provide power to Loop A Drain Iso1. Valve.

S.C Open (2RCS*MOV557A) "RCS 5.le Places control switch for 2RCS*MOV557A to Loop A Drain Valve". OPEN. (BB-A) 5.2 Verifies Red Light - LIT and Green Light - NOT LIT.

COMMENTS:

I

RTL#A5.640U 1I2-ADM-1301.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-056 i JPM TITLE: Place Excess Letdown in Service JPMREVISION: 7 i I STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=:;. SIU 6.C Open (2CHS*MOV201), 6.1C Places (2CHS*MOV201) to OPEN position. (BB-A).

"Excess Letdown Heat Exchanger Inlet Valve". 6.2 Verifies Red Light - LIT and Green Light - NOT LIT.

COMNIENTS:

7. Monitor Seal Injection flow on 7.1 Monitors Seal Injection flow on 2CHS-FI130A, 2CHS-FI130A, 127 A, 124A and 127A, 124A and leakoffflow on 2CHS-FR154A leakoffflow on 2CHS-FR154A while adjusting excess letdown flow. (VB-A) while adjusting excess letdown flow. COMMENTS:

8.C Establish excess letdown flow 8.lC Locates hand control station for (2CHS*HCV137) slowly, using Excess Letdown and slowly turns the pot in the clockwise direction to Hx Discharge. Press Reducing open the valve.

Valve (2CHS-HCV137), to allow for warm-up of heat 8.2C Controls Ex Letdown HX temperature at less than or exchanger. equal to140°F on 2CHS-TI139.

8.3 Contro:ts Ex Letdown HX Pressure < 135 psig on

[2CHS-PI138].

EVALUATOR CUE: Ten (10) minutes has elapsed.

i COMMENTS:

i

R1L#A5.640U 112-ADM-130l.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION: 7 STEP I STANDARD

( "e" Denotes CRITICAL STEP) ~ndi<:ate "S" FOR SAT or "u" FOR UNSAT)=:=> Stu 9C Ensures Ex. LTDN. HX. 9.1C Locates switch for 2CHS*HCV389 and places switch Discharge. "Diversion in VC Tank position.

Valve" (2CHS*HCV389) is aligned to VCT. 9.2 Verifies Red light (VCT Tank) - LIT and RED light (pR! DRN TRF TK) - NOT LIT.

COMMENTS:

10. Monitor Seal Injection flow 10.1 Verifies seal injection flow meters 2CHS-FIl30A, and adjust if necessary. 127A, 124A indicate 6-9 gpm per pump.

10.2 Coordinates efforts with local operator and adjusts (CHS *179, 178, 180) to maintain 6 - 9 gpm, if necessary.

COMMENTS:

I llC. Close Letdown Orifice 11.1C Places 2CHS* AOV200A and 200B control switches Vlvs 2CHS* AOV200AIB. to CLOSED position.

11.2 Verifies Green Lights - LIT and Red Lights - NOT LIT.

COMMENTS:

12C. Place auto/manual station for 12.1C Depresses 2CHS*FCV122 MANUAL .. pushbutton; Charging Pumps Discharge demand increases to 100% to CLOSE valve.

Flow Control Valve (2CHS FCV122) to MANUAL and COMMENTS:

CLOSE the valve.

i

RTL#A5.640U 112-ADM-130 l.F04 Page 10 oflO Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION: 7 I STEP

("C" Denotes CRITICAL STEP)

ISTANDARD Indicate "S" FOR SAT or "U" FOR UNSA D.C Close (2CHS*MOV289), 13.1C Places 2CHS*MOV289 control switch to CLOSE Normal Charging Header position.

Isolation Valve.

13.2 Verifies Green Light LIT and Red Light NOT LIT.

COMMENTS:

EVALUATOR CUE: Another operator will perform 20ST-6.4 and adjust 2CHS-HCV186 as needed. Shift Manager will discuss chemistry concerns with the Chemistry Department.

14. Report to supervisor. 14.1 Notifies Unit Supervisor that Excess Letdown has been placed into service o

to VCT, and the outlet temperature is <140 p and pressure is <135 psig.

COMMENTS.

EVALUATOR CUE:

That completes this JPM.

STOP TIME: ----------------

RTL#A5.640U 112-ADM-130l.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 KIA

REFERENCE:

003A2.01 3.5/3.9 TASK ID: 0061-046-04-012 015/017AA1.22 4.0/4.2 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM o TRAINING o FAULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

0 Perform 0 Plant Site 0 Annual Requal Exam 0 BVT 0 Simulate 0 Simulator [J Initial Exam 0 NRC 0 Classroom [J OJT/TPE 0 Other:

[J Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time k8J Yes Allotted 15 Minutes Actual minutes Critical: 0 No Time: Time:

JPMRESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-1301.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD:

2RCS*P21A tripped,

2RCS*PCV455A closed,

2CHS*MOV303A closed greater than three (3) minutes, but less than five (5) minutes, following the time that the reactor coolant pump was tripped.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to respond to reactor coolant pump seal trouble annunciator.

INITIAL CONDITIONS: The plant is in Mode 3 at normal operating temperature and pressure, with the reactor trip breakers open and with all RCS loops in operation.

INITIA TING CUE: Annunciator A2-4D, "REACTOR COOLANT PUMP SEAL TROUBLE", will alarm soon. You are to analyze the problem and respond accordingly.

This JPM contains time critical elements.

REFERENCES:

20M-7.4.AAH, "Reactor Coolant Pump Seal Trouble", Rev. 22 Unit 2 AOP 2.6.8, "Abnormal RCP Operation", Rev. 6 Unit 2 EOP E-O, "Reactor Trip or Safety Injection", Issue IC, Rev. 8 TOOLS: Plant computer.

HANDOUT: 20M-7.4.AAH, "Reactor Coolant Pump Seal Trouble", Rev. 22 Unit 2 AOP 2.6.8, "Abnormal RCP Operation", Rev. 6

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of 10 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to respond to reactor coolant pump seal trouble annunciator.

INITIAL CONDITIONS: The plant is in Mode 3 at normal operating temperature and pressure, with the reactor trip breakers open and with all RCS loops in operation.

INITIATING CUE: Annunciator A2-4D, "REACTOR COOLANT PUMP SEAL TROUBLE", will alarm soon. You are to analyze the problem and respond accordingly.

This JPM contains time critical elements_

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPMI!.

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce I have completed the JPM".

D Then hand this sheet to the evaluator.

II

R1L#A5.640U 1I2-ADM-1301.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 i STEP STANDARD

("C" Denotes CRITICAL STEP) ~dicate "s" FOR SAT or "U" FOR UNSA SIMULATOR SETUP:

Depending on desired core life, initialize IC-3, II, or

25. Mode 3, all RCP's running, NOPINOT, open RTB and allow the plant to stabilize. Failure to occur 30 seconds after simulator to run.

Set Trigger 1 to actuate 2RCS-P2IA #1 seal failure, malfunction. Set Malf RCPO 1A severity 10, ramp time 30 sec, delay time = 30 sec.

EVALUATOR CUE:

When candidate says that they are ready to Begin the JPM, go to run on the simulator and initiate Trigger 1 to actuate the malfunction.

ST.ART TIME: _ _ _ _ _ __

1.1 Acknowledge Annunciator A2 1.1 Acknowledges Annunciator A2-4D, "REACTOR 4D, "REACTOR COOLANT COOLANT PUMP SEAL TROIJBLE".

PUMP SEAL TROUBLE".

1.2 Obtain procedure. 1.2 Refers to ARP A2-4D (20M-7A.AAH), or may directly enter AOP 2.6.8.

EVALUATOR CUE: Provide candidate a copy of whichever procedure is referenced, either ARP A2-4D (20M-7.4.AAH) or AOP 2.6.8 (20M-S3CA.2.6.8).

The ARP can be provided during the JPM Briefing.

NOTE: The candidate may directly enter AOP 2.6.8 which is acceptable in which case step # 2 is NI A.

COMMENTS:

RTL#A5.640U 1/2-ADM-130l.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6

! STEP

( "e" Denotes CRITICAL STEP)

I STANDARD (Indicate "S" FOR SAT or "U" FOR UN SAT)=> I

2. Evaluate RCP status. 2.1 Evaluates RCP parameters.

2.2 Locates and identifies RCP # 1 sealleakoff on [2CHS FR154A] is higher than normal.

2.3 Refers to ARP section 4 and transitions to AOP 2.6.8.

COMMENTS.

3.1 Proceed to AOP 2.6.8 Step # 1. 3.1 Check criteria for immediate RCP shutdown in Table 1 (Left Hand Page) for any criteria exceeded.

3.2 Check Criteria for Immediate 3.2 Identifies sealleakoff flow >6 GPM immediate RCP RCP Shutdown in Table 1 shutdown criteria is met.

(Left Hand Page)

EVALUATOR NOTE: [2CHS-FR154A] upper range is 6 gpm.

COMMENTS:

! i ,

RTL#A5.640U 1I2-ADM-130 l.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 ISTEP

("C" Denotes CRITICAL STEP) ISTANDARD

.--LIndicate "s" FOR SAT or "U" FOR UNSAT):::::>

I I S/u EVALUATOR NOTE: It is expected that the candidate will not trip the reactor or transition to EOP E-O, since the reactor is already shutdown. If this is the case, NIA ]PM steps 4-8 and continue with JPM step 9.

]PM steps 4-8 are to be used if the candidate does trip the reactor and transitions to EOP E-O in response.

4.1 Trip the reactor, 4.1 Verifies reactor is tripped.

(AOP 2.6.8 step 1.a.l) 4.2 Go to E-O, "Reactor Trip or 4.2 Transitions to E-O, "Reactor Trip or Safety Injection" Safety Injection". for verification ofImmediate Manual Actions.

COMMENTS:

EVALUA.TOR CUE: Provide candidate a copy of procedure EOP E-O if candidate references procedure,

5. Verify E-O Immediate Manual 5.1 Verifies reactor trip:

Actions.

5. 1.1 Annunciator A5-6D lit.

(EOP E-O step 1) 5.1.2 Power Range Indication <5%.

5.1.3 Neutron flux dropping.

COMMENTS:

6. Verify E-O Immediate 6.1 Verifies turbine trip:

Manual Actions.

6.1.1 Throttle or Governor Valves all closed.

(EOP E-O step 2) 6.1.2 Main Generator Output Breakers open.

6.1.3 Exciter Circuit Breaker open.

COMMENTS:

I

RTL#A5.640U l/2-ADM-130 LF04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::::> J StU J

7. Verify E-O Immediate Manual 7.1 Verifies power to AC emergency busses:

Actions.

7.l.1 At least one AC Emergency Bus energized.

(EOP E-O step 3)

COMMENTS:

I

8. Verify E-O Immediate Manual 8.1 Checks SI status:

Actions.

8.1.1 SI actuated.

(EOP E-O step 4) 8.2 Checks if SI is required:

8.2.1 CNMT pressure >5 PSIG.

8.2.2 PRZR pressure <1860 PSIG 8.2.3 SG Steam pressure <500 PSIG.

8.3 Determines SI is NOT REQUIRED and returns to AOP 2.6.8 step 1.a.3, the step in effect.

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NillvfBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 I STEP I STANDARD

. ("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSA =>

9.1 C Stop affected RCP 9.1C Places [2RCS*P21A] control switch in STOP or PTL.

[2RCS*P21Al 9.2 Verifies green light - LIT and red light - NOT LIT.

I RECORD RCP STOP TIME:

9.3 Close PRZR spray valves for 9.3C Places [2RCS*PCV455A] in MANUAL and affected RCP(s) depresses pushbutton until 0% demand indicated.

COMMENTS:

10.C When 3 minutes has elapsed 1O.1C Waits 3 minutes from the time [2RCS*P21A] was from pump shutdown , Close stopped.

affected RCP(s) sealleakoff isolation valve within the IO.2C Places [2CHS*MOV303A] to CLOSE within the next following 2 minutes: 2 minutes

[2CHS*MOV303A],2IA 10.3 Verifies Green Light - LIT and Red Light - NOT RCP Seal Water Leakoff LIT.

VIvo I RECORD MOV CLOSE TIME: _ __

(AOP 2.6.8 step l.b)

EVALUATOR CUE: Terminate JPM after candidate completes closure of

[2CHS*MOV303A].

COMMENTS:

STOPTIME: ______________

RTL#A5.640U 112-ADM-1301.F04 Page 3 of 11 Revision 1

]PM NUMBER: 2CR-520

]PM TITLE: Transfer from Bypass to Main Feed Regulating Valve

]PM REVISION: 0 KIA

REFERENCE:

035A3.014.0/3.9 TASK ID: 0241-004-01-013 035A4.01 3.7/3.6

]PM APPLICATION: cgJ REQUALIFICATION I2J INITIAL EXAM D TRAINING cgJ F AULTED ]PM [J ADMINISTRATIVE ]PM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site [J Annual Requal Exam D BVT D Simulate D Simulator [J Initial Exam D NRC D Classroom [J OJT/TPE D Other:

[J Training

[J Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 10 Minutes Actual minutes Critical: cgJ No Time: Time:

]PM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: NamelSSN:

EVALUATOR Evaluator (Print): Date:

I Evaluator Signature:

I

RTL#A5.640U 1I2*ADM*130LF04 Page 4 of 11 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Transfer control of 21 A SG Water Level Control from the Main Feed Regulating Bypass Valve (MFRBV) in AUTO to the Main Feed Regulating Valve (MFRV) in AUTO.

Recognize improper MFRV control in AUTO and either shifts back to Manual MFRV control OR MFRBV control of 21 A NR S/G Water Level to maintain level between 39% to 49%.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to place 2FWS-FCV478, "21A SG Main Feed Regulating Valve in service.

INITIAL CONDITIONS:

The plant is in Mode 1 @ approximately 25% during a plant startup.

20M-S2.4.A, "Raising Power from 5% to Full Load Operation" is in effect.

Step F.2 directs SG Main Feed Regulating Valves placed in service in accordance with Attachment 5 (provided).

INITIATING CUE: The Unit Supervisor directs you to perform Part A of Attachment 5 of ZOM-52.4.A, "Placing [2FWS-FCV478], 21A SG Main Feedwater Regulating Valve in Service". [2FWS-FCV478] is to be placed in automatic to control Stearn Generator level.

REFERENCES:

20M-52.4.A, "Increasing Power From 5% to Full Load Operation" Rev. 69, Attachment 5 TOOLS: None HANDOUT: ZOM-5Z.4.A, "Increasing Power From 5% to Full Load Operation" Rev. 69, Attachment 5

RTL#A5.640U 1/2*ADM*1301.F04 Page 5 of 11 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

o Read:

TASK:

You are to place 2FWS-FCV478, "21A SG Main Feed Regulating Valve in service.

INITIAL CONDITIONS:

The plant is in Mode 1 @ approximately 25% during a plant startup.

20M-S2.4.A, "Raising Power from 5% to Full Load Operation" is in effect.

Step F.2 directs SG Main Feed Regulating Valves placed in service in accordance with Attachment 5 (provided).

INITIATING CUE: The Unit Supervisor directs you to perform Part A of Attachment 5 of 20M-52.4.A, "Placing [2FWS-FCV478], 21A SG Main Feedwater Regulating Valve in Service". [2FWS-FCV478] is to be placed in automatic to control Steam Generator level.

o At this time, ask the evaluator any questions you have on this JPM.

o When satisfied that you understand the assigned task, announce "I am now beginning the JPMII

o Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

o Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 LF04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: 2CR-S20 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSA Simulator Setup: Initialize to any 25% power IC with Bypass Feed Regulating Valves in automatic.

Place A,B,C NR levels on analog trend on plant computer. (L0400A, L0420A, L0440A).

To insert the fault which causes a controller failure on "A" MFRV when placed in AUTO insert the following:

Controller Tab -CNH-CFWIOB, Select Event Trigger #, Enter 50% severity, Enter 30 second ramp time.Clo084A = 1, click accept new event and ensure it is properly entered.

Freeze simulator and take a snap.

EVALUATOR CUE:

Provide candidate with a copy of20M-S2.4.A, Attachment 5 (Part A), "Placing 2FWS-FCV478, 2IA SG Main F eedwater Reg Vlv in Service". When candidate is ready to begin JPM, PLACE the simulator in RUN.

STARTTIME: ______________

\1. Review procedure. 1.1 Reviews procedure provided.

COMMENTS:

2. Verify 2IA SG level is being 2.1 Verifies 21 A SG is being controlled in AUTO using controlled in AUTO or Main Feed Bypass Control Valve and SG NR Water MANUAL using 21 A SG Level is STABLE at approximately 44%.

Feedwater Bypass Control Vlv AND is STABLE at COMMENTS:

approximately 44%.

RTL#A5.640U 1I2-ADM-1301.F04 Page 7 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-S20 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 I ~~:. Denotes CRITICAL STEP)

STANDARD (Indicate"S" FOR SAT or "U" FOR UNSAT)::::> I Stu 3 Verify [2FWS-FCV478] "21A 3.1 Verifies [2FWS*FCV478] AutolManual station in SG Main Feedwater Regulating MANUAL and 0% demand.

Valve in MANUAL and CLOSED. 3.2 Verifies Green light - LIT and Red light - NOT LIT.

COMMENTS:

4. Verify CLOSED [2FWS 4.1 Verifies [2FWS-MOV154A] is CLOSED.

MOV154A] "21A SG Main Feed water Isolation Valve", 4.2 Verifies Green light - LIT and Red light - NOT LIT.

(BB 'C').

4.3 Dispatches an operator to "A" MFRV to observe local valve stroke.

EVALUATOR CUE: Role Play NLO who is dispatcht!d to report local valve operation.

COMMENTS:

RTL#A5.640U 1!2-ADM-1301.F04 Page 8 of 11 Revision 1 OPERATIONS JOB PERFORMANCE :MEASURE JPM NUMBER: 2CR-520 JPM TITLE: Transfer fI-om Bypass to Main Feed Regulating Valve JPM REVISION: 0 I ~~~:. Denotes CRITICAL STEP) I STANDARD (Indicate .. s.. FOR SAT or "U" FOR UNSAT)=> sru

5. Stroke [2FWS-FCV478] "21A 5.1 Stokes (2FWS*FCV478] full OPEN by depressing SG Main Feedwater Reg Vlv." to

output pushbutton.

full OPEN and then full CLOSED, while verifying local 5.2 Verifie8 Red light - LIT and Green light - NOT LIT.

position indication.

5.3 Strokes [2FWS*FCV478] full CLOSED by depressing .. output pushbutton.

5.4 Verifies Green light - LIT and Red light - NOT LIT.

EXAMINER CUE: Report as the Field Operator that [2FWS-FCV478] traveled smoothly full open with no h(~sitation and now indicates full closed.

COMMENTS:

I 6.1 Trend L0400A (L0401A), 6.1 Trend L0400A (L0401A), (L0402A) - SG 21A NR (L0402A) - SG 21A NR LVL LVL FWS*LT474 (475), (476) on the Plant Computer FWS*LT474 (475), (476) on the (PCS) using lowest scan rate.

Plant Computer (PCS) using lowest scan rate.

6.2 Monitor Steam Generator level, 6.2 Monitors recorders and indicators for 21 A SG level, steam flow and feed flow. feed flow AND steam flow.

COMMENTS:

I

RTL#A5.640U 1I2-ADM-1301.F04 Page 9 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-520 II JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 i STEP I STANDARD I ("e" Denotes CRITICAL STEP) ~dicate "s" FOR SAT or "U" FOR UNSAT)=> Stu I

7. Maintain stable temperature 7.1 Verifies stable Tavg and reactor power by monitoring AND reactor power. NI power and Loop DT and Tavg.

EVALUATOR CUE: Tavg and reactor power are stable. Another operator will continue to monitor these parameters.

COMMENTS:

8.C Open [2FWS-MOVl54A], 8.lC Places [2FWS-MOVl54A] control switch to OPEN "21A SG Main Feedwater Isol position.

VIv.".

8.2 Verifies Red light - LIT and Green light - NOT LIT.

COMMENTS:

9. If feed flow to the 21A SG 9.1 Continuously monitors steam flow and feed flow rapidly rises or lowers when recorders andlor indicators for rapidly changing performing the following steps, feedwater flow.

THEN manually CLOSE the 21A SG Main Feedwater Reg COMMENTS:

Vlv AND establish proper feed flow AND level with 21 A SG Feedwater Bypass Valve.

RTL#A5.640U 1I2-ADM-1301.F04 Page 10 of II Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 STEP STANDARD

("C" Denotes cruTICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U IIO.C Verify [2FWS-FCV478] "2IA 1O.IC Verifies [2FWS*FCV478] is in MANUAL and

. SG Main Feedwater Reg VIv." slowly opens using .A output pushbutton.

controller in MANUAL and SLOWLY OPEN. COMMENTS:

11. Continue to open [2FWS 11.1 Continues to open [2FWS*FCV478].

FCV478] "21A SG Main Feed Reg Valve" until [2FWS 11.2 Verifies [2FWS*FCV479] is closing in AUTO OR is FCV479] "21A SG Feedwater being closed in MANUAL to maintain 21A SG Water Bypass Control Valve" is Level between 39% and 49%.

CLOSED.

COMMENTS:

12. When [2FWS-FCV479], 21A 12.1 Verifies [2FWS*FCV479] full CLOSED.

SG Feedwater Bypass Control Valve is CLOSED, verify 12.2 Verifies [2FWS*FCV479] controller in MANUAL.

[2FWS-FCV479]controller in MANUAL and check for 12.3 Verifies no leakage past valve.

leakage past valve.

COMMENTS:

RTL#A5.640U 1I2*ADM*1301.F04 Page' 11 ofl!

Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM N1JMBER: 2CR-S20 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 I STEP I STANDARD

~ "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSA FAULT STATEMENT: Alternate Path begins here when placing "A" MFRV into AUTO.

13.C Place controller for [2FWS 13.lC Places [2FWS*FCV478] controller to AUTO.

FCV478] Main Feed Reg Valve in AUTO and monitor l3.2C Recognizes 21A NR SG level control is NOT stable.

SG level AND feed flow and steam flow. 13.3C Places [2FWS*FCV478] controller back to MANUAL.

13.4C Maintains 21 A SG NR water level between 39% and 49% using either [2FWS*FCV478] in MANUAL or

[2FWS*FCV479] in MANUAL or AUTO.

13.5 Reports problem with [2FWS*FCV478] AUTO control to US.

COMMENTS:

EVALUATOR CUE: Once it is demonstrated that the candidate can control 21 A SG NR water level between 39% and 49%: "This JPM is COiVWLETE".

STOPTIME: ______________

RTL#A5.640U 112-ADM-130 LF04 Page 3 of 11 Revision 1 JPM NUMBER: 2CR-S24 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 KIA

REFERENCE:

064A4.06 3.9/3.9 TASK ID: 0362-005-06-013 JPM APPLICATION: I:8J REQUALIFICATION I:8J INITIAL EXAM o TRAINING I:8J F AULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

0 Perform 0 0 BVT 0 Simulate 0 0

Plant Site Simulator Classroom B0 Annual Requal Exam Initial Exam OJT/TPE 0 NRC 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 15 Minutes Actual minutes Critical: I:8J No Time: Time:

JPM RESULTS:

D SAT D UN SAT (Comments required for UNBAT evaluation)

Comments: -

OBSERVERS Name/SSN: !NameiSSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (print): Date:

i Evaluator Signature:

I

RTL#A5.640U 1I2-ADM-130l.F04 Page 4 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Diesel Generator 2-1 is synchronized and loaded in accordance with 20ST-36.1, "Emergency Diesel Generator [2EDG*2-1] Monthly Test" AND then tripped in response to Annunciator A8-4C and associated computer alarm indicating DG 2-1 DIFF.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to synchronize and load Emergency Diesel Generator 2-1.

INITIAL CONDITIONS: The plant is in Mode 1 with 20ST-36.1 being performed. The test has been completed up to step VII, Part B, step 21. All steps up to this point have been compk1ed satisfactorily.

INITIA TING CUE: Your supervisor directs you to perform Section VII, Part B, steps 21 through 35 of 20ST-36.1. You are responsible to respond to all alarms on Annunciator panel A8.

REFERENCES:

20ST-36.1, "Emergency Diesel Generator [2EGS*EG2-1] Monthly Test", Rev 62.

20M-36.4.ACS, "Diesel Gen 2-1 Electrical Fault", Issue 1, Rev. 9 TOOLS: None HANDOUT: 20ST-36.1, "Emergency Diesel Generator [2EGS *EG2-1] Monthly Test", Rev 62, place kept up to step 21.

20M-36.4.ACS, "Diesel Gen 2-1 Electrical Fault", Issue 1, Rev. 9 (AFTER ALARM OCCURS)

RTL#A5.640U 112-ADM-1301.F04 Page 5 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to synchronize and load Emergency Diesel Generator 2-1.

INITIAL CONDITIONS: The plant is in Mode 1 with 20ST-36.1 being performed. The test has been completed up to step VII, Part B, step 21. All steps up to this point have been completed satisfactorily.

INITIATING CUE: Your supervisor directs you to perform Section VII, Part B, steps 21 through 35 of20ST-36.1. You are responsible to respond to all alarms on Annunciator panel A8.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

R1L#A5.640U 1I2-ADM-130l.F04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-524 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 STEP I STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAn=>

Simulator Setup: Initialize an IC.,

Ensure simulator is setup for OST-36.1 conditions up to step 21 as follows:

DG in EXERCISE & running @ 514 RPM

DG voltage at ~ 122 volts Turn on Annuc All-4B, YOI86D, C02 in Lockout.

Set Trigger 1 to actuate when DG Load reaches 600 KW and actuates Annunciator A8-4C, Y2955D to support Alternate Path JPM as follows:

Seh~ct Even Triggers

Enter HWXC80 14M = 600 into event tab

Enter imf AS-4C-Y2955D 0 into command tab ENSURE "B" PROTECTED TRAIN POSTED START TIME: - - - - - - - -

1. Check EDG speed at ~514 1.1 Verifies EDG 2-1 Diesel Generator Speed at ",,514 RPM. RPMonBB-C.

I COMMENTS:

EVALUATOR CUE: Digital voltmeter readings are not required.

2. Obtain EDG voltage and 2.1 Records 2-1 EDG Output Voltage using benchboard frequency readings. indication in Step 22a.

2.2 Records 2-1 EDG Output Frequency using benchboard indication in Step 22a.

COMMENTS

RTL#A5.640U 112-ADM-130LF04 Page 7 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-524 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 I STEP

("C" Denotes croTICAL STEP)

ISTANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)::::> I SIU i EVALUATOR CUE: Motor Operated Potentiometer Test Not Required.

3.C Places 2-1 EMERG GEN 3.1C Places 2-1 EMERG GEN MOTOR OPERATED MTR OPERATED GROUND GROlJND DISCONNECT control switch to CLOSE.

DISCONNECT switch in the CLOSE position and verifies 3.2 Releases switch when Green light - NOT LIT and correct indication. Red light - LIT.

3.3 Acknowledges Annunciator A8-4B, "DIESEL GEN 2-1 M.O. GROUND SWNOT FULLY OPEN'.

COMMENTS:

4.C Position the 2-1 EMERG 4.1 C Places the 2-1 EMERG GEN SYNCHRONIZING GEN SYNCHRONIZING SELECTOR switch to the BUS 2AE position.

SELECTOR switch to the BUS 2AE position. COMMENTS:

5.C Adjust EDG speed using 2-1 5.1 C Raise or lowers 2-1 EMERG GEN GOVERNOR EMERG GEN GOVERNOR control switch to adjust EDG 2-1 speed until the switch until EDG 2-1 EDG 2-1 synchroscope is rotating slowly in the fast Synchroscope needle is direction.

rotating slowly in the FAST direction. COMMENTS:

I I

RTL#A5.640U 1I2-ADM-1301.F04 Page 8 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-524 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 I STEP

("e" Denotes CRITICAL STEP)

ISTANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I Stu I

6. Record voltage reading from 6.1 Records voltage from 2-1 EMERG GEN Voltmeter 2-1 EMERG GEN Voltmeter. on BB-C in Step 27a.

(BB-C)

COMMENTS *

7. Record voltage reading from 7.1 Records voltage from 4160V BUS 2AE Voltmeter 4160V BUS 2AE on BB-C in Step 27b.

Voltmeter. (VB-C)

COMMENTS:

8. If aligned to the SSST, Place 8.1 Determines NOT aligned to SSST and N/As Bus 2A Load Tap Changer in procedure step.

MANUAL.

COMMENTS:

9. Using the 2-1 EMERG GEN 9.1. Compares/verifies voltage between the EDG 2-1 VOLTAGE ADJUST switch, and the Bus 2AE within 1 volt or adjusts EDG 2-1 match EDG voltage with the voltage to within that tolerance using the 2-1 voltage on Bus 2AE within 1 EMERG GEN VOLTAGE ADJUST switch.

VAC.

COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 9 of 11 Revision 1 OPERATIONS JOB PERFORMANCE :MEASURE JPM NUMBER: 2CR-524 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 I STEP

. ("C" Denotes CRITICAL STEP)

I STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> Stu I 10.C While observing both EDG 10.lC Places 2-1 EMERG GEN OUTPlJT BKR ACB 2-1 synchroscope and 2E 10 control switch to CLOSE position when synchronizing lights perform synchronizing needle is at 12 o'clock and lamps the following: are dark.

When synchronizing lamps 10.2 Verifies 2E 10 Red Light - LIT and White Light are completely dark and NOT LIT and releases switch.

synchroscope needle is at 12 o'clock position, place the 2- COMMENTS.

i 1 EDG Output Breaker ACB 2E 10 control switch in the CLOSE position and when the red light above switch turns ON, release the switch. i 1l.C Increase load on EDG 2-1 to 11.1C Increases load on EDG 2-1 by turning 2-1 approximately 450 KW using EMERG GEN GOVERNOR Control switch EMERG GEN GOVERNOR intermittently to RAISE.

control switch.

. 11.2 Observes increasing EDG 2-1 watts and amps .

2-1 Emergency Generator Watts 2-1 Emer Gen 4KV Bus 2AE AMPS COMMENTS:

12. Place the 2-1 EMERG GEN 12.1 Places 2-1 EMERG GEN SYNCHRONIZING SYCHRONIZING SELECTOR switch in the OFF position.

SELECTOR switch in the OFF position. COMMENTS:

i i I i

RTL#A5.640U 1I2-ADM-130 l.F04 Page 10 ofll Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-524 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 Indicate "s" FOR SAT or "U" FOR UNSAT)~

13. Adjust 2-1 EMERG GEN 13.1 Adjusts 2-1 EMERG GEN POWER FACTOR POWER FACTOR using the using the 2-1 EMERG GEN VOLTAGE ADJUST 2-1 EMERG GEN switch to between 0.90 - 1.0 LAGGING.

VOLTAGE ADJUST switch to between 0.90 - 1.0 13.2 Verifies power factor on Power Factor meter (VB LAGGING. C)

EVALUATOR CUE: Post Maintenance testing of the EDG governor is NOT required.

COMMENTS:

14.C IncreaseEDGloadto~4050 14.1C Using 2-1 EMERG GEN GOVERNOR Switch KW over 15-20 minutes and intermittently in the RAISE position, pick up load maintain power factor 0.9-1.0 on 2-1 EDG.

LAGGING.

14.2 Begins raising EDG load to 4050 KW.

14.3C Using 2-1 EMERG GEN VOLTAGE ADJUST control switch, maintain power factor 0.9-1.0 LAGGING.

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 11 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-S24 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 STEP I STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=>

FAULT STATEMENT: At this point the JPM alternate path begins. Annunciator A8-4C, "DIESEL GEN 2-1 ELECTRICAL F AULT" will annunciate when EDG 2-1 loading reaches 600 KW. Computer alarm DG 2-1 DIFF will also be received. Candidate should respond to ARP and Trip the 2-1 EDG and open ACB 2EI0 which failed to automatically occur.

15.C Annunciator A8-4C, 15. 1 Acknowledges the alarm and responds by "DIESEL GEN 2-1 reviewing the ARP for A8-4C.

ELECTRICAL FAULT",

alarms due to 2-1 DG DIFF, 15.2 Determines the alarm is indicative of an EDG Trip.

(Y2955D) 15.3C Manually Trips EDG 2-1 and opens ACB 2EIO output breaker.

EVALUATOR CUE: Terminate the JPM after the candidate trips the EDG and opens the output breaker.

COMMENTS:

STOP TIME: ----------------

A~ppen d"IX 0 . 0 u tl*me S cenarlo Form ES 0 1 -

Facility: FENOC BVPS Unit 2 Scenario No.: 1 OpTestNo.: 2LOT7NRC Examiners: Candidates: SRO ATC BOP Initial IC 216: 61% power, MOL, Equ. Xe Conditions, CB "D" @ 152 steps, RCS boron -1044 Conditions: ppm, Condensate Polishing Air Compressor - OOS.

Turnover: Maintain current power level.

Critical Tasks: E-O.A, Auto Rx Trip failure E-O.H, Start LHSI Pumps E-O.E, Manually Initiate CIB ES-1.3.A, Transfer to Cold Leg Recirc Event Malf. No. Event Type Event Description No.

1 XMT-RCS054A I(ATC/SRO) Loop 1 Tcold RTD fails low SROTS 2 PMP-CFW004 C(BOP/SRO) 2FWS*P21A pump trip.(Power reduction required) 3 R(ATC) Power reduction to <50%

N(SRO/BOP) 4 FLX-CCP34. C(ALL) CCP supply leak to 2RCS*P21B (10 minute ramp to 450 gpm PMP-RCPOO3 SROTS leads to an automatic RCP tr!p).

5 PPLOIA C(ATC) Auto Reactor Trip failure (manual available)

PPLOIB (SRO) 6 RCS03B M(ALL) B Loop Large break LOCA 7 PPL07A C(ATC) Both low head SI pumps fail to auto start (manual start PPL07B _(SROJ availabltU*

8 PPL09A C(BOP) Auto CIB failure (manual available)

PPL09B (SRO) 9 SIS01 5000 gpm RWST leak PCS084 PCS085 C(ALL) Auto Transfer to Cold Leg Recire failure (requires manually PCS087 aligning components)

(N)ormal, (R)eaetivity. (I)nstrument. (C)omponent. (M),uor NUREG-1 021. Revision 9 Supplement 1 FENoe FaCSimile Rev AG

Appendix 0 Scenario Outline Form ES-O-1 The crew will take the shift at 61 % power, MOL at Equilibrium Xe, Bank D control Rods at 152 steps and RCS oron is at 1044 ppm. Crew instructions are to maintain current stable plant conditions.

Loop 1 Tcold RTD will fail low, requiring implementation of20M-6.4.IF, attachment 4. The ATC will have to accurately determine failed channel and select a non-failed channel and the SRO will evaluate TS.

2FWS-P21A will then trip requiring the crew to enter AOP 2.24.1 and rapidly reduce power to less than 50%.

When plant conditions have begun to stabilize, a leak dev(~lops on the CCP supply line to 2RCS-P2IB, "B" RCP. The leak will ramp to 450 gpm over ten minutes. First indication is annunciator A2-2B for UIL HIGH, ARP 20M-9.4.AAL will be entered at which point dropping CCP surge tank level indication will require entry into AOP 2.15.1. The US will evaluate TS 3.7.7 applicability. The "B" RCP will degrade and eventually trip with a failure of the reactor to trip automatically. The Unit Supervisor should direct a manual reactor trip and enter E-O.

Immediately following the reactor trip, a large break LOCA and a 5000 gpm RWST leak occurs. After completing E-O immediate actions, all RCPs should be manually tripped due to the loss of component cooling.

Additional failures that occur following the LOCA, the ATC operator will identify that both low head SI pumps failed to start automatically and will manually start them. During the performance ofEOP attachment A-O.II, the BOP will identify that Containment Isolation Phase "B" (CIB) failed to actuate automatically and will manually initiate CIB. The Unit Supervisor will progress through E-O to E-l at the "Check ifthe RCS is Intact" "tep, E-l will be implemented until the RWST level reduces to <400 inches at which point the crew will

.;;cognize the need to establish Cold Leg Recirculation flow lAW ES-l.3, automatic initiation of Transfer to Recirc is inhibited, requiring the crew to manually align components.

The drill is terminated after the crew has established Cold leg recirculation flow and verified flow in at least one flow path lAW step 3.d ofES-1.3.

Expected procedure flow path is E-O ---t E-l---t ES-l.3.

NUREG-1021 , Revision 9 Supplement 1 FENoe Facsimile Rev AG

BEAVER VALLEY PuvVER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 61 % Power, CBD = 152, EQU XE MOL, 1044 PPM Boron, IC-216 ADDITIONAL LINEUP CHANGES STICKERS YOND MARKINGS 2SAS*C22 in PTL YCTon CS None EQUIPMENT STATUS DATEfflME OOS TECHNICAL SPECIFICATION(S) 2SAS-C22 OOS 2 days ago None

- .. -~ ....---

SHIFT TURNOVER INFORMATION

1. 61 % Power, CBD = 152, EQU XE MOL, 1044 PPM Boron, ROD's in AUTO

2. Protected Train is Train "B"

3. Maintain steady state power level for confidence run on 2FWS-P21 B which was just returned to service at the end of last shift from a pump bearing replacement outage.

4. 2SAS-C22, Condensate Polishing Air Compressor OOS tor overhaul.

5. 20M-52.4.B is on Shift Managers desk.

SCENARIO SUPPORT MATERIAL REQUIRED

1. Reactivity plan placard for MOL

2. Placard for 2FWE*P22 position stating 2FWE*P22 is aligned to "A" header

3. Place plaque on wall for Protected Train "B" BVPS - 2 Scenario 1, Rev AG 1 of 22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Initialize IC Set 216, and establish Reactor plant at 61 % power, MOL, equilibrium initial plant conditions. conditions. RCS boron 1044 PPM, CBD = 152 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the drill Setup section of the HTML File for this drill:

TRGSET 1 'JPPLP4(1)' Set trigger 1 on Reactor trip IMF PPLOIA (0 0) 0 TRN "A" Auto Reactor trip failure IMF PPLOIB (0 0) 0 TRN "B" Auto Reactor trip failure

. IMF PPL07A (0 0) 4 2SIS*P21A auto start failure IMF PPL07B (0 0) 4 2SIS*P21B auto start failure IMF PPL09A (0 0) TRUE TRN "A" CIB Auto Actuation failure IMF PPL09B (0 0) TRUE TRN "B" CIB Auto Actuation failure IMF RCS03B (I 0) TRUE BLoop LBLOCA occurs on reactor trip IMF FLX-CCP34 (3 0) 1 450 gpm leak on CCP supply line to "B" RCP lOR XB4000lR (3 0) 1 Fail 2CCP*MOVI03B red light on.

IMF VL V-CCP042A (3 120) 15 420 Reduced CCP flow to 2RCS-P21B IMF PMP-RCP003 (3 720) 1 Trip of"B" RCP in 12 minutes TRG 4 'IMF PMP-RCP003 I' OPTIONAL action to allow booth operator to manually trip the "B" RCP.

TRGSET 5 'JPPLP4(1)' Set trigger 5 on Reactor trip TRG 5 'IMF SISOI 5000' 5000 gpm RWST leak upon Rx trip IMF BST-PCS084 (0 0) 1 Inhibit CH I Transfer to Recirc initiation IMF BST-PCS085 (0 0) 1 Inhibit CH II Transfer to Recirc initiation IMF BST-PCS087 (00) 1 Inhibit CH IV Transfer to Recirc initiation BVPS - 2 Scenario 1, Rev AG 2 of 22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 CJNSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ~

Assign shift positions SRO:

ATC:_ _ _ _ _ _ _ __

BOP:_ _ _ _ _ _ _ _ __

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless it operators. needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 1, Rev AG 30f22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT #1:

Loop 1 T cold fails low 2RCS-TE412D IMF XMT-RCS054A (0 0) 510240 IMMEDIATE PLANT RESPONSE:

A4-4C, - 'LOOP AT DEVIATION' - LIT ATC acknowledges alarms, infonns Crew.

A4-3F, - 'LOOP TAVG DEVIATION' - LIT BOP refers to ARP's.

SRO directs entry into Instrument Failure procedure, 20M-6.4.IF ATT 4.

ATC/SRO diagnoses Loop 1 Tcold as failed low.

ATC selects an unaffected loop on OTDT recorder selector s""itch.

SRO reviews TS TS 3.3.1, functions 6 & 7, Both are Condition E, trip Bistables w/in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

TS 3.3.2, function 8c, Condition K, verifY P-12 in correct position w/in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Contacts I&C to trip OTDT Bistables.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action to verifY P-12 in correct position.

Proceed with next event at LE discretion BVPS - 2 Scenario 1 Rev AG J 4 of 22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 r-U,NSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE *1 EXPECTED STUDENT RESPONSE EVENTS 2 and 3:

2FWS-P2IA Trip IMMEDIATE PLANT RESPONSE:

A6-10A, - 'SG FEED PUMP 2 1AlB AUTO-STOP' BOP recognizes feed pump trip and informs US IMF PMP-CFW004 (0 0) 1 -LIT Refers to ARPs as time permits.

A6-9E, A6-lOE, A6-IIE, - 'S/G 21A, B, C LEVEL As necessary, BOP controls SG level with manual DEVIATION FROM SETPOINT' - LIT control of the Main Feed Regulating valves.

BRIGHT white light for 2FWS-P21A SRO refers to AOP-2.24.1, Loss of Main Feedwater.

ATC verifies reactor power < 80%.

Turbine load reduction to < 50%. SRO refers to AOP-2.24.1 and directs load decrease to < 50% at desired reduction rate.

BOP decreases turbine load at rate designated by SRO.

In AUTO mode, Rods begin to step inward in ATC performs RCS boration to maintain response to Turbine Load Reduction. Tavg-Tref.

A TC maintains rods in Auto SRO places calls to Ops Management & Electrical maintenance.

BOP notifies turbine operator to check Aux oil pump for 2FWS-P21A Proceed with next event at LE discretion BVPS - 2 Scenario 1, Rev AG 50f22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 4:

IMMEDIATE PLANT RESPONSE:

CCP leak on supply line to "B" RCP Decreasing CCP Surge Tank level on with automatic RCP trip. 2CCP*LIlOOA and 2CCP*LIl OOB. Crew determines CCP header leak inside containment.

IMF FLX-CCP34 (3 0) 450 600 PMP-RCS003 SRO may initially enter AOP 2.6.7, 'Primary Plant Increasing containment sump levels. Leakage' due to containment sump alarms.

A2-2B, - 'UNIDENTIFIED LEAKAGE SYSTEM TROUBLE' - LIT SRO refers to AOP-2.15.1, 'Loss of Primary AI-2G, - 'UNIDENTIFIED LEAKAGE FLOW> Component Cooling Water' .

60 GALLONS' - LIT A2-3B, - 'INCORE INSTR ROOMlCNMT SUMP Crew may dispatch an operator to verify CCP LEVEL HIGHlY ALVE NOT RESET' - LIT makeup valve(s) unisolated.

Decreasing 21 B RCP motor CCP flow indication.

Increasing 21B RCP motor and bearing temperatures.

1 CCP pump operating. ATCIBOP checks CCP system status.

NOTE: Level control in manual with maximum makeup. ATCIBOP places surge tank level control valve in Dependant on timing and progression manual and adjusts control signal to maximize through AOP 2.15.1, CCP surge tank makeup to surge tank.

level may initially rise if makeup is quickly established, however as the ATC attempts to identify leak using AOP 2.15.1, leak continues to get larger, level will either Attachments 1 or 2 dependant upon timing.

then drop again.

BVPS - 2 Scenario 1, Rev AG 6 of 22

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE mn~

A2-5F, - 'RCP COOLING WATER TROUBLE' SRO enters AOP 2.6.8.

LIT Crew monitors RCP motor bearing upper and lower temperatures for RCPs.

Non-essential loads isolated. Crew attempts to locate the leak.

NOTE: Surge tank continues to decrease. Crew monitors to determine if any RCP If crew is preparing to pre-emptively temperatures are approaching limits OR operating trip the reactor before the RCP trip Cavitation of CCP pumps possible. CCP pumps discharge pressure and current times out, insert the following indicates cavitation, or if leakage is determined to command to trip the RCP immediately. Leakage excessive. be excessive:

TRG4 'IMF PMP-RCP0031' lAW AOP-2.15.l the crew will Trip the Rx, THEN Go to E-O and perform lMA's, THEN Stop all RCP's Isolate Letdown Transfer CHS suct to RWST Stop ALL CCP pumps NOTE: The "B" RCP condition will continue to degrade Crew recognizes Automatic Reactor trip failure and The Reactor will trip manually. and trip, however an automatic reactor trip will ATC manually trips the reactor using a Benchboard NOT occur. control switch.

A5-3F, - 'REACTOR COOLANT PUMP AUTO STOP' - LIT A5-2G, - '113 REACTOR COOLANT PUMP LOOP FLOW LOW REACTOR TRIP' - LIT BVPS - 2 Scenario 1, Rev AG 70f22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: SRO Applies TS; Due to the sequence of events, the SRO TS 3.7.7, Condition C, Immediately initiate actions may not identify applicable TS. Ask to restore one train of CCW to operable status.

follow-up question, "IfCCP Surge Tank levels dropped to 0%, What, if

. any TS entries would be required?"

EVENTS 5,6,7 & 8 Automatic Reactor Trip failure (preloaded)

TRGSET 1 'JPPLP4(1)' Set trigger 1 on Reactor trip SRO directs the ATC to manually trip the reactor, IMF PPLOIA (0 0) 0 TRN "A" Auto Reactor trip failure perform IMAs and trip all RCPs.

IMF PPLOIB (0 0) 0 TRN "B" Auto Reactor trip failure IMF PPL07A (0 0) 4 2SIS*P21A auto start failure IMF PPL07B (0 0) 4 2SIS*P21B auto start failure IMF RCS03B (1 0) DBA LOCA on reactor trip IMF PPL09A (0 0) TRN "A" Auto eIB failure IMF PPL09B (0 0) TRN "B" Auto CIB failure CRITICAL TASK: ATC manually trips the reactor.

E-O.A - Crew manually trips the reactor from the control room before performing the mitigation strategy of FR-S.l.

Crew enters E-O, performs immediate operator Crew performs IMAs of E-O.

actions BVPS - 2 Scenario 1, Rev AG 80f22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Rod bottom lights lit. Neutron flux dropping.

First Out: A5-2G, - '113 REACTOR COOLANT PUMP LOOP FLOW LOW REACTOR TRIP' LIT Steps 1 - 4 ofE-O are Immediate A5-6D, - 'TURBINE TRIP DUE TO REACTOR ATC verifies reactor trip.

Actions. TRIP' - LIT Power range indication - LESS THAN 5%

Neutron flux - DROPPING Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency Buses.

ENERGIZED Check SI - ACTUATED A TC checks SI status.

CNMT Pressure - > 5PSIG PZR Pressure - < 1860 PSIG SG Steam Pressure - < 500 PSIG CREW DETERMINES SI REQUIRED Crew continues E-O Manually actuate SI (both trains) ATC manually actuates SI both trains.

E-O Immediate Actions completed.

Manual reactor trip resulted in a DBA LOCA on SRO directs manual trip of all Reps.

RCS Loop B.

ATC trips all RCPs.

BVPS - 2 Scenario 1, Rev AG 90f22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONA[GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Alert Plant Personnel ATCIBOP sound Standby Alarm, announce reactor trip and safety injection.

Leak collection filtered exhaust fan status SAT. Crew verifies leak collection filtered exhaust fan 2HVS-FN204A or B running.

CRITICAL TASK: ATC verifies SI System status.

E-O.H - Crew manually starts at least Charging Pumps - TWO RUNNING 2CHS*P21A & 2CHS*P2IB running.

one low head ECCS pump before HHSI Flow - INDICATED HHSI Flow indicated on 2SIS-FI943.

transition out of E-O. LHSI Pumps - NONE RUNNING ATC manually starts 2SIS*P21A & 2SIS*P21B.

Motor-driven AFW Pumps - BOTH RUNNING BOP verifies AFW System status.

Turb Driven AFW Pump Stm Supply Isol Valves OPEN AFW Throttle Vlvs - FULL OPEN Total AFW Flow - GREATER THAN 340 GPM SRO directs an operator verify automatic actions by performing Attachment A-O.II when time permits.

Attachment A-O.ll included with List of Attachment A-O.ll Discrepancies:

scenario beginning on Pg 20. Operator assigned to perform Attachment A-O.II Both LHSI pumps failed to auto start and were reports status of attachment to the SRO and any manually started. actions taken when completed.

CIB failed to auto actuate and was manually actuated.

BVPS - 2 Scenario 1, Rev AG 10 of 22

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7

[ -INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE RCPs OPERATING - MONITOR Tavg ATCIBOP checks RCS Tcold stable at or trending RCPs STOPPED - MONITOR Teold to 547°F.

Plant rapidly cooled down due to DBA LOCA ATC reports RCS cold leg temperature and cool down caused by LOCA.

CheckCm ACTUATED ATC checks Recirc Spray Pump status.

Recirc Spray HXs - SERVICE WATER FLOW ATC verifies 2SWS*MOV103A(B) OPEN and TO ALL 4 HXs 2SWS*MOV106A(B) CLOSED.

Check Recire Spray Pumps - ANY RUNNING ATC checks no Recirc Spray pumps are running.

Cheek Recirc Spray Pumps - ALL RUNNING Check Recirc Spray Pumps - NOT CAVITATING If cm was not previously actuated, the Crew will recognize CIB is required and manually actuate cm - Both Trains.

PORVs - CLOSED(not leaking). ATC verifies PZR isolated.

Spray Valves - CLOSED Safety relief valves (PSMS Detailed Data Page 1)

-CLOSED Check PRT conditions CONSISTENT WITH EXPECTED VALVES Power to at least one block valve - AVAILABLE Block valves - AT LEAST ONE OPEN BVPS - 2 Scenario 1, Rev AG 11 of 22

BEAVER VALLEy POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 CINSTRDciR5NAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE 1 DIP between RCS pressure and highest SG pressure ATC checks if RCPs should be stopped.

LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

AND HHSI Flow- INDICATED Stop All RCPs If not previously stopped, ATC stops RCPs.

Pressures in all SGs - ANY DROPPING IN AN BOP determines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED Check all SG levels - NONE RISING IN AN Crew determines all SO tubes are intact.

UNCONTROLLED MANNER Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQI00] Air Ejector Discharge (1007)

[2SSR-RQI00] SG Blowdown Sample (1062)

[2MSS*RQI01A,B,C] Main Steamline Discharge (1005,3005,5005)

BVPS - 2 Scenario 1, Rev AG 12 of 22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL-=G-:-:U=ID=E:-:-L':":""IN=E=S--.-----=Pc:-LA-:-:N-=T=-S=T=A=T=-Uc-:-S--:O=R:---R""""'E""""'S=P-O-N-S-E-----,----=E:-:c-:X=P=EC=T=E=O=-S=T=-U=D-=Ec-:-=-R=ES-::-:P=-O=N-:-:S=E----,

NT Check the following consistent with pre-event Crew checks ifRCS is intact.

values:

CNMT Pressure CREW DETERMINES THAT RCS IS NOT CNMT Sump Level INTACT, TRANSITIONS TO E-l STEP 1.

CNMT Radiation Transition to E-l, US directs transition to E-l.

NOTE:

After transition to E-l, crew may enter FR-P.l due to the excessive cooldown, however FR-P.l will be exited as soon as adequate LHSI flow is verified.

Crew checks if CREVS should be actuated If Auto Actuation ofCREVs did not occur, BOP actuates both trains of CREVS using the Control Room radiation monitor [2RMC*RQ201, CONTROL ROOM EMERG AIR SUP 202J (1069, 1072) - NOT IN HIGH ALARM ACTUATION pushbuttons.

CIB - HAS OCCURRED DIP between RCS pressure and highest SG pressure ATC checks if RCPs should be stopped.

- LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

AND HHSI Flow INDICATED RCPs - STOPPED If not previously stopped, ATC stops RCPs.

BVPS - 2 Scenario 1. Rev AG 13 of 22

BEAVER VALLEy POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE CIB - ACTUATED ATC checks Recife Spray Pump status.

Recirc Spray Hxs - SERVICE WATER FLOW TO ATC verifies 2SWS*MOV103A(B) OPEN and ALL 4 HXS 2SWS*MOVI06A(B) CLOSED.

R WST Level- S 381 inches ATC checks RWST level> 381 inches.

Verify Recirc Spray Pumps - NOT CAVITATING Pressures in all SGs - ANY DROPPING IN AN BOP determines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED SGs are NOT faulted Narrow Range Levels - GREATER THAN 12% BOP checks intact SG levels.

[31 % ADVERSE CNMT]

BOP controls feed flow to intact SGs to maintain NR level between 12% [31 % ADVERSE CNMT]

and 50%.

BVPS - 2 Scenario 1, Rev AG 14 of 22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[-INSTRUCTiONAl.. GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check all SG levels - NONE RISING IN AN Crew detennines SG tubes are intact.

UNCONTROLLED MANNER Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQI00] (1007) Air ejector discharge

[2SSR-RQIOO] (1062) SGBD sample

[2MSS*RQI01A,B,C] Main Steamline discharge 005,3005,5005)

Power to the Block Vlvs - AVAILABLE ATC checks PRZR PORVs and Block Valves:

PORVs - CLOSED All PORVS CLOSED.

Block Vlvs - AT LEAST ONE OPEN All Block valves open and energized.

RCS Subcooling based on core exit TCs > 41F ATCIBOP check ifSI flow can be reduced.

[59F ADVbRSE CNMT]

Secondary heat sink: Crew detennines RCS subcooling is < required Total feed flow to intact SGs - GREATER THAN from Attachment A-5.1.

340GPM OR SI FLOW CANNOT BE REDUCED Narrow range level in at least one intact SG GREATER THAN 12% [31-% ADVERSE CNMT]

RCS pressure STABLE OR RISING PRZR level- GREATER THAN 17% [38% SI TERMINATION CONDITIONS ARE NOT ADVERSE CNMT] SATISIFIED, SRO CONTINUES IN E-l.

BVPS - 2 Scenario 1, Rev AG 15 of 22

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7

[ INSTRLJCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Any Quench spray or recire spray pump A TCIBOP check if CNMT Spray should be RUNNING stopped.

SRO continues with STEP 10.

SI & CIA - RESET ATC resets SI and CIA.

RCS Pressure - > 225 PSIG [250 PSIG ADVERSE ATC checks ifLHSI pumps should be stopped.

CNMT]

RCS Pressure - STABLE OR RISING ATC determines RCS pressure is NOT stable or rising.

LHSI Pumps stopped and in auto ATC determines RCS pressure < 225 psig, LHSI pumps to remain running.

ATCIBOP checks RCS and SG Pressures.

Check pressures in all SGs - STABLE OR RISING BOP determines SG pressures are stable or rising.

Check RCS Pressure - STABLE OR DROPPING ATC determines RCS pressure is dropping.

Verify AC emergency busses energized from BOP checks ifEDGs should be stopped.

offsite Stop any unloaded EDG by performing 20M* Crew initiates actions to STOP EDGs.

36.4.AF(AG)

Verify Cold Leg Recirculation Capability US directs operators to perform Art A-O.6 and verify cold leg recirculation capability.

ATCIBOP verifies all components in Attachment A-O.6 are available and dispatches an operator to energize valves per Step 4 of Attachment.

BVPS - 2 Scenario 1, Rev AG 16 of 22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 r- INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check Aux building and Safeguards radiation Crew recognizes that Rad Mon indications are CONSISTENT WITH PRE-EVENT consistent and leak is NOT outside containment.

ROLEPLAY: SM consults with TSC Staff to determine whether TSC is not yet activated, crew is to continue with If SRO requests TSC status - Report samples can be obtained next step.

TSC not yet activated.

Crew performs ATT A-I.I SRO directs crew to perform additional actions as required to aid in plant recovery per ATT A-I.I.

RCS Pressure - > 225 PSIG [250 PSIG ADVERSE ATC checks if cooldown and depressurization is CNMT] required:

Determines RCS pressure is < 225 psig and LHSI flow is > 1050 GPM.

Crew determines transition to ES-l.2 is not appropriate at this time.

NOTE: Check if Transfer to Cold Leg Recirculation is Depending on procedure pace, RWST Required. - Check RWST level < 400 inches.

level may not be at <400 inches, procedure will require looping back while waiting for level to decrease to RWST level < 400 inches Crew identifies need for Transfer to Cold Leg Transfer to Recire point. Recirc and transitions to ES-l.3.

ES-l.3 actions, Reset SI Previously completed.

Verify Service water flow to Recirc spray heat Previously completed.

exchangers.

BVPS - 2 Scenario 1, Rev AG 17 of 22

BEAVER VALLEy POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: Yerify SI system aligned for Recirculation Ifnecessary, ATCIBOP starts 2RSS*P21C, D.

Dependant upon timing, the Recirc Spray pumps may already be running ATC/BOP checks RWST level <369 inches.

due to auto start occurring at 381 inches in the RWST.

CRITICAL TASK:

ES-I.3.A - Crew transfers to cold leg RWST level < 369 inches SRO directs crew to manually align components to recirc and establishes EeCS establish Cold Leg Recirculation flow per recirculation flow prior to loss of Attachment A -0.7.

coolant flow to the core.

ATCIBOP depresses Pushbuttons for SI Recirc Mode Reset, both trains.

A.Tc/BOP closes 2SIS*MOV8887A,B, 21A,B Low Head SI Pump Disch To Hot Legs.

ATCIBOP opens 2SIS*MOV8811A,B, 21C,D Recirc Spr Pp Disch Crossover To 2IA,B LHSI Pump Disch.

ATCIBOP stops 2SIS*P21A,B, Low Head SI Pump.

ATCIBOP closes 2SIS*MOY8809A,B, 21A,B Low Head SI Pump Suet Isol Vlv.

BVPS - 2 Scenario 1, Rev AG 18 of 22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ - iNSTRUCTIC)NAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ATCIBOP places [2RSS*P21C(D)], Recirc Spray Pumps in PULL~TO~ LOCK.

ATCIBOP resets CIB (both trains).

ATCIBOP closes 2RSS*MOV156C(D), 21C(D)

Recirc Spray Pump Disch Isolation Vlvs.

ATCIBOP starts 2RSS*P21C(D), Recirc Spray Pump.

ATCIBOP opens 2SIS*MOV863A,B 21A,B Low Head SI Pump Disch To High Head Pumps.

ATCIBOP closes 2CHS*LCVl15B,D, Charging Pumps Suet From RWST.

ATe/BOP closes 2SIS*MOV8890A,B, 21A,B Low Head SI Pump Min Flow Recirc Isol Vlvs.

ATCIBOP places 2SIS*P2IA,B, Low Head SI Pump control switches in PULL~TO-LOCK.

Terminate drill when crew has established Cold Leg recirculation flow LHSI flow indicated on 2SIS~FI945/946 Crew verifies recirc flow in LHSI and HHSI flow and verified flow in at least one flow HHSI flow indicated on 2SIS~FI943 paths.

path lAW step 3.d ofES~1.3.

Classify Event SRO evaluates EPP and declares an ALERT either due to Loss of ReS Barrier (TAB 1.2.3) or Failure of Rx Protection (Tab 2.3)

BVPS - 2 Scenario 1, Rev AG 19 of 22

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Attachment A-O.11 'Verification of SRO directs an operator to perform Automatic Actions' perfonned as time Attachment A-O.ll as time & manpower permit.

& manpower pennit.

Diesel generators - BOTH RUNNING Check both EDGs running.

Ensure Reheat Steam Isolation Verifies 2MSS-MOVI OOA,B closed.

Depresses reheater controller RESET pushbutton.

CNMT pressure - GREATER THAN 7 PSIG Check if MSLI is required.

OR SG Steam Pressure - LESS THAN 500 PSIG If not required, go to step 4.

OR Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIT Verify steamline isolation.

Open 2CCS-AOVII8 domestic water to station air BOP establishes domestic water system cooling to compressors. the station air compressors by opening 2CCS AOV1l8.

At least one Station Air Compressor - RUNNING BOP starts I station air compressor as required.

CCP pumps - AT LEAST 1 RUNNING Check CCP Pump status - None running due to CIR 2NME-NR45 Nuclear Recorder selected to Align neutron flux monitoring for shutdown.

operable source and intennediate range displays BVPS - 2 Scenario 1, Rev AG 20 of 22

BEAVER VALLEY POWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE CNMT pressure - HAS REMAINED < 11 PSIG Check crn status.

IF NOT Actuate CIB if required.

CRITICAL TASK:

E-O.E - Crew manually actuates at Manually initiate CIB - BOTH SWITCHES FOR BOP Manually Actuates CIB both trains.

least the minimum required BOTH TRAINS complement of containment cooling equipment before an Extreme (red Manually align equipment as required path) challenge develops to the All RCPs - STOPPED Stop ALL RCPs.

Containment CSF. BV-1 operator verifies CREVS actuation and Service water flow established to RSS HX(s)

Service Water Pumps - 2 RUNNING Verify Service Water System in service.

Senrice Water Header Pressure - GREATER THAN55PSIG SWS Seal Water Pressure - NOT LOW (2HCS*SOVIOOAl, Bl] - CNMT Sample amber Verify both CNMT hydrogen analyzers running.

light LIT BVPS - 2 Scenario 1, Rev AG 21 of 22

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ~

Verify ESF Equipment status - Start/align equipment as required.

CRITICAL TASK: All Red SIS Marks - LIT E-O.H - Crew manually starts at least 2SIS*P21A and 2SIS*P21B failed to start If ATC didn't previously start both LHSI pumps one low head ECCS pump before automatically. the BOP will start them now.

transition out of E-O. All Orange CIA Marks - LIT All Green FWI Marks - LIT Power available to both Emergency AC Busses Verify power to both AC Emergency busses.

Restore power as required.

Attachment A-O.ll - COMPLETE Report any discrepancies to SRO.

BVPS - 2 Scenario 1, Rev AG 22 of 22

RTL#A5.640U 112-ADM-1301.F04 Page 3 of 11 Revision 1 JPM NUMBER: 2CR-599 JPM REVISION: 0 JPM TITLE: Verify CREVS Actuation KJA

REFERENCE:

060 AAl.02 2.9/3.1 TASK ID: 0441-007-01-013 JPM APPLICATION: cgJ REQUALIFICATION cgJ INITIAL EXAM D TRAINING cgJ FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site 0 Annual Requal Exam D BVT D Simulate D Simulator [J Initial Exam D NRC D Classroom D OJT/TPE 0 Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 10 minutes Actual minutes Critical: ~ No Time: Time:

JPMRESULTS:

0 SAT D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U l/2-ADM-1301.F04 Page 4 of 11 Revision 1 JPM NUMBER: 2CR-599 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 EVALUATOR DIRECTION SHEET TASK STANDARD: MANUALLY closes 2HVC*MOD201B which failed to AUTO close.

MANUALLY starts 2HVC*FN241B due to 2HVC*FN241A and 2HVC*FN241B failing to start.

RECOMNIENDED Simulator ST ARTING LOCATION:

DIRECTIONS: You are to verify CREVS Actuation.

INITIAL CONDITIONS: A Large Break LOCA has occurred.

A transition to E-1, "Loss of Reactor or Secondary Coolant" has just been made.

crn has actuated.

INITIATING CUE: The Unit Supervisor directs you to petform Step 1 RNO actions ofE-!,

"Loss of Reactor or Secondary Coolant".

REFERENCES:

20M-53A.l.E-I, "Loss of Reactor or Secondary Coolant", Issue IC, Rev. 12.

1I20M-44A.4A.A, "Post Control Room Habitability System Actuation!Recovery", Rev. 15 TOOLS:

HANDOUT: 20M-53A.1.E-I, "Loss of Reactor or Secondary Coolant", Issue IC, Rev. 12.

1/20M-44A.4A.A, "'Post Control Room Habitability System Actuation!Recovery", Rev. 15

RTL#A5.640U 112-ADM-1301.F04 Page 5 of 11 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK:

INITIAL CONDITIONS: A Large Break LOCA has occurred.

A transition to E-l, "Loss of Reactor or Secondary Coolant" has just been made. crn has actuated.

INITIATING CUE: The Unit Supervisor directs you to perform Step I RNO actions ofE-I, "Loss of Reactor or Secondary Coolant".

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM" .

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130l.F04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-599 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) Indicate "s" FOR SAT or "U" FOR UNSAT)=>

START TIME: - - - - - - -

SIMULATOR SETUP:

Begin with any power IC.

Insert aLB LOCA Malfunction (MALF RCS03A(B,C))

on either loop.

Perform actions ofE-O, up to step 10fE-I.

Fail2HVC*MOD201B from AUTO closing (can manually close) as follows:

Select VLV-MSC029 (I-Fail Open)

Select Event Trigger, Select Event #, Enter Event XBSI065C = 1, Enter command DMF VLV-MSC029 Fail 2HVC*FN241 A from AUTO and MANUAL Start:

Ent~~r BST-MSCO14 (0- Actuate)

Enter lOR XBS1077T - OFF

Enter lOR XBS 1077C - ON Fail2HVC*FN241B from AUTO Start ONLY:

Enter BST-MSC013 (O-Actuate)

Freeze and take a snap.

EVALUATOR NOTE:

When the candidate is ready to begin the JPM, place the simulator in RUN.

1. Review procedure. 1.1 Reviews procedure (B-1 Step 1 RNO) provided.

COMMENTS:

2. Actuate both trains using the 2.1 Actuates BOTH trains of CREVS using the CONTROL ROOM EMERG CONTROL ROOM EMERG AIR SUP AIR SUP ACTUATION ACTU ATION pushbuttons located on Building pushbuttons. Services Panel.

COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 7 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-599 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 i STEP I STANDARD

("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I S/U I EVALUATOR NOTE:

The following step can be done in any order.

3. C Verify CREVS actuation: 3.1 Verifies 2HVC*MOD20 1A, "Control Room ACU Control Room Air Intake Outside Air Intake" CLOSED.

Dampers - CLOSED.

3.2 Verifies Green Light - LIT and Red Light - NOT LIT.

3.3 Verifies 2HVC*MOD20 1C, "Control Room ACU Outside Air Exhaust" CLOSED.

3.4 Verifies Green Light - LIT and Red Light - NOT LIT.

3.SC Verifies 2HVC*MOD201B, "Control Room ACU Outside Air Intake" CLOSED. Recognizes 2HVC*MOD201B did NOT AUTO close and manually places 2HVC*MOD201B control switch to CLOSE.

3.6 Verifies Green Light LIT and Red Light - NOT LIT.

3.7. Verifies 2HVC*MOD201D, "Control Room ACU Outside Air Exhaust" CLOSED.

3.8 Verifies Green Light - LIT and Red Light - NOT LIT.

COMMENTS

i

RTL#A5.640U 1I2-ADM-1301.F04 Page 8 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-S99 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or !lU" FOR UNSAT)~ sru I EVALUATOR CUE: When requested, role play and acknowledge request for Unit 1 Control Staff verification of CREVS actuation.

4. Request Unit 1 Control 4.1 Requests Unit 1 Control Room staff to verify CREVS Room staff to verify CREVS actuation.

actuation COMMENTS:

S.C Verify one control room 5.1 Recognizes that neither 2HVC*FN241A or pressurization fan starts. 2HVC*FN241B AUTO started. (Green Lights LIT (2HVC*FN241A or 241B) and Red Lights - NOT LIT.

5.2 Places 2HVC*FN241A control switch to START.

5.3 Recognizes 2HCVC*FN24 1A did NOT start: Green Light - LIT and Red Light - NOT LIT.

5.4C Places 2HVC*FN241B control switch to START.

5.5 Verifies Red Light - LIT and Green Light NOT LIT.

EVALUATOR NOTE: Candidate may opt to attempt a start of a fan prior to going to 1I20M 44A.4A.A, which is acceptable. Operation Managers Expectation is to manually perform actions which should have automatically occurred.

COMfvfENTS:

I

RTL#A5.640U 1I2-ADM-1301.F04 Page 9 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-599 JPM TITLE: VerifY CREVS Actuation JPM REVISION: 0 I STEP I STANDARD

! ("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR UNSAT)=:. I SIU I EVALUATOR NOTE:

Once located, provide candidate a copy of 1/20M 44.4AA, "Post Control Room Emergency Habitability System Activation/Recovery, Part A".

6. Refer to 1I20M-44.4AA, 6.1 Locates and references 1/20M-44.4AA, "Post "Post Control Room Control Room Emergency Habitability System Emergency Habitability Activation/Recovery, Part A".

System Activation/Recovery, Part A".

COl\.1MENTS:

7. If CREVS was initiated as a 7.1 NIA this step since CREVS was initiated by a Large result of a toxic gas release, Break LOCA as opposed to a Toxic Gas Release.

refer to 1I20M 53C.4A44AA, "Toxic Gas

COl\.1MENTS:

Release".

8. VerifY 2HVC*FN24 1A, 8.1 Recognizes 2HVC*FN241A failed to start: Green "Control Room Emer Vent Light -- LIT and Red Light - NOT LIT.

Fan", has auto started AND 2HVC*MOD204A, "Control COMMENTS:

Room Emer Outside Air Intake Damper has opened.

I

RTL#AS.640U 112-ADM-1301.F04 Page 10 of11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-599 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 I ("e" STEP Denotes CRITICAL STEP)

ISTANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I sroJ EVALUATOR NOTE: Some ofthese critical steps may have been previously performed.

9.C If2HVC*FN241A failed to 9.1 Places 2HVC*FN241A control switch to STOP.

start, perform the following:

9.2C Places 2HVC*FN241B control switch to START.

Place 2HVC*FN241A, "Control Room Emer Vent 9.3 Verifies 2HVC*MOD204B OPEN.

Fan" control switch to OFF.

If2HVC*FN241B, "Control 9.4 Verifies Red Light - LIT and Green Light - NOT Room Emer Vent Fan" has LIT.

NOT started automatically, START 2HVC*FN241B. 9.5 Verifies annunciator AlO-3E, "CONTROL ROOM

Verify,2HVC*MOD204B, SUPPLY AIR FLOW LOW" is NOT in alarm.

"Control Room Emerg Outside Air Intake Damper" COMMENTS:

OPEN.

Verify OFF annunciator AIO-3E, "CONTROL ROOM SUPPLY AIR FLOW LOW".

10. If annunciator AI0-3E, 10.1 Recognizes Annunciator AlO-3E is NOT ON: N/A's "CONTROL ROOM EMER this step and does NOT proceed to step IY.A6.

SUPPLY AIR FLOW LOW" is ON, proceed to step COMMENTS:

IY.A6.

RTL#A5.640U 112-ADM-130 l.F04 Page 11 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-599 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate ns" FOR SAT or "U" FOR UNSA EVALUATOR NOTE/CUE: If the candidate decides to leave the control room to obtain DP indications, inform the candidate that an NLO will obtain this information.

11. Observe the following 11.1 Requests an NLO to observe the following indicators:

indicators and verifies the combined differential

2HVC.*PDIS21A(B), DP for 2HVC*FLT A251A(B).

pressure on 2HVC

2HVC-PDIS22A(B), DP for 2HVC*FLTA252A(B).

PDIS21A(B), 22A(B) AND

2HVC-PDIS23A(B), DP for 2HVC*FLTA253A(B).

23A(B) is < 5.6 in. WG.

EVALUATOR CUE: NLO reports 2HVC

2HVC-PDIS21A(B), DP for PDIS21B is reading 1.3 in W.G. 2HVC 2HVC*FLT A251 A(B). PDIS22B is reading 1.2 in W.G. and 2HVC

2HVC-PDIS22A(B), DP for PDIS23B is reading 1.1 in W.G.

2HVC*FLT A252A(B).

2HVC-PDIS23A(B), DP for 2HVC*FLT A253 A(B). 11.2 Determines the combined differential pressure on 2HVC.*PDIS21A(B), 22A(B) AND 23A(B) is < 5.6 in. WG.

IEVALUATOR CUE:

This JPM is COMPLETE.

i COMMENTS:

STOP TIME: - - - - - - - -

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of8 Revision 1 JPM NUMBER: 2PL-061 JPM TITLE: Transferring Power for 2RHS*MOV702A JPM REVISION: 8 KJ A

REFERENCE:

005 K4.07 3.2/3.5 TASK ID: 0101-022-01-042 JPM APPLICATION: rsJ REQUALIFICATION cg] INITIAL EXAM o TRAINING o FAULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

o Perform 0 Plant Site D Annual Requal Exam 0 BVT o Simulate D Simulator D Initial Exam 0 NRC D Classroom D OJT/TPE D Other:

0 Training

[J Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 15 Minutes Actual minutes Critical: rsJ No Time: Time:

JPMRESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments: ---

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U l/2-ADM-130 l.F04 Page 4 of8 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: [2RHS*MOV702A] is powered from [2MCC*E05].

RECOMMENDED In-Plant STARTING LOCATION:

You are to simulate transferring power for [2RHS*MOV702Al DIRECTIONS:

INITIAL CONDITIONS:

The Control Room has been evacuated due to a fire.

The Alternate Safe Shutdown panel has been activated.

A plant cooldown is in progress and nearing the point where the Residual Heat Removal System can be placed into service.

Your supervisor directs you to transfer power for [2RHS*MOV702A]

INITIATING CUE:

from [MCC*2-E06] to [MCC*2-E05] in accordance with 20M-56CA, Subprocedure F -12. The use of any required keys is to be simulated.

20M-56CA.F-12, "Transferring Power For [2RHS*MOV702A] From

REFERENCES:

Normal Power [MCC*2-E06] To Alternate Power [MCC*2-E05]",

Issue 1 Revision 5 TOOLS: Keys (simulated).

HANDOUT: 20M-56CA.F-12, "Transferring Power For [2RHS*MOV702A] From Normal Power [MCC*2-E06] To Alternate Power [MCC*2-E05]",

Issue 1 Revision 5

RTL#AS.640U 1I2-ADM-1301.F04 Page Sof8 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

You are to simulate transferring power for [2RHS*MOV702A].

TASK:

INITIAL CONDITIONS:

The Control Room has been evacuated due to a fire.

The Alternate Safe Shutdown panel has been activated.

A plant cooldown is in progress and nearing the point where the Residual Heat Removal System can be placed into service.

INITIATING CUE: Your supervisor directs you to transfer power for [2RHS*MOV702A]

from [MCC*2-E06] to [MCC*2-E05] in accordance with 20M-56CA, Sub procedure F-12. The use of any required keys is to be simulated.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-061 JPM TITLE: Transferring Power for 2RHS*MOY702A JPMREVISION: 8 I STEP STANDARD I ("e" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=>

STARTTIME: ______________

1. Reviews procedure 20M 1.1 Reviews procedure provided.

56C.4.F-12, "Transferring Power For [2RHS*MOY702A] From COMMENTS:

Normal Power [MCC*2-E06] To Alternate Power [MCC*2-E05]"

2. e Ensure the following breakers 2.1 C Removes lock and energizes [MCC*2-E05] cubicle are energized: 8A by turning the switch handle to the ON position.

[MCC*2-E05] cubicle 8A

[2CAB*RCPBP-04] cubicle EVALUATOR CUE:

R4A Breaker is in the ON position.

2.2 Locates [2CAB*RCPBP-04] cubicle R4A and verifies cubicle R4A in ON position.

EVALUATOR CUE:

Breaker is ON.

COMMENTS:

3.e At [2RHS*TRSMOY702A] 3.1 e Inserts the key into the upper lock for switch handle insert key into the upper lock [MCC*2-E06-7A] and turns it to release the switch on the normal power supply handle.

[MCC*2-E06] to release the switch handle. EVALUATOR CUE:

Key is INSERTED and TURNED.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-061 JPM TITLE: Transferring Power for 2RHS*MOV702A JPM REVISION: 8

\ STEP

. ("e" Denotes CRITICAL STEP)

I STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> Stu \

4.C De-energize normal power 4.lC Pulls the [MCC*2-E06-7 A] switch handle to the OFF

[MCC*2-E06]. position (handle down).

EVALUATOR CUE:

Handle is in OFF position.

I COMMENTS:

S.C Lock the normal power in the S.IC Turns the key in the lower lock to lock [MCC*2-E06 OFF position. 7A] power OFF and remove the key.

EVALUATOR CUE:

Key is TURNED and REMOVED.

CO:NIMENTS:

6.C Place the released key into the 6.1C Places the released key in the lower lock of alternate lower lock on the alternate power [MCC*2-EOS-8A] and turn it to release the power supply [MCC*2-EOS]. switch handle.

EVALUATOR CUE:

Key is INSERTED and TURNED.

COMMENTS:

I I \

RTL#A5.640U 112-ADM-130l.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE :MEASURE JPM NUMBER: 2PL-061 JPM TITLE: Transferring Power for 2RHS*MOV702A JPM REVISION: 8 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "8" FOR SAT or "U" FOR UNSAT)=>

7.C Energize the alternate power 7.1 C Places [MCC*2-E05-8A] switch handle to the ON supply. position (handle up).

EVALUATOR CUE:

Handle is in ON position.

COMMENTS:

8. Lock the alternate power in the 8.1 Turns and removes the key in the upper lock to lock ON position. [MCC*2-E05-8A] power ON.

EVALUATOR CUE:

Key is TURNED and REMOVED.

COMMENTS:

EVALUATOR CUE:

That Completes this JPM STOPTlME: - - - - - - -

RTL#A5.640U I/2-ADM -130 l.F04 Page 3 of8 Revision I JPM NUMBER: 2PL-150 JPM TITLE: Locally Throttle Open AFW Valve During ECA-O.O JPM REVISION: 0 KIA

REFERENCE:

061A2.05 3.1/3.4 TASK ill: 0534-010-05-042 JPM APPLICATION: I:8J REQUALIFICATION I:8J INITIAL EXAM D TRAINING D FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJTITPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 10 Minutes Actual minutes Critical: I:8J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 l.F04 Page 4 ofS Revision 1 EVALUATOR DIRECTION SHEET 2FWE*HCVIOOF is OPEN.

TASK STANDARD:

RECOMMENDED In-Plant STARTING LOCATION:

You are to simulate MANUALLY opening 2FWE*HCVIOOF.

DIRECTIONS:

INITIAL CONDITIONS:

The plant has tripped from 100% and has experienced a loss of all AC power.

The crew has entered ECA-O.O, "Loss Of All AC Power".

Total AFW flow to the Steam Generators is less than 340 gpm.

The Steam Driven AFW Pump is running and aligned to the "B" Header.

21A SG AFW Throttle valve 2FWE*HCVIOOF is CLOSED.

Your supervisor directs you to OPEN 21A SG AFW Throttle valve INITIATING CUE:

2FWE*HCVIOOF by performing 20M-53A.l.A-l.ll, "Manual Handpump Operation Of Hydraulically Actuated Valves". The valve is to be left in the full open position.

20M-53A.1.A-l.ll, "Manual Handpump Operation Of Hydraulically

REFERENCES:

Actuated Valves", Issue 1C Rev. 5.

TOOLS: None 20M-53A.1.A-1.11, "Manual Handpump Operation Of Hydraulically HANDOUT: Actuated Valves", Issue IC Rev. 5.

RTL#A5.640U 1I2-ADM-1301.F04 Page 50f8 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

o Read:

You are to simulate MANUALLY opening 2FWE*HCVlOOF.

TASK:

IN1TIAL CONDITIONS:

The plant has tripped from 100% and has experienced a loss of all AC power.

The crew has entered ECA-O.O, "Loss Of All AC Power".

Total AFW flow to the Steam Generators is less than 340 gpm.

The Steam Driven AFW Pump is running and aligned to the "B" Header.

21A SG AFW Throttle valve 2FWE*HCVlOOF is CLOSED.

Your supervisor directs you to OPEN 21A SG AFW Throttle valve INITIATING CUE:

2FWE*HCVIOOF by performing 20M-53A.1.A-1.11, "Manual Handpump Operation Of Hydraulically Actuated Valves". The valve is to be left in the full open position.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce til am now beginning the JPM" .

o Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

o After determining the Task has been met announce II I have completed the JPM".

Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-150 I .' .

JPM REVISION: 0 1 JPM TITLE. Locally 1hrottle Open AFW Valve Durmg ECA-O.O I STANDARD UNSA~~

STEP

[ ("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" !fQ!!

START TIME:

1. Reviews procedure 20M- 1.1 Reviews procedure provided.

53A.l.A-1.11, "Manual Handpump Operation Of COMMENTS:

Hydraulically Actuated Valves".

EVALUATOR NOTE: It may take the candidate several minutes to proceed to step 4 due to procedure awkwardness.

2. Refer to the two lists in step 1 2.1 Determines 21A SG AFW Throttle valve for "Fail-Closed" vs. "Fail-As 2FWE*HCVlOOF is a "Fail-As-Is" actuator.

Is" actuators.

AND Proceeds to step 4 of the procedure.

COMMENTS:

3. Open supply breaker for 3.1 N/A 2FWE*HCVIOOF EVALUATOR CUE:

[MCC*2-E14 Cub 3D (East Role-play the Unit Supervisor and report that another Cable Vault 735')] operator was dispatched to OPEN MCC*2-E14 Cub 3D, and it is OPEN.

COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERF'ORMANCE MEASURE JPM NUlVIBER: 2PL-150 JPM REVISION: ° JPM TITLE: Locally Throttle Open AFW Valve During ECA-O.O I (STEP "e" Denotes CRlTICAL STEP)

STANDARD i (Indicate "S" FOR SAT or "U" FOR UNSATI::::> S/U I I I EVALUATOR NOTE: ValveisNSAOPEN I

I

! 4.C Place the three position pump 4.1C Rotates the three position pump control valve to control valve to OPEN OPEN position.

position.

EVALUATOR CUE:

Pump control valve is in the OPEN position.

I I

COMl\1ENTS:

I i

5.C Insert the pump handle into the 5.1 Locates the locally mounted hand pump handle.

hand-pump socket 5.2C Inserts the pump handle into the hand-pump socket EVALUATOR CUE:

Pump handle INSERTED.

i COMl\1ENTS:

I i

EVALUATOR NOTE: Valve position is located on back side ofvalve.

6.C Pump the hand pump until 6.1C Pumps the hand pump (up and down) until the valve the valve reaches the desired is full OPEN.

position.

6.2 Verifies valve stem is moving towards the OPEN position.

EVALUATOR CUE:

Valve is FULL OPEN or AS INDICATED.

COMl\1ENTS:

RTL#AS.640U 112-ADM-130 l.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-150 JPM TITLE: Locally Throttle Open AFW Valve During ECA-O.O JPM REVISION: 0 I STEP ! STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~

7.C If the valve is to be left in its 7.1 C Rotates the three position pump control valve to current position, THEN place NEUT position.

the three position pump control valve to NEUT position.

EVALUATOR CUE:

Pump control valve is in the NEUT position.

COMMENTS:

EVALUATOR CUE:

That Completes this JPM STOPTIME: ______________

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of22 Revision 1 JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPMREVISION: 3 KIA

REFERENCE:

064 Kl.Ol 4.114.4 TASK ID: 0362-005-06-013 JPM APPLICATION: I2$J REQUALIFICATION I2$J INITIAL EXAM o TRAINING I2$J FAULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

0 Perform 0 Plant Site 0 Annual Requa! Exam 0 BVT 0 Simulate 0 Simulator D Initial Exam D NRC 0 Classroom 0 OJT/TPE D Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 20 minutes Actual minutes Critical: I2$J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 LF04 Page 40f22 Revision 1 JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 EVALUATOR DIRECTION SHEET TASK STANDARD: Relay 27-VE2200(VF2200) and 27-VE2200X(VF2200X) are tested and reset RECOMMENDED In-Plant STARTING LOCATION:

EVALUATOR NOTE: This JPM is designed for either train. Perform for Train A relays if Protected Train B, and Train B relays if Protected Train A Steps 1-18 of the JPM are for Train A performance. Steps 19-36 ofthe JPM are for Train B performance. Sign key out ahead of time and notify Shift manager that the JPM will be performed. Give key to student during reading of the initiating cue.

DIRECTIONS: You are to simulate the task Test the EDG UV Start Relay.

INITIAL CONDITIONS: The plant is in Mode 5. 20ST-36.15A(l5B) is in progress. The Initial Conditions and Part A, Test Preparation, are complete. Steps 1 through 14 of Part B, Shutdown Mode Testing, are complete.

INITIATING CUE: Your supervisor directs you to review the Initial Conditions and Precautions and Limitations, then perform Part B, Steps 15 through 24 of20ST-36.I5A (I5B).

REFERENCES:

20ST-36.l5A(15B), Revision 3 TOOLS: Key 33 (34) for PNL*2UV-T-A(B)

HANDOUT: 20ST-36.15A(15B), Revision 3 Filled out through step Y.B. 14

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of 22 Revision 1 CANDIDATE DIRECTION SHEET Use This Sheet if Protected Train "A"

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Test the EDG UV Start Relay INITIAL CONDITIONS: The plant is in Mode 5. 20ST-36.15B is in progress. The Initial Conditions and Part A, Test Preparation, are complete. Steps 1 through 14 of Part B, Shutdown Mode Testing, are complete.

INITIATING CUE: Your supervisor directs you to review the Initial Conditions and Precautions and Limitations, then perform Part B, Steps 15 through 24 of20ST-36.15B.

o At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM" .

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

o After determining the Task has been met announce II I have completed the JPM".

Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130l.F04 Page 6 of 22 Revision 1 CANDIDATE DIRECTION SHEET Use This Sheet if Protected Train "B"

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Test the EDG UV Start Relay INITIAL CONDITIONS: The plant is in Mode 5. 20ST-36.15A is in progress. The Initial Conditions and Part A, Test Preparation, are complete. Steps 1 through 14 of Part B, Shutdown Mode Testing, are complete.

INITIATING CUE: Your supervisor directs you to review the Initial Conditions and Precautions and Limitations, then perform Part B, Steps 15 through 24 of20ST-36.1SA.

D At this time, ask the evaluator any questions you have on this JPM.

o When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#AS.640U 1I2-ADM-130 l.F04 Page 7 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STANDARD Indicate "5" FOR SAT or "U" FOR UNSA S~rJ\FlT TIME:

EVALUATOR NOTE:

This is a "F AULTED" JPM, read cues carefully to ensure alternate path situation is presented to candidate.

EVALUATOR NOTE:

This JPM is setup for either Train.

If Train A is to be performed, follow JPM steps 1-18.

If Train B is to be performed, follow JPM steps 19-36.

1. Review the OST. 1.1 Reviews initial conditions, P&Ls and instructions.

COMMENTS:

2. Obtain Key 33. 2.1 N/A provided by evaluator.

COMMENTS:

3. Open the door on the Train A 3.1 Uses key to unlock and open panel door. (PNL

UV Test Panel. 2UV-T-A)

COMMENTS:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 8 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP I STANDARD I ( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> sru I 4.C Place [lB-ENSAB] in TEST. 4.1C Turns 4KV Bus 2AE Test [lB-ENSAB] switch to the TEST position and allows it to spring return to normal.

EVALUATOR CUE:

Test switch was placed in TEST and allowed to spring return to NORM.

COMMENTS:

5. Verify red indicating light for 5.1 Verifies red indicating light for [TEST: 27-VE2200X

[27-VE2200X] is OFF. COIL] is OFF.

EVALUATOR CUE:

Red light is NOT LIT.

COMMENTS:

6. Veri.fy white indicating light 6.1 Verifies white indicating light for [TEST: 27 for [27-VE2200] is OFF. VE2200 CONTACT] is OFF.

EVALUATOR CUE:

White light is NOT LIT.

COMMENTS:

I

RTL#A5.640U 112-ADM-1301.F04 Page 9 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP I STANDARD I ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu I

7. Verify white (Push-to-Test) 7.1 Verifies white test pushbutton for [TEST: 27 pushbutton Test: [27 VE2200X CONTACT] is OFF.

VE2200X] Contacts is OFF (lB-ENSAB). EVALUATOR CUE:

White test pushbutton light is NOT LIT.

COMMENTS:

8. At cubicle 2E6 verify red trip 8.1 At [4KVS*2AE] Swgr, Cubicle 2E6, Verifies red trip target displayed on [27 target is displayed on relay [27-VE2200].

VE2200].

EVALUATOR CUE:

Red trip target is DISPLAYED.

COMMENTS:

RTL#AS.640U 1I2*ADM*1301.F04 Page 10 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3

,STEP STANDARD

("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::::> Stu I

9. Verify control room alarms 9.1 Establishes communications with Control Room.

A8-4H and computer point

[YS714D] are active. 9.2 Requests Control room operator to verify annunciator A8-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" in alarm.

AND Computer point [YS714D] 4KV EMER BUS 2AE UV TEST is active.

EVALUATOR CUE:

Role-play the control room operator and report Annunciator A8-4H, 4KV EMER BUS 2AE12DF UV CKT "IN TEST" is IN ALARM and computer point

[Y5714D) 4KV EMER BUS 2AE UV TEST is ACTIVE.

. COMMENTS:

I lO.C Depress white pushbutton lO.lC Depresses [TEST: 27-VE2200X CONTACT) white and verify lamp ON when pushbutton.

depressed and OFF when released to verify continuity IO.2C Verifies light is ON when pushbutton is depressed.

through the trip circuit (Test

[27-VE2200XD* IO.3C Verifies light goes OFF when pushbutton released.

EVALUATOR CUE:

Light is LIT when button depressed and NOT LIT when button released.

COMMENTS:

I I

RTL#A5.640U II2-ADM-130 l.F04 Page 11 of22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 I

~

STEP STANDARD

("e" Denotes CRITICAL STEP) I. -.---lIndicate "S" FOR SAT or "U" FOR UNSAT)=> Stu I l1.C Reset relay [27-VE2200] by 11.1 C Places and holds for 5 seconds switch IB-ENSAB in placing switch IB-ENSAB in the RESET position.

the RESET position for five seconds minimum. 11.2C Allows it to spring return to NORM.

EVALUATOR CUE:

Switch was held to RESET for 5 seconds and then returned to NORM.

COMMENTS:

~ ----.--~-----------.------+--- ..-....------------.. --------------------+-~

12. Verify white indicating light 12.1 Verifies white light for [TEST: 27-VE2200 for [27-VE2200] and red CON'T ACT] is ON.

indicating light for [27 VE2200X] are ON. 12.2 Verifies red light for [TEST: 27-VE2200X COIL] is ON.

EVALUATOR CUE:

Both lights are LIT.

COMMENTS:

FAULT STATEMENT:

This is where the Alternate path begins, the RELAY will NOT reset on the first attempt, cues are written to support this situation.

RTL#AS.640U 1I2-ADM-1301.F04 Page 12 of22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP

( "C" Denotes CRITICAL STEP)

I STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)::::) S/U

13. Verify circuit is reset by 13.1 Verifi.es [TEST: 27-VE2200X CONTACT] white checking white light on test pushbutton light is ON.

pushbutton is ON when not depressed and OFF when EVALUATOR CUE:

depressed. White light is NOT LIT.

13.2 Determines that the indications do not support verification that the relay was RESET and determines that the relay reset should be attempted a second time.

EVALUATOR NOTE:

Ifthe candidate does depress the button, cue that the light remains NOT LIT.

COMMENTS:

I 14.C Reset relay [27-VE2200] by 14.1C Places and holds for 5 seconds switch IB-ENSAB in placing switch IB-ENSAB in the RESET position.

the RESET position for fi.ve seconds minimum. 14.2C Allows it to spring return to NORM.

EVALUATOR CUE:

Switch was held to RESET for 5 seconds and then returned to NORM.

COMMENTS:

i

RTL#AS.640U 1/2-ADM-1301.F04 Page 13 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM N1.JMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 i STEP

( "C" Denotes CRITICAL STEP) i STANDARD (Indicate "s" FOR SAT or "u" FOR UNSAT)~ Stu J

15. Verify white indicating light 15.1 Verifies white light for [TEST: 27-VE2200 for [27-VE2200] and red CONTACT] is ON.

indicating light for [27 VE2200X] are ON. 15.2 Verifies red light for [TEST: 27-VE2200X COIL] is ON.

EVALUATOR CUE:

Both lights are LIT.

COMMENTS:

16. Verify circuit is reset by 16.1 Verifies [TEST: 27-VE2200X CONTACT] white checking white light on test pushbutton light is ON.

pushbutton is ON when not depressed and OFF when EVALUATOR CUE: I depressed.

I :White light is LIT.

16.2 Depresses [TEST: 27-VE2200X CONTACT] white pushbutton light and verifies light goes OFF when depressed.

EVALUATOR CUE:

White light is NOT LIT when depressed.

16.3 Releases [TEST: 27-VE2200X CONTACT] white pushbutton light and verifies light comes ON when released.

EVALUATOR CUE:

White light is LIT when released.

COMMENTS:

I J

RTL#A5.640U 1I2-ADM-1301.F04 Page 14 of22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STANDARD "e" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "Uti FOR UNSA

17. Verify control room alarms 17.1 Establishes communications with Control Room.

A8-4H and computer point

[YS714D] are reset. 17.2 Requests Control room operator to verify annunciator A8-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is NO LONGER IN ALARM.

AND Computer point [Y5714D] 4KV EMER BUS 2AE UV TEST is normal.

EVALUATOR CUE:

Role-play the control room operator and report Annunciator A8-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is NO LONGER IN ALARM AND Computer point [Y5714D] 4KV EMER BUS 2AE UV TEST is NORMAL.

COMMENTS:

18. At 4KV cubicle 2E6, reset 18.1 At [4KVS*2AE] Swgr, Cubicle 2E6, Depresses the the red trip target on [27 relay target reset pushbutton for relay [27-VE2200].

VE2200].

EVALUATOR CUE:

Red trip target is NOT FLAGGED (BLACK).

COMMENTS:

EVALUATOR CUE:

That completes this JPM. (For Train A)

STOP TIME: - - - - - - - -

RTL#A5.640U 1/2-ADM-1301.F04 Page 15 of22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: 2PL-549 .

JPM REVISION: 3 I JPM TITLE: Test the EDG UV Start Relay I STANDARD

~AT or "Un FOR UNSAT)=> I SIU I STEP 1 ( "e" Den<:,tes CRITICAL STEP) (Indicate "S" FOR EVALUATOR NOTE:

Steps 19-36 are for Train B performance. :I

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

_ . . . -------------------------+------------------------------------------+-----i

19. Review the OST. 19.1 Reviews initial conditions, P&Ls and instructions.

COMMENTS:

20. Obtain Key 34. 20.1 Nt A provided by evaluator.

COMMENTS:

21. Open the door on the Train B 21.1 Uses key to unlock and open panel door. (PNL

UV Test Panel. 2UV-T-B)

COMMENTS:

22.C Place [IB-ENSBB] in TEST. 22.1C Turns 4KV Bus 2DF Test [lB-ENSBB] switch to the TEST position and allows it to spring return to normal.

EVALUATOR CUE:

Test switch was placed in TEST and allowed to spring return to NORM.

COMMENTS:

RTL#AS.640U 1I2-ADM-1301.F04 Page 16 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM ]\lUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 I STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U

23. Verify red indicating light for 23.1 Verifies red indicating light for [TEST: 27-VF2200X

[27-VF2200X] is OFF. COIL] is OFF.

EVALUATOR CUE:

Red light is NOT LIT.

COMMENTS:

i

24. Verify white indicating light 24.1 Verifies white indicating light for [TEST: 27-VF2200 for [27-VF2200] is OFF. CONTACT] is OFF.

EVALUATOR CUE:

White light is NOT LIT.

COMMENTS:

25. Verity white (Push-to-Test) 25.1 Verifies white test pushbutton for [TEST: 27 pushbutton Test: [27 VF2200X CONTACT] is OFF.

VF2200X] Contacts is OFF (lB-ENSBB). EVALUATOR CUE:

White test pushbutton light is NOT LIT.

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 17oi22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP

( "e" Denotes CRITICAL STEP)

ISTANDARD (Indicate "S" FOR SAT or "U" FOR UN8AT)~ 81U I

26. At cubicle 2F6 verify red trip 26.1 At [4KVS*2DF] Swgr, Cubicle 2F6, Verifies red trip target displayed on [27- target is displayed on relay [27-VF2200].

VF2200].

EVALUATOR CUE:

Red trip target is DISPLAYED.

COMMENTS:

27. Verify control room alarms 27.1 Establishes communications with Control Room.

A8-4H and computer point

[Y5715D] are active. 27.2 Requests Control room operator to verify annunciator A8-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" in alarm.

AND Computer point [Y5715D] 4KV EMER BUS 2DF UV TEST is active.

EVALUATOR CUE:

Role-play the control room operator and report Annunciator A8-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is IN ALARM and computer point

[Y5715D] 4KVEMERBUS 2DF UVTEST is ACTIV}:.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 18 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP \ STANDARD I ( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=:> \ sru \

28.C Depress white pushbutton 28.1 C Depresses [TEST: 27-VF2200X CONTACT] white and verify lamp ON when pushbutton.

depressed and OFF when released to verify continuity 28.2C Verifies light is ON when pushbutton is depressed.

through the trip circuit (Test

[27 -VF2200X]). 28.3C Verifies light goes OFF when pushbutton released.

EVALUATOR CUE:

Light is LIT when button depressed and NOT LIT when button released.

COMMENTS:

29.C Reset relay [27-VF2200] by 29.1C Places and holds for 5 seconds switch IB-ENSBB in placing switch IB-ENSBB in the RESET position.

the RESET position for five seconds minimum. 29.2C Allows it to spring return to NORM.

EVALUATOR CUE:

Switch was held to RESET for 5 seconds and then returned to NORM.

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 19 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP STANDARD

("e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT}==> Stu I

30. Verify white indicating light 30.1 Verifies white light for [TEST: 27-VF2200 for [27-VF2200] and red CONTACT] is ON.

indicating light for [27 i VF2200X] are ON. 30.2 Verifies red light for [TEST: 27-VF2200X COIL] is ON.

EVALUATOR CUE:

Both lights are LIT.

COMMENTS:

FAULT STATEMENT:

This is where the Alternate path begins, the RELAY will NOT reset on the first attempt, cues are written to support this situation.

31. Verify circuit is reset by 31.1 Verifies [TEST: 27-VF2200X CONTACT] white checking white light on test pushbutton light is ON.

pushbutton is ON when not depressed and OFF when EVALUATOR CUE:

depressed. White light is NOT LIT.

31.2 Determines that the indications do not support verification that the relay was RESET and determines that the relay reset should be attempted a second time.

i EVALUATOR NOTE:

If the candidate does depress the button, cue that the light remains NOT LIT.

i COMMENTS:

i i

RTL#A5.640U 1I2-ADM-1301.F04 Page 20 of 22 Revision 1 OPERATIONS JOB PERFORMANCE :MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 I STEP STANDARD

("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU 32.C Reset relay [27-VF2200] by 32.1C Places and holds for 5 seconds switch IB-ENSBB in placing switch IB-ENSBB in the RESET position.

the RESET position for five seconds minimum. 32.2C Allows it to spring return to NORM.

EVALUATOR CUE:

Switch was held to RESET for 5 seconds and then returned to NORM.

COMMENTS:

33. Verify white indicating light 33.1 Verifies white light for [TEST: 27-VF2200 for [27-VF2200] and red CONTACT] is ON.

indicating light for [27 VF2200X] are ON. 33.2 Verifies red light for [TEST: 27-VF2200X COIL] is ON.

EVALUATOR CUE:

Both lights are LIT.

COMMENTS:

RTL#A5,640U 112-ADM-130l.F04 Page 21 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3

\ STEP

( "C" Denotes CRITICAL STEP)

J STANDARD Jlndicate "S" FOR SAT or "U" FOR UNSAT)=> S/U \

34. Verify circuit is reset by 34.1 Verifies [TEST: 27-VF2200X CONTACT] white checking white light on test pushbutton light is ON.

pushbutton is ON when not depressed and OFF when EVALUATOR CUE:

depressed.

White light is LIT. I 34.2 Depresses [TEST: 27-VF2200X CONTACT] white pushbutton light and verifies light goes OFF when depressed.

EVALUATOR CUE:

White light is NOT LIT when depressed.

34.3 Releases [TEST: 27-VF2200X CONTACT] white pushbutton light and verifies light comes ON when released.

EVALUATOR CUE:

White light is LIT when released.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 22 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP STANDARD

( "e" Denotes CRITICAL STEP) Indicate "s" FOR SAT or "U" FOR UNSAT)::::>

35, Verify control room alarms 35,1 Establishes communications with Control Room.

A8-4H and computer point

[Y5715D] are reset. 35.2 Requests Control room operator to verify annunciator A8-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is NO LONGER IN ALARM.

AND Computer point [Y5715D] 4KV EMER BUS 2DF UV TEST is normal.

EVALUATOR CUE:

Role-play the control room operator and report Annunciator A8-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is NO LONGER IN ALARM AND Computer point [Y5715D] 4KV EMER BUS 2DF UV TEST is NORMAL.

COMNIENTS:

36. At 4KV cubicle 2F6, reset 36.1 At [4KVS *2DF] Swgr, Cubicle 2F6, Depresses the the red trip target on [27 relay target reset pushbutton for relay [27-VF2200].

VF2200l EVALUATOR CUE:

Red trip target is NOT FLAGGED (BLACK).

. COMMENTS:

EVALUATOR CUE:

That completes this JPM. (For Train B)

STOP TIME: c - '_ _ _ _ __

RTL#A5.640U 1I2-ADM-130 1.F04 Page 3 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM N1JMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoj)erable Rod) SRO ONLY KIA

REFERENCE:

2.1.25 4.2 TASK ID: 0011-006-06-013 JPM APPLICATION: C8J REQUALIFICATION C8J INITIAL EXAM D TRAINING D FAULTEDJPM C8J AD1vlINISTRATlVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site 0 Annual Requal Exam D BVT 0 Simulate 0 Simulator D Initial Exam D NRC D Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 25 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

0 SAT 0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 4 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determine that Shutdown Margin is greater than COLR required value of 1. 77% and less than 2.4%. Determines Power defect is 2340 + 20 pem.

RECOMMENDED Classroom ST ARTING LOCATION:

DIRECTIONS: Determine Shutdown Margin in accordance with 20ST-49.1, Shutdown Margin Calculation (plant Critical) (Updated for Cycle 15).

INITIAL CONDITIONS: The Unit is in Mode 1, 100% power. All rods at 230 steps.

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 838 ppm. Current burnup is 12,000 MWDIMTU INITIATING CUE: The Shift Manager directs you to perform a shutdown margin (SDM) calculation for the present plant conditions by performing steps VII.A through VII.C.1 of20ST-49.1, Shutdown Margin Calculation (Plant Critical). Report your results in the space provided. Be sure to include a determination of whether or not the Technical Specification required SDM is being met. (Space provided on candidate direction sheet).

REFERENCES:

20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15), Rev. 16, Unit 2 Curve Book Cycle 15 (dated 4/911 0),

License Requirement Manual, Technical Specifications.

TOOLS: Calculator HANDOUT: 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15), Rev. 16 Filled out up to step VII.A Unit 2 Curve Book Cycle 15 (dated 4/9/10), License Requirement Manual, Technical Specifications.

RTL#A5.640U 1I2-ADM-130l.F04 Page 5 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

TIDS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Determine Shutdown Margin in accordance with 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15).

INITIAL CONDITIONS: The Unit is in Mode 1, 100% power. All rods at 230 steps.

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 838 ppm. Current burnup is 12,000 MWDIMTU INITIATING CUE: The Shift Manager directs you to perform a shutdown margin (SDM) calculation for the present plant conditions by performing steps VItA through VII. C.l of 20ST-49.1, Shutdown Margin Calculation (Plant Critical). Report your results in the space provided. Be sure to include a determination of whether or not the Technical Specification required SDM is bein met.

RESULTS:

Calculated SDM is- - - - - - - -

Calculated SDM _ _ _ _ _ _within the limits specified in the Technical Specifications?

IS/IS NOT D At this time, ask the evaluator any questions you have on this JPM.

o When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#AS.640U 1I2-ADM-130 1.F04 Page 6 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) SRO ONLY STEP STANDARD

("C" Denotes CRITICAL STEP) Indicate "s" FOR SAT or "U" FOR UNSAT)=>

EVALUATOR NOTE:

Some judgment may be required to determine satisfactory performance on this JPM. Refer to attached Data Sheet 1 ANSWER KEY.

STARTTIME: ______________

1. If the plant is in Mode 1, Verify 1.1 Initials Step VII. A 1, (plant in Mode 1, Tavg <3 OF that Tavg is less than 3°F above above Tref(Annunciator A4-3C OFF) from Initial Tref (Annunciator A4-3C, Conditions.

TAVG DEVIATION FROM TREF is OFF) (Otherwise N/A). COMMENTS:

(Step VII. A I)

2. If the plant is in Mode 2, Verify 2.1 N/A's Step VII.A2, (plant not in Mode 2).

that Tavg is less than 8°F above Program Tavg as follows:

(Otherwise NIA) COMMENTS:

(Step VII.A2)

3. Request Chemistry to 3.1 Determines current boron concentration is 838 ppm determine current RCS Boron from initial conditions.

concentration in ppm.

(Step VILA3)

COMMENTS:

RTL#A5.640U 112-ADM-130l.F04 Page 7 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-03S JPM TITLE: Perform Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) SRO ONLY I STEP \ STANDARD U "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)::::;> I stu I

4. Record the number of steps 4.1 Records Control Bank D as 230 steps withdrawn on withdrawn for Control Bank D Data Sheet 1 (Block A4) from initial conditions.

from the group demand counters, (BB-B) on Data Sheet 1. COMrvIENTS:

. (Step VII.A4)

I

5. Record the current reactor 5.1 Records reactor power as 100% on Data Sheet 1 power level in percent of full (Block AS).

power from [2NME-NR4S],

Power Range Recorder, (VB B) OR PCS computer point COMMENTS:

UllSO, IMIN AVG PWR RNG NUCLEAR FLUX, on Data Sheet 1.

(Step VII.AS) 6.C Record the number of 6.1 C Records number of immovable or untrippable rods as immovable or untrippable "ONE" on Data sheet 1 (Block A 6) (given in Initial control rods on Data Sheet 1. Conditions).

(Step VII.A6)

COMMENTS:

7. If the number of immovable or 7.1 Determines Step VII.A7 is N/A and marks step N/A untrippable control Rods is greater than 1, Use Attachment 1 to determine the required COMMENTS:

boron concentration with greater than one struck rod and Record below. (Otherwise

! N/A)

I (Step VII.A7)

RTL#A5.640U 112-ADM-130 l.F04 Page 8 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) SRO ONLY STEP STANDARD

("e" Denotes CRITICAL STEP) (Indicate "8" FOR SAT or "U" FOR UNSAT)=> 8tu 8.C Determine control bank 8.1C Determines ARO Total Bank Worth (from the Data reactivity worth per the Sheet 1 table) to be 7.425 %AkIk and records on Data following: Sheet 1 (Block B.1.a).

Using the ARO Total Bank Worth table on Data Sheet 1, COMMENTS:

Enter the total bank worth for the current core bumup range, in the space provided on Data Sheet 1.

(Step VII.B.1.a) 9.C Using Curve Book Figures 9.1C Using Curve Book Figure CB-24B, determines CB-24A, 24B or CB-24C, integral rod worth to be ZERO and records on Data Determine integral rod worth Sheet 1 (Blocks B.1.b.1) and B.1.b).

for the current bank position AND Enter this value on Data Sheet 1. COMMENTS:

Divide value from curve (in pcm) by 1000 to convert to

%Aklk AND Record on Data Sheet 1.

(Step VII.B.1.b)

10. Subtract the integral rod 10.1 Determines TBW-IRW is 7.425 %Aklk and records worth from the Total Bank on Data Sheet 1 (Block B.1.c).

Worth AND Enter the result on Data Sheet 1.

COMMENTS:

(Step VII.B.1.c)

I

RTL#A5.640U 1!2-ADM-1301.F04 Page 9 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM N£..ThIlBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) SRO ONLY STEP

( "e" Denotes CRITICAL STEP)

I STANDARD (Indicate "S" FOR SAT or "U" FOR UNSA1):::::)o I S/U I

11. Multiply this result by 0.9 to 11.1 Determines 90% ofTBW to be 6.6825 %AkJk and apply a 10% uncertainty records on Data Sheet 1 (Block B.1.d).

AND Enter the result on Data Sheet 1.

COMMENTS:

(Step VILB.I.d) 12.C If ONE rod is inoperable 12.IC Determines stuck rod worth to be 2.330 %AkIk and (untrippable), Record "Worst records on Data Sheet 1 (Block B.2).

Case Stuck Rod with Inoperable Rod" worth on Data Sheet 1. Value is COMMENTS:

determined from Column "B" on Attachment 2 for the appropriate Cycle Bumup.

(Step VII.B.2.b)

13. Subtract Stuck Rod(s) Worth 13.1 Determines 90% Total Bank Worth minus Stuck from the 90% Total Bank Rod(s) Worth to be 4.3525 %AkJk and records on Worth value AND Enter the Data Sheet 1 (Block B.3).

result on Data Sheet 1.

(Step VII.B.3)

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 10 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) SRO ONLY

~TEP

( "e" Denotes CRITICAL STEP)

I STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)==>

i S/U I

14. Determine Power Defect as 14.1 Record RCS Boron Concentration of838 ppm on follows: Data Sheet 1 (Block BAa).

Record RCS Boron Concentration results from COMMENTS:

Chemistry on Data Sheet 1.

(Step VII.BA.a)

15. Using Curve Book Figure 29, 15.1 Determines B-I0 Correction Factor to be 0.895 and Determine the B-1 0 records on Data Sheet 1 (Block BAb).

Correction Factor for the present Burnup (If between two Burnup values, Use the COMMENTS:

B-I0 Correction Factor for the greater MWDIMTU Burnup entry) AND Record on Data Sheet 1. I (Step VII.B.4.b) i i

I

16. Determine Corrected Boron 16.1 Determines Corrected Boron Concentration to be 750 Concentration by multiplying ppm and records on Data Sheet 1 (Block BA.c).

the RCS Boron Concentration and the B-1 0 Correction Factor AND COMMENTS:

Record on Data Sheet 1.

(Step VII.BA.c)

RTL#A5.640U 1/2-ADM-1301.F04 Page 11 of 12 Revision 1 OPERATIONS JOB PERFORMANCE NIEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) SRO ONLY STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSA1)o I SIU

17. U sing Curve Book Figure 21, 17.1 Determines ABSOLUTE VALUE of the Power Determine the ABSOLUTE Defect to be 2340 pcm and records on Data Sheet 1 VALUE of the Power Defect (Block BAd).

for the current power level and the Corrected Boron Concentration AND Enter COMNIENTS:

this value on Data Sheet 1.

(Step Vn.B.4.d) 18.C Divide value from curve (in 18.1C Converts ABSOLUTE VALUE of the Power Defect pcm) by 1000 to convert to of2340 pcm to 2.34 %~k/k and records on Data

%~k/k AND Record on Data Sheet 1 (Block B.4.e).

Sheet 1.

(Step VII.B.4.e)

COMMENTS:

19. Add 0.IS0 % ~k1k for 19.1 Determines Power Defect plus operating temperature operating temperature band band margin to be 2.49 % ~k/k and records on Data margin to the Power Defect Sheet 1 (Block BAf).

recorded in Step VILB.4.e AND Record on Data Sheet

l. COMMENTS:

(Step VII.B.4.f)

I

RTL#A5.640U 112-ADM-1301.F04 Page 12 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) SRO ONLY STEP STANDARD

( "e" Denotes CRITICAL STEP) Indicate "s" FOR SAT or "U" FOR UNSAT)=>

20. C Determine SHUTDOWN 20.IC Determines SDM to be 1.8625 % AkJk and records on MARGIN by subtracting Data Sheet 1 (Block B.4.t) AND space provided on Power Defect (Step candidate direction sheet.

VII.B.4.t) from the value determined in Step VII.B.3 AND Record on Data Sheet COMMENTS:

1.

(Step VII.B.5) 21.C Consult the Acceptance 21.1 Consults the Acceptance Criteria, LRM 5.1.2, and Criteria for acceptable Technical Specification 3. 1. 1.

performance.

21.2C Determines SDM is within limits and records on space (Step VII.C.1) provided on candidate direction sheet.

COMMENTS:

EVALUATOR CUE:

That Completes this JPM STOPTIME: ______________

8VPS - SBS Unit 2 205T-49.1 Revision 16 Operating Surveillance Test Page 12 of 17 Shutdown Margin Calculation (Plant Critical)

(Updated For Cycle 15)

~*1fJL l:\N~

,./' -11 V wfR KEV~HUTDOWN ""'~ATA SHEET 1 MARGIN CALCULATION A. 4. CBD Steps Withdrawn (OR CBC if CBD @ 0 steps) STEPS

5. Reactor Power %

6. Number of inoperable Rods ROD(s)

ARO TOTAL BANK WORTH (% Aklk) oto 10000 MWD/MTU I I 10000 to EOL 6.985 J I 7.425 -1 B. 1. a. AR o Total Bank Worth (See Table above)

I (TBW) , =21 ~ 0/_ .... C

b. Integral Rod Worth (Curve Book Figure 24A, 24B OR 24C) (IRW) I - ~, ......... C'

1) __ 4-#,<<_ __ (pcm from B.1.b) X ~ = ---.,F#"---- % AkJk f"'L 1OOOpcm

c. TBW (B.l.a) -IRW (B.l.b.l)

d. 90% Current Total Bank Worth o.9x7*12S f"2[%tM \

ti (B.l.c) 2.

3.

Stuck Rod(s) Worth (90% Total Bank Worth) - (Stuck Rod(s) Worth)

L*1.33 %A>Jk C J.

(,.(,,82..5 )o( 2.. 330 =4.35Z5%AkJk (B.l.d) (B.2)

4. a. RCS Boron Concentration = 838 ppm

b. B-l0 Correction Factor (CB Figure 29) =0.815

= 750 ppm

d. ABSOLUTE VALUE of Power Defect (CB Figure 21) = 234\0 pcm

e. 2310 (pcm from B..

1%ak/k 4 d) X -

1000 P*3~

$1

%AkJk S)

f. Power Defect + Operating temperature band margin 2..! , -4 = 2.. 11

5. SHUTDOWN MARGIN (B.4.e) + 0.150% AkJk %AkJk

[ 1 (Acceptance Criteria Within Limits Specified In COLR) 0 (1.3515 (B.3)

)of 2. . ~1 )

(B.4.~

=1.8"'2 S %AkJk C (1 )

Initial (2)

Initial DATA SHEET 1

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of7 Revision 1 OPERATIONS JOB PERFORMANCE :rvIEASURE JPM NUMBER: 2AD-024 JPM TITLE: Determine Availability For Call-in (3 ROs) SRO ONLY JPM REVISION: 1 KJA

REFERENCE:

2.1.3 3.9 TASK ID: 0481-002-03-043 JPM APPLICATION: [g] REQUALIFICATION [g] INITIAL EXAM D TRAINING D FAULTEDJPM [g] ADMINISTRATIVE JPM EVALUATION :rvIETHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam 0 BVT 0 Simulate 0 Simulator D Initial Exam 0 NRC D Classroom D OJT/TPE 0 Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 15 Minutes Actual minutes Critical: L8J No Time: Time:

0 SAT JPM RESULTS:

0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-1301.F04 Page 4of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determines that working hour limits ofNOP-LP-4011, FENOC Work Hour Control, will be exceeded for ROs Bill and Joe AND NOT exceeded for Sam.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to perform the task "Determine availability for call-in".

INITIAL CONDITIONS: Both Units have been in Mode 1 for the past 100 days. Today is 8/14/10. The daylight RO for 8/15110 has called in sick. It is desired to replace the daylight RO by assigning an RO to fill this vacancy. Three ROs are available to assume this vacancy, beginning at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on 8/15/10. The available RO replacements have the listed work hour history.

INITIATING CUE: As the Unit Supervisor, determine which one(s), if any of the available RO replacements are able to work the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months daylight shift on 8/1511 0 without violating the 10CFR 26 Work Hour Limits specified in NOP LP-4011, FENOC Work Hour Control. Explain why or why not.

Document your results on the sheet provided.

REFERENCES:

NOP-LP-4011, FENOC Work Hour Control, Rev. 3 TOOLS: Calculator.

HANDOUT: Working hour history; NOP-LP-4011, FENOC Work Hour Control, Rev. 3

RTL#A5.640U 1I2-ADM-l30 l.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perform the task "Determine availability for call-in".

INITIAL CONDITIONS: Both Units have been in Mode 1 for the past 100 days. Today is 8/14/10. The daylight RO for 8/15110 has called in sick. It is desired to replace the daylight RO by assigning an RO to fill this vacancy. Three ROs are available to assume this vacancy, beginning at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on 8/15/10. The available RO replacements have the listed work hour history.

IN1TIATING CUE: As the Unit Supervisor, determine which one(s), if any of the available RO replacements are able to work the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months daylight shift on 8115/10 without violating the 10CFR 26 Work Hour Limits specified in NOP LP-4011, FENOC Work Hour ControL Explain why or why not.

Document your results on the sheet provided.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce II I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-024 JPM REVISION: 1 JPM TITLE: Determine Availability For Call-in (3 ROs) SRO ONLY STEP STANDARD

( "e" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSA EVALUATOR CUE:

PROVIDE WORK HISTORY SHEET (LAST PAGE OF JPM)

START TIME: _ _ _ _ _ __

1. Evaluate work hour history. l.1 Compares work hour history against NOP-LP-4011, FENOC Work Hour Control requirements of section

4.2. COMMENTS

2.C Determines working hour 2.1 C Determines that RO Bill may NOT be called in.

limit will be exceeded for RO 2.2C Determines that RO Bill will exceed 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in 48 Bill, and documents on the hours after working 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months on 8/15. (Turnover times sheet provided. are not considered in this determination) 2.3C Documents the result in the space provided.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 7 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-024 JPM TITLE: Determine Availability For Call-in (3 ROs) SRO ONLY JPM REVISION: 1 i STEP \ STANDARD

("C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=>

3.C Determines working hour 3.1C Determines that RO Joe may NOT be called in.

limit will be exceeded for RO 3.2C Determines that the RO Joe will exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 Joe, and documents on the days.

sheet provided. 3.3C Documents the result in the space provided.

COMMENTS:

4. C Determines working hour 4.lC Determines that RO Sam may be called in.

limit will NOT be exceeded 4.2C Determines that RO Sam meets all of the call-in for RO Sam, and documents requirements on the sheet provided. 4.3C Documents the result in the space provided.

COMMENTS:

EVALUATOR CUE:

The evaluation on this JPM is complete when the applicant determines whether the ROs may be called m.

STOP TIME:

WORK HISTORY T 10 = Turnover time Joe, Sam, and Bill are all 8- hour Operations Shift workers.

~re Joe Sam Bill 7/18/10

. through Vacation Vacation Vacation I 8/7/10 8/8/10 OFF 0700-1500 1500-2300 \

T/O 20 min T/O 20 min

\

8/9/10 0700-1900 0700-1900 1500-2300 T/O 20 min T/O 20 min T/O 20 min 8/10/10 0700-1900 1100-2300 OFF I T/O 20 min T/O 20 min 8111110 0700-1900 1500-2300 OFF T/O 20 min T/O 20 min 8112/10 0700-1900 1500-2100 0700-1500 I T/O 20 min T/O 20 min T/O 20 min L

8113110 0700-1900 0700-1500 1100-2100 T/O 20 min T/O 20 min T/O 20 min 8/14/10 0700-1700 0700-1900 0700-2000 T/O 20 min* T/O 20 min T/O 20 min 8/15/10 OFF OFF OFF RESULTS:

WORK HISTORY ANSWER'KEY DO NOT GIVE TO STUDENTS T/0 = Turnover time Joe, Sam, and Bill are all 8- hour Operations Shift workers.

Date Joe Sam Bill 7/18/10 through Vacation Vacation Vacation 8/7110 818/10 OFF 0700-1500 1500-2300 T/O 20 min T/O 20 min 8/9/10 0700-1900 0700-1900 1500-2300 T/O 20 min T/O 20 min T/O 20 min 8/10/10 0700-1900 1100-2300 OFF T/O 20 min T/O 20 min 8/11/10 0700-1900 1500-2300 OFF T/O 20 min T/O 20 min 8/12/10 0700-1900 1500-2100 0700-1500 T/O 20 min T/O 20 min T/O 20 min 8/13/10 0700-1900 0700-1500 1100-2100 T/O 20 min T/O 20 min T/O 20 min 8/14/10 0700-1700 0700-1900 0700-2000 T/O 20 min T/O 20 min T/O 20 min

~-

8/15/10 OFF OFF OFF RESULTS:

1. RO Bill may NOT be called in. He will exceed 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after working 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months on 8/15.

2. RO Joe may NOT be called in. He will exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 days.

3. RO Sam may be called in. He meets all of the call-in requirements

RTL#A5.640U 1I2-ADM-130l.F04 Page 3 of?

Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-033 JPM TITLE: Determine Compensatory Actions for Low CO 2 Tank Level JPM REVISION: 0 SRO ONLY KIA

REFERENCE:

2.2.37 4.6 TASK ID: 1300-029-03-023 JPM APPLICATION: I2l REQUALIFICATION I2l INITIAL EXAM o TRAINING D FAULTEDJPM C8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

o Perform 0 Plant Site 0 Annual Requal Exam D BVT D Simulate D Simulator 0 Initial Exam D NRC 0 Classroom 0 OJTITPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 Minutes Actual minutes Critical: C8J No Time: Time:

JPMRESULTS:

0 SAT 0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-1301.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Required actions of 1I2-ADM-1900, Fire Protection Program Attachment B items 4a and 4b are identified.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to Determine appropriate Compensatory Actions for Low CO2 Tank Level.

INITIAL CONDITIONS: Both Units have been in Mode 1 for the past 100 days. The 24 Ton CO2 storage tank 2FPD-TK24 is empty and on clearance for maintenance.

The tour operator reports the following CO2 Storage Tank levels:

10 Ton CO2 Storage Tank 2FPD-TK22 is 86%

10 Ton CO2 Storage Tank 2FPD-TK23 is 80%.

7.5 Ton CO2 Storage Tank 2FPD-TK21 is 70%

INITIA TING CUE: Determine the required 112-ADM-1900, Fire Protection Program compensatory actions, if any, for these CO2 Storage Tank levels. List any required actions on the attached answer sheet.

REFERENCES:

1I2-ADM-1900, Fire Protection Program Rev. 22 TOOLS: None HANDOUT: 112-ADM-1900, Fire Protection Program Rev. 22

RTL#A5.640U 1I2-ADM-130l.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to Determine appropriate Compensatory Actions for Low CO2 Tank LeveL INITIAL CONDITIONS: Both Units have been in Mode 1 for the past 100 days. The 24 Ton CO2 storage tank 2FPD*TK24 is empty and on clearance for maintenance.

The tour operator reports the following CO2 Storage Tank levels:

10 Ton C02 Storage Tank 2FPD-TK22 is 86%

10 Ton CO2 Storage Tank 2FPD-TK23 is 80%.

7.5 Ton CO 2 Storage Tank 2FPD-TK21 is 70%

INITIATING CUE: Determine the required 112-ADM-1900, Fire Protection Program compensatory actions, if any, for these CO2 Storage Tank levels. List any required actions on the attached answer sheet.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM" .

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verifY or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2*ADM*1301.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-033 JPM TITLE: Determine Compensatory Actions for Low CO2 Tank Level JPM REVISION: 0 SROONLY STEP STANDARD

( "e" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSA EVALUATOR CUE:

Provide student with attached answer sheet to document the determination.

START TIME: _ _ _ _ _ __

I.C Determines l12-ADM-I900, 1.1C Utilizes Attachment B item 4a and determines the Fire Protection Program item following actions are required:

4a required actions Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Establish a continuous fire watch in the following areas:

Cable Spreading Area CntrL Bldg. Elev. 725

Process Rack Area CntrL Bldg. Elev. 707

Cable Tunnel (Between Cntr!' & Aux. Bldgs.) Elev.

712

West Cable Vault Elev. 735

Cable Vault & Rod Cntrt Area Elev. 755

Cable Spreading Area Service Bldg. Elev. 745 1.2C Restore to operable status within 14 days COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 7 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-033 JPM TITLE: Determine Compensatory Actions for Low CO2 Tank Level JPMREVISION: 0 SROONLY

. STEP STANDARD

. ( "e" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=>

2.C Determines 1/2-ADM-1900, 2.1 C Utilizes Attachment B item 4b and determines the Fire Protection Program item following actions are required:

4b required actions Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Establish an hourly fire watch patrol and establish controls to prohibit transient combustibles and ignition sources in the following areas:

Relay Room Elev. 755

Emergency Diesel Generator Bldg. Rooms

East Cable Vault Elev. 735 2.2C Identifies the need to verify the operability of Early Warning Fire Detection in the following affected areas:

Relay Room Elev. 755

Emergency Diesel Generator Bldg. Rooms

East Cable Vault Elev. 735 2.3C Restore to operable status within 14 days COMMENTS:

EVALUATOR CUE:

That Completes this JPM.

STOP TIME:

ANSWER SHEET PROVIDED TO STUDENT 1/2-ADM-1900, Fire Protection Program required Actions, if any, if there are none, simply state NONE:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-O 14 JPM REVISION: 1 JPM TITLE: Approve Emergency Exposure KIA

REFERENCE:

2.3.4 3.7 TASK ID: 1350-006-03-023 JPM APPLICATION: C8J REQUALIFICATION [gJ INITIAL EXAM o TRAINING o FAULTED JPM C8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

o Perform 0 Plant Site o Annual Requal Exam o BVT 0 Simulate 0 Simulator o Initial Exam o NRC 0 Classroom o OJTITPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 15 Minutes Actual minutes Critical: C8J No Time: Time:

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2~ADM~ 130l.F04 Page 4 of6 Revision 1 OPERATIONS JOB PERFORMANCE :MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determine appropriate Emergency authorization limit in accordance with EPP/IP 5.3 (Limit exposure to: 75 rem TEDE; 225 rem lens of eye, 750 rem organ CDE)

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: Determine the Emergency Exposure Authorization Limit.

INITIAL CONDITIONS:

A Site Area Emergency has been declared at Unit 2.

An individual is trapped and bleeding in a Locked High Radiation Area.

An immediate response is necessary to save their life.

It has been clearly determined that actions establishing adequate or equivalent protection, with less dose are not readily available.

Bill Jones, a qualified radiation worker has volunteered to perform the rescue activity and has been briefed on risks of projected radiation exposure.

Bill Jones has a year to date exposure of 880 mR (TEDE).

The area dose rate is 8,110 mRlhr and there is no airborne radioactivity present.

The rescue activity could take up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

INITIATING CUE: As the Emergency Director, you are to evaluate the listed conditions and determine the Emergency Exposure Authorization Limit. Document your determination in the box below. The Emergency Exposure Authorization Form will NOT be filled out at this time.

REFERENCES:

1I2-EPP/IP 5.3 Emergency Exposure Criteria and Control, Rev. 10 TOOLS: None HANDOUT: 1I2-EPPIIP 5.3 Emergency Exposure Criteria and Control, Rev. 10

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Determine the Emergency Exposure Authorization Limit.

INITIAL CONDITIONS:

A Site Area Emergency has been declared at Unit 2.

An individual is trapped and bleeding in a Locked High Radiation Area.

An immediate response is necessary to save their life.

It has been clearly determined that actions establishing adequate or equivalent protection, with less dose are not readily available.

Bill Jones, a qualified radiation worker has volunteered to perform the rescue activity and has been briefed on risks of projected radiation exposure.

Bill Jones has a year to date exposure of 880 mR (TEDE).

The area dose rate is 8,110 mRlhr and there is no airborne radioactivity present.

The rescue activity could take up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

INITIATING CUE: As the Emergency Director, you are to evaluate the listed conditions and determine the Emergency Exposure Authorization Limit. Document your determination in the box below. The Emergency Exposure Authorization Form will NOT be filled out at this time.

DETERMINATION:

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "1 am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce "1 have completed the JPM" .

D Then hand this sheet to the evaluator.

R1L#A5.640U 1I2-ADM-1301.F04 Page 6 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-0 14 JPM REVISION: 1 JPM TITLE: Approve Emergency Exposure STANDARD Indicate "s" FOR SAT or "U" FOR UNSA START TIME: _ _ _ _ _ _ __

1.C Per Attachment A, determine 1.1 C Using Attachment A, determines the Emergency the appropriate Emergency Exposure Authorization Limit:

Exposure Authorization Limit.

Block 1:

(Step 8.1.1)

Declared Emergency YES Site Area Personnel are qualified YES No declared pregnant YES Male workers Block 2:

Exposure necessary to (1) save human life YES Block 3:

Personnel are volunteers and have been YES briefed on risks of projected radiation exposure Block 4C:

Sr. Vice President authorization for NO (3,244 exposure >75 rem mR)

Block 5C:

Limit exposure to: 75 rem TEDE; 225 rem lens of eye, 750 rem organ CDE COMMENTS:

EVALUATOR CUE:

That completes this JPM STOPTIME: _____________

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of8 Revision 1 JPM NUMBER: 2AD-034 JPM TITLE: Classify an Emergency Event (Scenario Specific)

JPM REVISION: 0 KJA

REFERENCE:

2.4.41 4.6 TASK ID: 1350-004-03-023 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D FAULTEDJPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam 0 NRC 0 Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 10 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

0 SAT 0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-1301.F04 Page 4 of8 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: The correct EPP classification is made for the associated scenario AND all "critical" steps of the initial notification form are correctly completed.

RECOM:MENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform the task Classify An Emergency Event and complete the initial notification form.

INITIAL CONDITIONS: The simulator scenario just completed.(2LOT7 NRC Exam)

INITIATING CUE: As the Unit Supervisor, you are to classify the events in the scenario just completed in accordance with EPPII-la, Recognition and Classification of Emergency Conditions AND complete the initial notification form.

F or the purpose of filling out the initial notification form the following conditions exist:

The code word is "TANGO"

Unit 1 is at 100% steady state power

Wind direction at 150' is 65°

Wind speed at 35' is 7 mph

REFERENCES:

EPP/I-l b, Recognition and Classification ofEmergency Conditions, Rev. 14, 1/2-EPP-IP-1. LFOl, Nuclear Power Plant Initial Notification Form Rev. 4 TOOLS: None HANDOUT: EPP/I-l b, Recognition and Classification of Emergency Conditions, Rev. 14, 1I2-EPP-IP-1.1.FOl, Nuclear Power Plant Initial Notification Form Rev. 4

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of8 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perform the task Classify An Emergency Event and complete the initial notification form.

INITIAL CONDITIONS: The simulator scenario just completed.(2LOT7 NRC Exam)

INITIATING CUE: As the Unit Supervisor, you are to classify the events in the scenario just completed in accordance with EPPII-la, Recognition and Classification of Emergency Conditions AND complete the initial notification form.

For the purpose of filling out the initial notification form the following conditions exist:

The code word is "TANGO"

Unit I is at 100% steady state power

Wind direction at 150' is 65°

Wind speed at 35' is 7 mph o At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce II I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130l.F04 Page 6 of8 Revision 1 OPERATIONS JOB MEASURE JPM NUMBER: 2AD-034 JPM TITLE: Classify Emergency Event (Scenario Specific)

JPM REVISION: 0 STANDARD "s" FOR SAT or "u" FOR NOTE:

'-'..u"......, .... ~..., is being evaluated on classifying the Iscenan' just completed. (2LOT7 NRC be necessary to review the events oe~~m~lmg the JPM.

1.C Classify the event in 1.1C '-'11....1\.'.1 correctly classifies the event.

accordance with the Emergency Plan.

ALERT Tab 1.2.3 OR Tab 2.3

ALERT Tab 1.2.4

SITE AREA EMERGENCY Tab 2.3

. #4: SITE AREA EMERGENCY Tab 1.2.3 AND 1.3.2 COMMENTS:

RTL#AS.640U 1I2-ADM-130 l.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-034 JPM TITLE: Classify an Emergency Event (Scenario Specific)

JPM REVISION: 0

STEP U"e" Denotes CRITICAL STEP)

\ STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT}=:> \ Stu \

2, C Completes the initial 2.1 C Places the following information on the space notification form. provided on the initial notification form.

Item 1 places a checkmark in the this is a drill box

Item 2 leaves name and notification time blank (this is for the communicator) places the word TANGO in the code space.

C Item 3 places a checkmark in the appropriate classification box (as identified in step 1 of the JPM above) and places a checkmark in the initial declaration box

Item 3 places a 2 in the Unit space, places current time in the declaration time space, places the date in the date space, places Unit 1 at 100% and Unit 2 at 0% in the all units power level space.

C Item 4 places the appropriate EAL tab number in the EAL number space (as identified in step 1 of the JPMabove).

Item 4 places the appropriate EAL description in the space provided (as identified in step 1 of the JPM above)

C Item 5 places a checkmark in the an airborne radiological release in progress due to this event box.

C Item 6 places 65° and 7 mph in the wind speed and direction spaces

Item 7 places a checkmark in the this is a drill box 2.2 Places candidate name and current date in the approved space and date.

2.3 Places an X in the NONE box on page 2 (PAR)

COMMENTS:

I

RTL#A5.640U 112-ADM-1301.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUlVIBER: 2AD-034 JPM TITLE: Classify an Emergency Event (Scenario Specific)

JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "8" FOR SAT or "U" FOR UN8A =:> Stu EVALUATOR NOTE:

Refer to Answer Key for initial notification form critical steps.

EVALUATOR CUE:

That completes this JPM STOPTIME: ______________

1I2*EPP*IP*1.1.FOl A N 5 WER t\ E>'1 RTL# A5.715DP Rev. 4 SCENA RIO 11 Page 1 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM

1. Call Status ~ THIS IS A DRILL o THIS IS AN ACTUAL EVENT

2. This is:

At: Beaver Valley Power Station

~~~;~;;~one 724-643-8000 The Code Word is: TA N&O Notification Time is: _ _ _ __

... tt C 3. Emergency Classification: 0 Unusual Event o General Emergency

~ Alert o This event has been terminated o Site Area Emergency Unites): o Both Declaration Time: T, M e.., Date: ----'D~It..!:-LV...3e-=-___

Power Level at time of Notification UNIT 1 100 % UNIT2

..(J %

~

This represents alan:

\'

C II

~ Initial Declaration o Escalation ] In Classification Status o NoChange

4. The Emergency Action Level (EAL) number is: -[JIB 1.2.3 D8 Z.3 Brief non-technical description of the event:

'1\ II o No Radiological Release in Progress due to the event e 5. There is: ~ An Airborne Radiological Release in Progress due to the event o A Liquid Radiological Release in Progress due to the event 1

,\ It t 6. Wind Direction is FROM: degrees at 150' Wind Speed is: mph at 35'

~

7.

Conclusion:

THIS IS A DRILL o THIS IS AN ACTUAL EVENT APPROVED: DATE:

PEERCBECK

1I2-EPP-IP-1.1.FOl RTL# A5.715DP Rev. 4 Page 2 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM BEAVER VALLEY POWER STATION PROTECTIVE ACTION RECOMMENDATION (PAR) 0 INITIAL - .. TIME D UPGRADED TIME

~ NONE (Done) INIT.

D N/A D 2 Miles Evacuate 3600 D 5 Miles D 10 Miles AND D N/A Evacuate Downwind Wedge D 5 Miles (circle appropriate sectors)

D 10 Miles (circle appropriate sectors)

A B C D E F G H J K L M N P Q R D N/A D Remainder of lO-Mile Emergency Planning Zone (EPZ)

Shelter D IO-Mile EPZ D 0-2 Miles, 360 Degrees and 5 Mile Downwind Wedge (circle appropriate sectors)

A B C D E F G H J K L M N P Q R D Administer Potassium Iodide in accordance with State Plan D Plant Conditions D Release In Progress D Dose Projection REASON D Other (Explain)

Other Info:

Current Wind Direction is FROM -~

degrees at 150' Wind Speed is _ _ _ mph at 35' l\PPROVED:

DATE PEER CHECK:

lIl-EPP-IP-l.1.FOl It N5WE. R K! Y RTL# AS.71SDP Rev. 4 SCENt\ RIO Ir l Page 1 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM

1. Call Status ) ( THIS IS A DRILL o THIS IS ANACTUAL EVENT

2. This is:

Beaver Valley Power Station

At:

My Telephone 724-643 -8000 The Code Word is: -r A N'-0 Notification Time is:

Number is: I" \7 ______

".. t' C 3. Emergency Classification: 0 Unusual Event o General Emergency

~ Alert o This event has been terminated o Site Area Emergency Unit(s): 1 (i) Both Declaration Time: T. M e, Date: _Da::....::If--=----v-==e~_ __

Power Level at time of Notification UNIT 1 It)O % UNIT 2 fi %

This represents a/an: "

C II

~ Initial Declaration o Escalation ] In Classification Status o No Change 71t8 I. 2.1

\\ "

4. The Emergency Action Level (EAL) number is:

Brief non-technical description of the event: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

'"C"5.

o No Radiological Release in Progress due to the event There is: ~ An Airborne Radiological Release in Progress due to the event o A Liquid Radiological Release in Progress due to the event

.. loS 1

,\

C. 6. Wind Direction is FROM: degrees at 150' Wind Speed is: mph at 35'

~ THIS IS A DRILL

7.

Conclusion:

o THIS IS ANACTUAL EVENT APPROVED: DATE:

PEER CHECK

1I2-EPP-IP-1.1.FOl RTL# A5.715DP Rev. 4 Page 2 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM BEAVER VALLEY POWER STATION PROTECTIVE ACTION RECOMMENDATION (PAR)

D INITIAL _ _ _ TIME D UPGRADED _ _ _ TIME

~ NONE (Done) _ _ _ INIT.

0 N/A 0 2 Miles Evacuate 360 0 D 5 Miles D 10 Miles

'-~----AND 0 N/A Evacuate Downwind Wedge 0 5 Miles (circle appropriate sectors) 0 10 Miles (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o N/A D Remainder of IO-Mile Emergency Planning Zone (EPZ)

Shelter o 10-Mile EPZ o 0-2 Miles, 360 Degrees and 5 Mile Downwind Wedge (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o Administer Potassium Iodide in accordance with State Plan o Plant Conditions o Release In Progress 0 Dose Projection REASON o Other (Explain)

Other Info:

Current Wind Direction is FROM _ _ _ degrees at 150' Wind Speed is _ _ _ mph at 35' APPROVED:

DATE PEERCBECK:

1I2-EPP-IP-l.1.FOl A NSWE R t\ EY3 RTL# A5.715DP Rev. 4 SCENt\ RIO 11 Page 1 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM

1. Call Status X THIS IS A DRILL o THIS IS AN ACTUAL EVENT

2. This is:

Beaver Valley Power Station

At:

My Tele~hone Number 1S:

_7_2_4_-6_4~3_-8_00_0_ The Code Word is: -rIn A N'-O

\7 Notification Time is:

,II .' -----

C. 3. Emergency Classification: 0 Unusual Event o General Emergency o Alert o This event has been terminated

~ Site Area Emergency Unit(s): o Both Power Level at time of Notification Declaration Time:

UNIT 1 IbO 7, fV\ e- Date:

% UNIT2 (j %

DA-re This represents alan: " C. II ~ Initial Declaration

~

o Escalation ] In Classifi<eatipo S1atus o No Change

4. The Emergency Action Level (EAL) number is: 1/tB 2. 5 Briefnon-technical description of the event: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

'" II o No Radiological Release in Progress due to the event C 5. There is: K An Airborne Radiological Release in Progress due to the event o A Liquid Radiological Release in Progress due to the event

,\

t 6. Wind Direction is FROM:

~ THIS IS A DRILL degrees at 150' Wind Speed is:

1 mph at 35'

7.

Conclusion:

o THIS IS AN ACTUAL EVENT APPROVED: DATE:

PEER CHECK

1/2-EPP-IP-l.l.FOl RTL# A5.715DP Rev. 4 Page 2 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM BEAVER VALLEY POWER STATION PROTECTIVE ACTION RECOMMENDATION (PAR) o INITIAL _ _ _ TIME o UPGRADED _ _ _ TIME

~ NONE (Done) INIT.

0 N/A 0 2 Miles Evacuate 3600 0 5 Miles 0 10 Miles 1----- AND 0 N/A Evacuate Downwind Wedge 0 5 Miles (circle appropriate sectors) 0 10 Miles (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o N/A Shelter o Remainder of lO-MiIe Emergency Planning Zone (EPZ) o 10-Mile EPZ o 0-2 Miles, 360 Degrees and 5 Mile Downwind Wedge (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o Administer Potassium Iodide in accordance with State Plan o Plant Conditions o Release In Progress 0 Dose Projection REASON o Other (Explain)

Other Info:

Current Wind Direction is FROM _ _ _ degrees at 150' Wind Speed is _ _ _ mph at 35' APPROVED:

DATE PEER CHECK:

1I2-EPP-IP-1.1.FOI ft NSWE R t( EY RTL# A5.715DP Rev. 4 SCENA RIO #- 4 Page 1 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM

1. Call Status ) ( THIS IS A DRILL o THISJS AN ACTUAL EVENT

2. This is:

Beaver Valley Power Station

At:

My Tele~hone Number IS:

724-643-8000 The Code Word is: T_nj~ N\7~O Notification Time is:

~. II C 3. Emergency Classification: 0 Unusual Event o General Emergency o Alert o This event has been terminated

~ Site Area Emergency Unites): 1 0 Both Declaration Time: ,., fV\ e-- Date: ---lDIIE-,;;.'+~T4..:::11e.oE-_ __

Power Level at time ofNotification UNIT 1 100 % UNIT2 Ii %

This represents alan:

\'

C II ~

~ Initial Declaration o Escalation In Classification Status o No Change

,\ "

4. The Emergency Action Level (EAL) number is: I. 3.2 Briefnon-technical description of the event: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

'" II o No Radiological Release in Progress due to the event C 5. There is: ~ An Airborne Radiological Release in Progress due to the event o A Liquid Radiological Release in Progress due to the event e.

,l *.

6. Wind Direction is FROM: G:> 5 degrees at 150' Wind Speed is:

1 mph at 35'

7.

Conclusion:

~ THIS IS A DRILL o THIS IS ANACTUAL EVENT APPROVED: DATE:

'PEER CHECK

1I2-EPP-IP-l.1.FOl RTL# A5.715DP Rev. 4 Page 2 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM BEAVER VALLEY POWER STATION PROTECTIVE ACTION RECOMMENDATION (PAR)

D INITIAL _ _ _ TIME D UPGRADED _ _ _ TIME

~ NONE (Done) - - INIT.

D N/A D 2 Miles Evacuate 360 0 D 5 Miles D 10 Miles I------AND ~ .- - - - - - - - - - - - - - - - - - - - - - - - - - - I D N/A Evacuate Downwind Wedge D 5 Miles (circle appropriate sectors)

D 10 Miles (circle appropriate sectors)

A B C D E F G H J K L M N P Q R D NlA D Remainder of 10-Mile Emergency Planning Zone (EPZ)

Shelter D 10-Mile EPZ o 0-2 Miles, 360 Degrees and 5 Mile Downwind Wedge (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o Administer Potassium Iodide in accordance with State Plan o Plant Conditions D Release In Progress 0 Dose Projection REASON o Other (Explain)

Other Info:

Current Wind Direction is FROM _ _ _ degrees at 150' Wind Speed is _ _ _ mph at35' APPROVED:

DATE PEER CHECK:

A.ppen d IX D s cenarlo

' 0utline Form ES-D-1 Facility: FENOC BVPS Unit 2 Scenario No.: 2. Op Test No.: 2LOT7NRC Examiners: Candidates: SRO ATC BOP Initial IC 212: 10% power, BOL, Equ. XE Conditions, CB "D" @ 118 steps, RCS boron - 1854 Conditions: ppm, Condensate Polishing Air Compressor - OOS.

Turnover: Raise power to 15% to Stu main turbine.

Critical Tasks: E-3.A, Isolate Ruptured SG E-3.B, Cooldown RCS E-3.C, Depressurize ReS Event Malf. No. Event Type Event Description No.

t R(ATC) Normal power increase to 15% lAW 20M-52.4.A NISRO/BOP) 2 RCS04B C(ALL) SO 21B Tube Leak SROTS 3 CNHMSS03A C (ATC/SRO) SO 21B atmospheric dump valve fails open.

SROTS 4 NIS08A I(ALL) N41 Power Range Instrument fuse blown SROTS) 5 RCP06B C (ATC/SRO) 21 B RCP high vibration (Manual RCP trip required)

RCPOIB Manual reactor trip 6 RCS04B M(ALL) 21 B SO Tube Rupture 7 CNHPCS07A I (BOP/SRO) Condenser steam dumps fail c1osed.(Requires cooldown with 21 A and 21 C Atmospheric Steam Dumps 8 VL V*MSS057A C (BOP/SRO) 2SDS-AOV129A failed open, requires RNO actions for S/O isolation_

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor NUREG-1021 , Revision 9 Supplement 1 FENoe Facsimile Rev AG

Appendix 0 Scenario Outline Form ES-O-1 After taking the shift, the crew will continue the startup to raise power to 15% in accordance with 20M-52.4.A,

rrt IV A, Plant Startup, currently the plant is at 10% power and Step 7 is in progress. The ATC will withdraw control rods lAW the reactivity plan while the BOP will be required to manually control the "C" S/G level due to the AUTO level control function being OOS.

A SG Tube leak will occur as evidenced by Rad monitor indications, the Unit Supervisor will direct actions per AOP 2.6.4 and refer to TS 3.4.13 for Primary to Secondary leakage.

2SVS*PCV101B, 21B SG atmospheric steam dump valve will fail open and stick open, the valve will not close in Auto, Manual or Locally, requiring the crew to direct the local isolation. The Unit Supervisor will refer to TS 3.7.4 for Inoperable Atmospheric Steam Dumps.

An Instrument power fuse will blow for Power range Channel N41, requiring the use of AOP 2.2.1 C. The crew will take actions per AOP 2.2.1 C and the SRO will evaluate TS 3.3.1.

When the AOP actions are completed for N41, a 21B RCP high vibration condition develops, the crew will respond using AOP 2.6.8. The high vibration will increase at>1 millhr which requires the crew to trip the reactor, enter E-O and take the reactor coolant pump out of service.

Following the reactor trip, a 500 gpm SGTR occurs on the 21B SG resulting in a Safety Injection actuation.

The crew will transition to E-3 at the "Check ifSG Tubes are Intact" step ofE-O.

~Vhen the cooldown is attempted in E-3 the condenser steam dumps will fail closed, requiring the BOP operator

.0 use manual control of the atmospheric steam dump valves andlor 2SVS-HCVI04.

The drill will be terminated when HHSI flow is isolated in E-3.

Expected procedure flow path is EO -+ E3.

NUREG-1021 , Revision 9 Supplement 1 FENoe Facsimile Rev AG

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 10 % Power, CBD = 118, EQU XE BOL, 1854 PPM Boron, IC-212 ADDITIONAL LINEUP CHANGES STICKERS YOND MARKINGS 2SAS-C22 in PTL YCTonCS None 2FWS-FCV499 AUTO Pushbutton YCTonCS None EOUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION(S) 2SAS-C22 OOS 2 days ago None 2FWS-FCV499 AUTO control OOS Yesterday, 1200 hrs None SHIFT TURNOVER INFORMATION

1. Plant is at 10% power, BOL, EQU XE, CB "D" at 118 steps, RCS boron = 1854 ppm.

2. Protected Train is Train "B"

3. Continue the plant startup to 100% IAW 20M-52.4.A, Step 7

4. 2SAS-C22, Condensate Polishing Air Compressor OOS for overhaul.

5. AUTO control function of"C" Bypass Feed Reg Valve, 2FWS-FCV499 is OOS, requires manual operation.

SCENARIO SUPPORT MATERIAL REQUIRED

1. Plant startup reactivity plan.

2. Placard for 2FWE*P22 position stating 2FWE*P22 is aligned to "A" header

3. Place plaque on wall for Protected Train "B"

4. 20M-52.4.A, Increasing Power From 5% Reactor Power And Turbine On Turning Gear To Full Load Operation, completed through Step 7.a.l SETUP Start w/IC-5, raise power to 10% lAW reactivity plan and 20M-52.4.A, then SNAP IC BVPS - 2 Scenario 2, Rev AG 1 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 r=JNSTROCTIONAL GUiDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Initialize IC Set 212, and establish Reactor plant at 10% power, BOL, equilibrium initial plant conditions. conditions. RCS boron 1854 PPM, CBD = 118 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the drill Setup section ofthe HTML File for this drill:

TRGSET 1 'JPPLP4(1), Set trigger 1 on Reactor Trip TRGSET 4 'TPCSTAAU <=530' Set trigger 4 on Tavg < 530 degrees f IMF CNH-PCS07A (4 0) 0 2MSS-PK464 failed, closes Steam Dumps IMF VL V-MSS057A (0 0) 100 2SDS*AOV129A failed open TRGSET 6 'JMLRCP6B = l' Set trigger 6 when malfunction RCP06B is actuated TRG 6 'IMF RCP06B 21 600 15' Ramp RCP vibration to 21 mils over 10 minutes BVPS - 2 Scenario 2, Rev AG 20f25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Assign shift positions ATC:

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless it operators. needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 2, Rev AG 3 of 25

BEAVER VALLEY t"OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 1:

Normal Plant Startup, Reactor Power increase to 15% to support Turbine Startup.

20M-52.4.A, step 7 Crew commences power increase in accordance with reactivity plan.

Continue reactor startup Reactor at 10% power.

ATC commences raising reactor power to between 10 and 15%.

Status lights on Panel 308 actuate at 10%. ATC verifies P-IO bistables lit on Panel 308 ATC verifies AI2-IG, 'P-lO PERMISSIVE' - LIT.

AI2-2B, - 'NIS IR TRIP BLOCKED' - LIT. ATC blocks the IR High Flux Trip AND IR High Flux Rod Stop by placing the IR BLOCK TRAIN and TRAIN B control switches to the BLOCK position and verifies annunciator A12-2B is LIT.

AI2-2C, - 'POWER RANGE LOW SETPOINT ATC blocks the Power Range Low Overpower Trip TRIP BLOCKED' LIT. by placing the PR BLOCK TRAIN A and TRAIN B control switches to the BLOCK position and verifies annunciator A12-2C is LIT.

AI2-IH, - 'NOT P-7' NOT LIT. ATC verifies that annunciator AI2-IH, 'NOT P-7' is NOT LIT.

BVPS - 2 Scenario 2, Rev AG 4 of 25

BEAVER VALLEY POWER STATION 112 - ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE A4-5G, - 'NIS POWER RANGE HIGH/LOW SP ATC verifies that annunciator A4-5G is OFF.

NEUTRON FLUX HIGH' NOT LIT.

ATC selects highest power ranges on N-45.

"C" S/G level decreases during power increase. BOP controls S/G level at target using manual controlof2FWS-FCV499.

Proceed with next event at LE discretion BVPS - 2 Scenario 2, Rev AG 50f25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 2:

After Crew has raised reactor power to 15% Insert TRG! 3 IMMEDIATE PLANT RESPONSE:

A4-5A; - 'RADIATION MONITORING SYSTEM ATC reports Alarms to the SRO.

IMF RCS04B (3 0) 0.040 TROUBLE' - LIT (pre-loaded) A4-5C, - 'RADIATION MONITORING LEVEL BOP checks DRMS panel and detennines that HIGH' - LIT 2MSS-RQ102B is indicating a 53 gpd tube leak in 53 gpd tube leak "B" S/G. the "B" S/G.

BOP refers to the ARP and detennines entry to AOP 2.6.4 is necessary.

SRO refers to AOP-2.6.4 Estimate initial pri-sec leakrate SRO detennines that the leak rate is> 30 gpd due to the HIGH alarm on 2MSS-RQI02B actuated.

Check PZR level - DROPPING ATC detennines value and trend for PZR level PZR Level is stable SRO monitors SG Tube leak by perfonning ATTACHMENT 1 of AOP 2.6.4.

BVPS - 2 Scenario 2, Rev AG 6of25

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ATTACHMENT 1, >5 gpd tube leak If necessary, ATC opens 2SSR *AOV117 A,B,C prior to obtaining Blowdown samples.

BOP to report leak rate from N-16 monitor every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SRO Notifies Chemistry of entry into AOP-2.6.4, requests them to identify S/G, and quantify leakrate and report every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SRO Notifies RP of entry into AOP-2.6.4, requests them to quantify leakrate and report every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and to obtain grab samples every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and calculate leakrate based upon samples.

SRO determines leak rate is > 30 gpd and proceeds to ACTION LEVEL 1 of Attachment 1.

BVPS - 2 Scenario 2, Rev AG 7of25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ACTION LEVEL I, >30 gpd tube leak If necessary, ATC opens 2SSR*AOVI17A,B,C prior to obtaining Blowdown samples.

BOP to report leak rate from N-16 monitor every 15 minutes.

SRO Notifies Chemistry of entry into AOP-2.6.4, requests them to identify S/G, and quantify ~eakrate and report every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SRO Notifies RP of entry into AOP-2.6.4, requests them to quantify leakrate and report every 15 minutes and to obtain grab samples every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and calculate leakrate based upon samples, and perform additional surveys as appropriate.

SRO determines sustained leakrate is < 75 gpd and does not enter ACTION LEVEL 2.

SRO references Technical Specification 3.4.13 for "Res Operational Leakage", determines not applicable until leakage > 150 gpd.

Next event occurs 10 minutes from initiation of Tube Leak (pre-loaded)

BVPS - 2 Scenario 2, Rev AG 8of25

BEAVER VALLEY POWER STATION 112 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 3:

IMMEDIATE PLANT RESPONSE:

10 minutes after tube leak occurs, STATUS #2 ALARM PANEL on VB-C indicates 2SVS-PCVlOIB fails OPEN, requires SG 21B ATM STM DUMP, 2SVS-PCVlOIB is manual isolation 'NOT CLOSED' Red light illuminated for 2SVS-PCVlOIB IMF CNH-MSS03B (3 600) 100 RCS Tavg shows a slight decrease SRO directs ATC to take manual control of open (pre-loaded) ADV, (2SVS-PCVI01B) and close it.

SG level deviation alarms may actuate.

ADV will NOT close from BB control ATC places controller for 21B SG ADV in manual and attempts to close ADV.

SRO requests I&C assistance.

Crew notifies Field operator to close 2SVS Valve requires manual isolation, valve PCVIOIB using 20M-21.4.J will not close via either local manual Or locally isolate via 2SVS-24 or de-energize via operation or by de-energizing MCC ROLEPLAY:

IF requested to Isolate 2SVS-24, INSERT 'LOA-MSSOI7 0' then report to Control Room that 2SVS-24 is isolated SRO refers to TS 3.7.4, Condition A for inoperable atmospheric dump valve. Requires restoring within 7 days.

BVPS - 2 Scenario 2, Rev AG 90f25

BEAVER VALLE'r POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Continue with next event at LE discretion EVENT 4 N41 Instrument Power fuse blows IMMEDIATE PLANT RESPONSE:

A4-4F, -'NIS POWER RANGE COMPARATOR ATC notes associated Power Range alarms and IMF NIS08A (0 0) 0 DEVIATION' - LIT indications, reports this to SRO.

A4-4G, - 'NIS POWER RANGE NEUTRON FLUX RATE HIGH' - LIT SRO determines AOP 2.2.1 C is necessary due to A4-4H, - 'NIS POWER RANGE HIGH indications of failed Power Range channel.

SETPOINT OVERPWR ROD STOP BLOCK ROD WID' - LIT A4-5G, - 'NIS POWER RANGE HIGHfLOW SP NEUTRON FLUX HIGH' - LIT BB-B Indication for N41 indicates downscale NIS Rack drawer 41A, downscale indication and all Indicating lights illuminate.

Crew verifies malfunction of only 1 Power Range Channel has occurred.

BVPS - 2 Scenario 2, Rev AG 10 of 25

BEAVER VALLE t'POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7

,-INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE To comply with TS 3.3.1, functions 17.c, 17.d, &

17.e, within I hr, SRO directs ATC to verify P-8, P-9 and P-l 0 interlocks are in the required state for the existing Plant conditions.

ATC verifies A 12-1 G - P-1 0 PERMISSIVE' ,

A12-2G 'NOT P-8' and A12-3G - 'NOT P-9' ALL LIT and in the required state for the plant being at 15% power.

Within 72 hrs, SRO directs BOP to TRIP the Nuclear Bistables by removing the Control Power Fuses from Drawer N41A.

ALL STATUS lights on Drawer N41A extinguish. BOP removes Control Power Fuses from drawer N41A.

At NIS Rack N50, BOP turns the "Rod Stop Bypass Switch" to BYPASS for N41.

Status light A-14 on status panel 308 illuminates ATC verifies status light A-14 on status panel 308 A4-4H, - 'NIS POWER RANGE HIGH illuminates.

SETPOINT OVERPWR ROD STOP BLOCK ROD WID' - CLEARS ATe verifies Reactor Power is < 50%

BVPS - 2 Scenario 2, Rev AG 11 of 25

BEAVER VALLE 1 POWER STATION 112 -ADM -1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE At NIS Rack N371N46, BOP turns "Comparator Channel Defeat Switch" to N41 channel.

NIS Drawer N371N46 Status light indication for "CHANNEL DEVIATION" clears and indication illuminates for "COMPARATOR DEFEAT" A4-4F, -'NIS POWER RANGE COMPARATOR DEVIATION' - CLEARS ATC verifies Vertical board recorders are NOT selected to N41.

To comply with TS 3.3.1 functions 6 & 7, SRO contacts I&C and requests Bistables on Attachment 1 for N41be tripped w/in 72 hrs.

ATC verifies Reactor Power is < 50%

SRO refers to TS 3.3.1 function 2.b and to SR 3.2.3.1 for applicability, determines they are not applicable due to being at 15% reactor power.

Continue with next event at LE discretion BVPS - 2 Scenario 2, Rev AG 12 of 25

BEAVER VALLE. POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT #5 B RCP High Vibration/Seal Failure Insert the following: IMMEDIATE PLANT RESPONSE:

21 B RCP sealleakoff rising as indicated on 2CHS ATC acknowledges RCP Hi vibration alarm, IMF RCPOIB (5 0) 4 30 FR154A. informs SRO, BOP refers to A2-5C ARP.

A2-5C, - 'REACTOR COOLANT PUMP Crew notes 21 B RCP Shaft vibrations at 15 mils IMF RCP06B (5 0) 15 VIBRATION ALERTIDANGER' -LIT and trends.

IMF RCP06B 2160015 (inserted as 21B RCP vibration rises to >20 mils.

pre-load on trg 6)

SRO enters AOP-2.6.8, Crew checks RCP parameters in Table 1 of AOP 2.6.8 to determine if Criteria is met for an Immediate RCP Shutdown.

NOTE:

Trend on RCP vibration will need to be SRO continues in AOP 2.6.8 observed before RCP trip criteria is met.

ATC verifies that EITHER Seal Injection Flow OR Thermal Barrier cooling flow is indicated to EACH RCP.

NOTE: SRO refers to Attachment 3 for RCP Vibration SRO May not enter Attachment 3 if issue.

Trend ofRCP vibration has identified Immediate RCP Trip Criteria has been met.

BVPS - 2 Scenario 2, Rev AG 13 of 25

BEAVER VALLE:: I POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Shaft vibration> 15 mils and rising at > 1.0 When it is determined that RCP vibration is > 15 milslhr. mils rising at>1 mil/hour, the SRO directs a reactor trip and the stopping of21B RCP after E-O Immediate Actions are completed.

EVENT 6 ATC manually trips reactor.

500 gpm B SGTR IMF RCS04B (1 0) 500 (preload) 500 gpm 21 B SGTR when the reactor is tripped. ATC informs SRO of a reactor trip.

Steps 1 - 4 ofE-O are Immediate ATCIBOP commence IMA's ofE-O, SRO Actions. references E-O to verify lMA' s.

A5-6D, - 'TURBINE TRIP DUE TO REACTOR ATC verifies reactor trip.

TRIP' - LIT.

Power range indication - LESS THAN 5%

Neutron flux dropping.

Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency Buses.

ENERGIZED BVPS - 2 Scenario 2, Rev AG 14 of 25

BEAVER VALLE:, POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Due to SGTR; RCS pressure reducing PZR Level goes offscale low.

SG level and Feedflow /Steam flow mismatch BOP will continue to control "C" S/G level due to alarms will occur. 2FWS-FCV499 controller in manual.

NOTE: SI may not have actuated at Evaluate if SI is Actuated or Required this time however, RCS conditions are Check SI ACTUATED degrading due to 21 B SGTR. If crew CNMT Pressure - > 5PSIG ATC reports SI status, manually actuates SI.

transitions to ES-O.l at this time, they PZR Pressure - < 1860 PSIG will be required to manually actuate SI SO Steam Pressure - < 500 PSIG and return here. This drill assumes SI is actuated at this time and the crew SI actuated on low PZR pressure.

continues with E-O.

E-O Immediate Actions completed.

SRO directs RO to secure 21B RCP due to high vibrationlsealleakoff trouble.

21B RCP secured. ATC secures 21B RCP.

Alert Plant Personnel ATC/BOP sound Standby Alarm, announce reactor trip and safety injection.

Leak collection filtered exhaust fan status SAT. Crew verifies leak collection filtered exhaust fan 2HVS-FN204A or B running.

BVPS - 2 Scenario 2, Rev AG 15 of 25

BEAVER VALLI:: T POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Verify SI Status ATC verifies SI System status.

2CHS*P21A & 2CHS*P21B running.

HHSI flow indicated on 2SIS-FI943 Both LHSl pumps running.

Verify AFW Status BOP verifies 2FWE*P23A & B both running 2FWE*P22 steam supply valves all open AFW Throttle valves all full open And total AFW flow is > 340 gpm.

SRO directs an operator verify automatic actions by performing Attachment A-O.II when time permits.

Attachment AwO.ll included with List of Attachment A-O.ll Discrepancies:

scenario beginning on Pg 24. Operator assigned to perform Attachment A-O.II AIl Automatic actions of AwO.ll are SAT reports status of attachment to the SRO and any actions taken when completed.

RCS temperature trending to 547°F. ATC reports Tavg status, SRO directs crew to control steam/feed flow as necessary to achieve RCPs OPERATING - MONITOR Tavg desired status.

RCPs STOPPED - MONITOR Teold Check CIB - NOT ACTUATED ATe checks Recirc Spray Pump status, CIB NOT actuated, Recirc spray pumps not running.

Recire Spray HXs SERVICE WATER FLOW TOALL4HXs Check Recire Spray Pumps - ANY RUNNING Check Recirc Spray Pumps - ALL RUNNING Check Recire Spray Pumps NOT CAVITATING BVPS - 2 Scenario 2, Rev AG 16 of 25

BEAVER VALLEy POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 I* INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE PORVs - CLOSED ATC verifies PZR isolated.

Spray Valves - CLOSED Safety relief valves - (PSMS Detailed Data Page 1)

-CLOSED Check PRT conditions - CONSISTENT WITH EXPECTED VALUES Power to at least one block valve - AVAILABLE Block valves - AT LEAST ONE OPEN 21B RCP previously secured. ATC checks ifRCPs should be stopped.

21A & 21C RCPs running.

CCP flow normal.

Pressures in all SOs - ANY DROPPINO IN AN BOP determines no SOs are faulted.*

UNCONTROLLED MANNER OR ANY SO COMPLETELY DEPRESSURIZED 21B SO level rising in an uncontrolled manner. SRO directs operator to check if SO tubes are Secondary rad monitors not consistent with pre intact.

event levels. BOP determines that the 21B SO level is rising in an uncontrolled manner.

Crew transitions to E-3. SRO makes transition to E-3 and informs crew.

SRO directs STA to monitor status trees.

BVPS - 2 Scenario 2, Rev AG 17 of 25

BEAVER VALLEY POWER STATION 112 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Control room habitability system not required. BOP verifies control room habitability.

21B RCP previously secured. ATCIBOP checks if RCPs should be stopped, 21A & 21C RCPs running. determine 21A & 21C RCPs to remain running.

RCS Highest SG Delta Pressure >205 psid CCP flow normal.

CRITICAL TASK 21 B SG level rising in an uncontrolled manner. Crew identifies SG 21B as the ruptured SG.

E-3.A - Crew isolates feed flow into Secondary rad monitors not consistent with pre and steam flow from the ruptured event levels.

SG and directs operator to close isolations valve(s) operated from outside of the control room before a transition to ECA-3.1 occurs.

Crew isolates flow from ruptured SG.

Adjust ruptured SG atmospheric steam dump controller setpoint to 100% and verify Crew notes that 2SYS*PCYI0IB was previously 2SYS*PCY101B closed. isolated.

ATC verifies 2SYS*HCY104 closed IRF LOA-MSSOIO 0 VerifY closed 21B SG steam supply to 2SYS Crew dispatches an operator to close 2SYS*28 HCYI04,2SYS*28.

ROLEPLAY:

NotifY crew that 2SYS*28 closed when requested.

BVPS - 2 Scenario 2, Rev AG 18 of 25

BEAVER VALLEy POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Isolate 2IB SG steam supply to 2FWE*P22 BOP verifies both motor driven AFW pumps nmmng.

BOP closes 2MSS*SOV105B and E Verify Blowdown and Steamline drains isolated ATC verifies 2BDG*AOVIOOBl is closed ATC verifies 2SDS*AOVIllBI is closed VLV-MSSOS7A (pre-loaded) 2SDS*AOV129A, Residual Heat Release Piping BOP verifies 2SDS*AOV129A is not closed.

Drain Isolation Valve - failed open BOP identifies that 2SDS* AOVI29A is failed open, and won't close from VB-C control switch.

Reports to SRO and closes 2SDS*AOVI29B.

Closes Ruptured SG main steam lines isolation and bypass valves. BOP closes 2MSS* AOVlOIB and verifies 2MSS*AOVI02B is closed.

21 B SG narrow range level greater than 12% (31 % BOP checks ruptured SG level.

adverse). When NR level is>12%, BOP isolates feed flow to 21B SG by closing 2FWE*HCVlOOC & D.

Feed Water Isolation verified BOP confirms FWI was previously verified using Attachment A-O.II.

Ruptured SG pressure> 240 psig. BOP verifies ruptured SG pressure> 240 psig.

BVPS - 2 Scenario 2. Rev AG 19 of 25

BEAVER VALLE: 1 POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GU/DEUNES PLANT STATUS OR RESPONSE EXPECTED STlJDENT RESPON-sE-- 1 CRITICAL TASK Based on ruptured SG pressure. SRO determines target temperature for cooldown, E-3.B - Crew establishes/maintains 1000 - 1084 = 505°P (480°F). uses NORMAL containment parameters.

an RCS temperature so that 900 - 999 = 492°P (467°P).

transition from E-3 does not occur because the RCS temperature is in either of the following conditions:

Too high to maintain minimum required subcooling for subsequent RCS depressurization, OR below the RCS temperature that causes a red or orange path challenge to Subcriticality or Integrity CSF.

ATC blocks low steamline pressure SI when PRZR pressure is less than 2000 psig.

Steam dump is available, Max rate cooldown. BOP attempts to dump steam at maximum rate using condenser steam dumps in steam pressure Mode. Ifnot already in steam pressure mode, BOP Steam dumps fail closed Condenser steam dumps fail closed, does so now.

CNH-PCS07A BOP determines that the condenser steam dumps have failed closed and reports to SRO.

SRO directs BOP to use the 21A and 21C ADV's to initiate max rate cooldown.

STA monitors thermocouples.

BVPS - 2 Scenario 2, Rev AG 20 of 25

BEAVERVALLE:r POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL-GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE BOP stops cooldown when core exit TCs < target temperature.

BOP places 21A & 21C atmospheric dump valve controllers in auto with pot setting corresponding to current intact SO pressure.

Intact SO levels> 12% (31 % adverse). BOP controls intact SO feed flow as required (340 gpm min) to achieve/maintain levels between 26%

and 50%.

Power to PORVs & block valves SAT. ATC verifies PORVlblock valve conditions as PORVs closed, not leaking. expected.

PORVlblock alignment SAT.

Auto SI blocked A 12-1 C lit. ATC resets SI (both trains).

SI signal A12-1D NOT lit.

Both trains of CIA reset. ATC resets CIA and CIB (both trains).

CIB not actuated.

Station air available. BOP verifies/reports status of station air system.

Instrument air established to CNMT. Crew establishes instrument air to CNMT.

BOP verifies 2IAC-MOV131 - open.

BOP opens 2IAC-MOV130.

BOP verifies Instrument air header pressure> 85 psig on VB-C.

RCS pressure> 225 psig (250 psig adverse). A TC verifies RCS pressure> 225 psig and stable, LHSI pumps stopped, in auto. stops LHSI pumps and places them in auto.

BVPS - 2 Scenario 2, Rev AG 21 of 25

BEAVER VALLI:: r POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES I. . . PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Ruptured SG pressure stable. BOP verifies ruptured SG pressure stable.

Subcooling > 61°F (79°F adverse). Crew verifies subcooling SAT at >61 OF.

CRITICAL TASK Depressurize RCS to minimize break flaw and ATC depressurizes RCS to minimize break flow E-3.C -Crew depressurizes RCS to refill PRZR and refill PRZR by; meet SI termination criteria before Verifying 21A and 21C RCPS both running.

water release from the ruptured SG Opening both pzr spray valves, 2RCS*PCV455A safety or atmospheric relief valve. and 2RCS*PCV455B.

Opens one PORV Verifies RCS pressure is reducing.

Depressurization Termination ATC closes the PORV and spray valves when RCS pressure is < ruptured SG pressure AND PRZR level is > 17%.

Verify PORV closed. ATC verifies RCS pressure rising.

Check if SI Flaw should be terminated. ATC verifies RCS subcooling > 41°F.

BOP verifies secondary heat sink, total AFW flow

> 340 gpm or one intact SG NR level> 12%

ATC verifies RCS pressure is stable or rising.

ATC verifies PRZR level is > 17%.

SRO determines that above conditions support termination of SI.

BVPS - 2 Scenario 2, Rev AG 22 of 25

BEAVERVALLEr POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Terminate SI flow. SRO directs ATC to stop all but one charging pumps.

ATC secures all but one charging pumps.

SRO directs ATC to close 2SIS*MOV867 A, B, C, D.

ATC closes 2SIS*MOV867A, B, C, D from BB-A.

Terminate scenario when HHSI is isolated in E-3.

Classify Event:

ALERT due to Tab 1.2.4, LOSS of RCS Barrier, Primary to Secondary Leak.

BVPS - 2 Scenario 2, Rev AG 23 of 25

BEAVER VALLEY POWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of SRO directs an operator to perform Attachment A Automatic Actions' performed as time 0.11 as time & manpower permit

& manpower permit Diesel generators BOTH RUNNING Check both EDGs running Ensure Reheat Steam Isolation Verify 2MSS-MOVIOOA and B closed Depress Reheater Controller RESET push button CNMT pressure GREATER THAN 7 PSIG Check ifMSLI is required OR SG Steam Pressure - LESS THAN 500 PSIG If not required, go to step 4 OR Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIT Verify steamline isolation Step 4 Open [2CCS-AOV118] Domestic Water to Station Establish Domestic Water System Cooling to Air Compressor Station Air Compressors At least one Station Air Compressor - RUNNING Start 1 Station Air Compressor as required CCP pumps - AT LEAST 1 RUNNING Check CCP Pump status

[2NME-NR45] Nuclear Recorder selected to Align neutron flux monitoring for shutdown operable source and intermediate range displays BVPS - 2 Scenario 2, Rev AG 24 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE CNMT pressure - HAS REMAINED LESS THAN Check CIB status 11 PSIG IF NOT Actuate CIB if required Manually initiate CIB - BOTH SWITCHES FOR BOTH TRAINS Manually align equipment as required All RCPs - STOPPED Stop ALL RCPs BV-1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps - 2 RUNNING Verify Service Water System in service Service Water Header Pressure GREATER THAN 55 PSIG SWS Seal Water Pressure - NOT LOW

[2HCS*SOVlOOAl, BI] - CNMT Sampleamber Verify both CNMT hydrogen analyzers running light-LIT All Red SIS Marks - LIT Verify ESF Equipment status - Start/align All Orange CIA Marks - LIT equipment as required All Green FWI Marks LIT Power available to both Emergency AC Busses Verify power to both AC Emergency busses Restore power as required Attachment A-O.ll - COMPLETE Report any discrepancies to SRO BVPS - 2 Scenario 2, Rev AG 25 of 25

Appendix D Scenario Outline Form ES -D-1 Facility: FENOC BVPS Unit 2 Scenario No.: J. Op Test No.: 2LOT7NRC Examiners: Candidates: SRO ATC BOP Initial IC-213 MOL, 100 % power Equ Xe, Rods Bank D @ 230 steps, Res Boron - 883 PPM, Conditions: Condensate Polishing Air Compressor - OOS.

Turnover: Maintain current plant conditions Critical Tasks: FR-S.1.A, Crew isolates the main turbine from the SG's FR-S.1.C, Crew inserts negative reactivity into the core by inserting RCCAs E-2.A, Crew isolates/directs isolation of faulted SG Event Malf. No. Event Type Event Description No.

1 XMT-MSS043A I(ALL) 2MSS*PT447 fails LOW, Rods Auto insert, Rx power rises SROT.S. due to cold Feedwater, Power reduction required.

2 R(ATC) Emergency Power reduction N(BOP/SRO) 3 XMT-RCS030A I(ATC/SRO) 2RCS*PT444 drifts HIGH, Pzr pressure decreases, manual SROT.S. control of pzr pressure required.

4 FLX-CFW31 M(ALL) 4500 gpm Feedwater leak inside cnrnt on "A" S/G 5 PPLOlA PPLOIB M(ALL) ATWS - Failure of auto/manual Rx trip 6 EHC03B C(BOP/SRO) Incomplete turbine trip, requires manual Steamline isolation EHCOIB actuation 7 VLV-MSS003A C(BOP/SRO) Auto MSLI Isolation actuation failure with 2MSS-AOV101A PPLlOA PPLlOB failing to close on a manual MSLI actuation, manual isolation required.

8 (N)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe FaCSimile Rev AG

Appendix D Scenario Outline Form ES-D-1 The crew will assume the shift at 100% power, Equilibrium MOL conditions with instructions to maintain lrrent power leveL 2MSS*PT447 will fail low, this will cause 2CNM-AOVIOO to open resulting in an overpower condition, causing the control rods to insert. The crew will respond by performing an Emergency Shutdown IA W AOP 2.51.1. Once the overpower condition has been corrected, 20M-24.4.IF, attachment 5 will be implemented to respond to 2MSS*PT447 failure. The SRO will evaluate TS 3.3.1 applicability and initiate required actions.

When the plant has stabilized, 2RCS*PT444 will drift high, requiring use of20M-6.4.IF, Attachment 2, the ATe will be required to manually control Res pressure. The SRO will evaluate TS 3.4.1 applicability.

A 4500 gpm Feedwater leak on the "A" loop inside containment will begin to ramp in, 1st indication of leak will be containment sump pumpout and Incore sump alarms. Based upon the sump alarms, the crew may enter AOP 2.6.7 to diagnose leak location. Feed flow to the "A" S/G will increase, however, S/G level will begin to drop ..

Level will continue to drop to the Reactor trip setpoint, however, Auto and Manual Reactor trips have been inhibited. When the crew recognizes a reactor trip is necessary a manual reactor trip will be directed by the SRO and E-O will be entered.

When it is recognized that the reactor will not trip, the SRO will direct entry into FR-S.l, this will be complicated by TV -2 and GV -2 sticking open on a turbine trip. An automatic MSLI actuation is inhibited requiring the BOP to manually actuate a MSLI, this is further complicated by 2MSS-AOVIOIA failing to automatically close on the manual MSLI actuation, which will require manual closure. The ATe will be

'1serting control rods and initiating emergency boration. An operator will be dispatched to locally trip the eactor, which will occur 2 minutes after being dispatched, at which time the crew will transition back to E-O.

The crew will identify the "A" S/G as faulted and transition to E-2 to isolate.

When the crew has isolated the "A" S/G, in E-2, the drill will be terminated.

Expected Procedure flow path is E-O - FR-S.1 - E-O- E-2 NUREG-1 021. Revision 9 Supplement 1 FENoe Facsimile Rev AG

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 100 % Power, CBD = 230, EQU XE MOL, 883 PPM Boron, IC-213 ADDITIONAL LINEUP CHANGES STICKERS YOND MARKINGS 2SAS-C22 in PTL YCTonCS None EQUIPMENT STATUS DATErrIME OOS TECHNICAL SPECIFICATION(S) 2SAS-C22 OOS 2 days ago None SIDFT TURNOVER INFORMATION

1. 100 % Power, CBD = 230, EQU XE MOL, 883 PPM Boron

2. Protected Train is Train "B"

3. Maintain steady state power level.

4. 2SAS-C22, Condensate Polishing Air Compressor OOS for overhaul.

SCENARIO SUPPORT MATERIAL REQUIRED

1. Reactivity plan placard for MOL

2. Placard for 2FWE*P22 position stating 2FWE*P22 is aligned to "A" header

3. Place plaque on wall for Protected Train "B" BVPS - 2 Scenario 3, Rev AG 1 of 19

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIO-N-AL -=-G~U=ID-----:E--Ll:-:-CN-E--:-"S---'-----P-LA-N-T-S-T-A-T-U-S-O-R-R-E-S-P-o-N-sE-----.-------=E,---,X,-p-EC--T-E-D-s---:::T~U-:-:-D-E-----N=T--R-,-:-,-E-=-SP=-O-::-cNSE Initialize IC Set 213, and establish Reactor plant at 100 % Power, MOL, equilibrium initial plant conditions. conditions, RCS Boron 883 PPM, CBD 230 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the drill Setup section of the HTML File for this drill:

TRGSET 1 'JPPLP4(1)' Set trigger 1 on Reactor Trip IMF PPLOIA (0 0) 1 Set ATWS condition TRN "A" IMF PPLOIB (0 0) 1 Set ATWS condition TRN "B" IMF EHC03B (00) 1000 100 TV 2 stuck open TRGSET 2 'JPPLASO(I)' Set trigger 2 on Turbine Trip (auto stop oil low)

IMF EHCOIB (2 0) 74 0 ASIS GV 2 stuck in pre-trip position IMF PPLI0A (0 0) TRN "A" AUTO MSLI inhibited IMF PPLI0B (0 0) TRN "B" AUTO MSLI inhibited IMF VLV-MSS003A (0 0) 100 2MSS-AOVlOIA failed to auto close on MSLI TRGSET 3 'XC2I027C = l' Set trigger 3 on manual close attempt with TRN "A" 2MSS-AOVIOIA CS TRG 3 'DMF VL V-MSS003A' Delete MALF preventing 2MSS-AOVIOIA closure.

TRGSET 4 'XC2I028C = l' Set trigger 4 on manual close attempt with TRN "B" 2MSS-AOVlOIA CS TRG 4 'DMF VLV-MSS003A' Delete MALF preventing 2MSS-AOVIOIA closure.

IMF PPL02A (30 120) Train A trip BKR open IMF PPL02B (30 130) Train B trip BKR open IRF LOA-CRF007 (30 140) 1 Trip A rod drive MG set IRF LOA-CRF008 (30 150) 1 Trip B rod drive MG set BVPS - 2 Scenario 3, Rev AG 2 of 19

BEAVERVALLE'v POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Assign shift positions SRO:_ _ _ _ _ _ _ __

ATC:_ _ _ _ _ _ _ __

BOP:- - - - - - - - -

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless it operators. needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 3, Rev AG 3 of 19

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

~~INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENTS 1 &2:

2MSS*PT447 fails LOW requires Emergency Power Reduction IMF XMT*MSS043A (0 0) 030 ASIS IMMEDIATE PLANT RESPONSE:

Rods begin stepping inward Automatically ATC observes Inappropriate Rod Movement and A4-3C, - 'TAVG DEVIATION FROM TREF' performs Immediate Action Step of AOP 2.1.3.

LIT ATC determines No Load Rejection is in progress A6-12G, - 'AMSAC TROUBLE' - LIT and places Rod Control into Manual to stop rod movement.

Followed by; A6-5E, - 'CONDENSATE PUMP DISCH/SUCT PRESSURE LOW' - LIT A6-5D, - 'CONDENSATE PUMP AUTO START/AUTO STOP' - LIT 2CNM-P21A Auto Starts Red light illuminated 2CNM-AOVI00 opens - Red light illuminated SRO implements AOP 2.1.3 Checks First Stage Pressure indication BOP identifies that 2MSS-PT447 is failing low.

Loop delta T's exceed 100% power indication Crew determines that Reactor Power is exceeding 100%

SRO enters AOP 2.51.1 and directs an emergency power reduction.

BVPS - 2 Scenario 3, Rev AG 4 of 19

BEAVER VALLEy POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: A TC initiates Emergency power reduction by 2CNM-AOVIOO will automatically close 4 minutes Depressing 1st stage in pushbutton, after opening. Setting EHC setter to -5% below current power lvI, Setting load rate thumbwheel to 5%/min Depressing GO pushbutton ATC monitors Power level less than 100% and not rising. If necessary, SRO directs BOP to reduce additional turbine load.

ATC controls RCS Tavg via use of Control Rods manual andlor Boration of the RCS.

When power level is <100%, SRO implements 20M-24.4.IF BOP selects 2MSS*PT446 by placing "Main Turb First Stage Press Sensor Select" CS to PM446 position on BB-C SRO directs BOP to remove the Arming signal to the condenser steam dumps by placing the "Steam Dump Control Mode Selector Switch" on BB-C to the RESET position.

Steam dump arming signal reset - stm dumps close.

BOP verifies 2CNM-AOVlOO closed BOP places Steam Dumps in Steam Pressure Mode of Operation with a control Setpoint of 1005 psig lAW SRO Direction per 20M-24.4.IF.

BVPS - 2 Scenario 3, Rev AG 5 of 19

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE SRO refers to TS 3.3.1, Function 17.f, Condition P, verify P-13 interlock is in it's required State w/in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ATC determines A12-IF, 'P-13 PERMISSIVE' is lit.

When the Crew has stabilized the plant at less than 100% power and the SRO has determined TS applicability, Proceed with next event at LE discretion EVENT 3:

2RCS-PT444 drifts high RCS Pressure control input PT IMF XMT-RCS030A (0 0) 2500 90 IMMEDIATE PLANT RESPONSE:

A4-1D, - 'PRESSURIZER CONTROL ATC notes/verifies alarms, informs SRO/Crew of PRESSURE HIGHlLOW' - LIT apparent instrument failure of2RCS*PT444.

A4-1E, - 'PRESSURIZER CONTROL PRESS DEVIATION HIGHlLOW' - LIT A4-2F, - 'PRESSURE RELIEF BLOCK' - LIT ATC takes manual control of Pressurizer pressure A2-4B, - 'REACTOR COOLANT SYSTEM control to restore pressure.

SUBCOOLING OFF NORMAL' - LIT BVPS - 2 Scenario 3, Rev AG 6 of 19

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 f INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE SRO enters 20M-6.4.IF Attachment 2 and directs ATC to place the CS for 2RCS*PCV455C to close.

SRO directs ATC to manually control pressurizer spray valves and heaters as necessary to restore/control RCS pressure.

ATC reports to SRO that Pressurizer pressure reduced low enough to require entry into DNB TS.

Per TS 3.4.1, SRO identifies that pressure must be restored within limit w/in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ATC continues to manually control Pressurizer pressure for the remainder of the scenario.

When ATC has stabilized pressure and SRO has addressed DNB TS.

Continue with next event at LE discretion BVPS - 2 Scenario 3, Rev AG 7 of 19

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7

[ INSTRU-CTfoNAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 4:

4500 GPM Feedwater leak, "A" S/G inside enmt IMF FLX-CFW31 (0 0) 4500600 0 IMMEDIATE PLANT RESPONSE:

IMFCRFOIA Cnmt Sump Alarms, A2-2B, - 'UNIDENTIFIED LEAKAGE SYSTEM TROUBLE' - LIT Al-2G, - 'INCORE INSTRUMENT ATC notes cnmt sump alarms and informs SRO.

ROOMlCNMT SUMP LEVEL HIGHNALVE BOP refers to ARP for A2-2B, checks CCP surge NOT RESET' - LIT tank levels stable and reports that ARP directs entry Cnmt Dewpoints rising into AOP 2.6.7.

NOTE: SRO enters AOP 2.6.7 It not likely that AOP 2.6.7 actions will be taken due to the degrading S/G parameters that will become evident.

A6-9E, - 'SG 21A LEVEL DEVIATION FROM BOP acknowledges alarm and informs SRO.

SETPOINT' - LIT "A" SG level dropping wi increasing Feedwater BOP recognizes and informs the crew, that the A flow. SG level is dropping with an increase in Feedwater flow.

A2-3B, - 'UNIDENTIFIED LEAKAGE FLOW ATC informs SRO that another Cnmt Sump alarm GREATER THAN 60 GALLONS' - LIT has annunciated.

BVPS - 2 Scenario 3, Rev AG 8 of 19

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE A6-9D, - 'SG 21A LEVEL HIGHlLOW' -LIT BOP reports to the crew that the A S/G low level 21A S/G level continues to drop with an increasing alarm has annunciated and that level continues to Feedwater flow rate drop.

SRO directs the crew to perform a manual reactor trip and enter E-O EVENTS 5 -7: (pre-loaded)

IMMEDIATE PLANT RESPONSE:

ATWS, Incomplete Turb Trip, MSLI Reactor will NOT trip from the control room Actuation failure Crew enters E-O, performs Crew performs IMAs of E-O.

immediate operator actions.

A5-6D, - 'TURBINE TRIP DUE TO REACTOR ATC verifies reactor is NOT tripped.

TRIP' - NOT LIT Power range indication - NOT LESS THAN 5% ATC attempts manual reactor trip from BB-B and Neutron flux - NOT DROPPING BB-A, reports reactor has NOT tripped US transitions to FR-S.l Reactor IS NOT tripped SRO/Crew determine FR-S.l entry conditions met, transitions to FR-S.l Step 1 Crew performs IMAs ofFR-S.l BVPS - 2 Scenario 3, Rev AG 9 of 19

BEAVER VALLE 'I' POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE IMF EHC03B (0 0) 100 0 100 Turbine trip BOP manually trips the turbine by depressing both TRGSET 2 'JPPLASO(l)' Turbine Trip push buttons on BB-C.

IMF EHCOIB (2 0) 74 0 ASIS IMF PPLI0A (0 0) BOP identifies that TV-2 and GV-2 have not closed IMF PPLI0B (0 0) and the turbine has not tripped.

IMF VLV-MSS003A (00) 100 TRGSET 3 'XC2I027C = l' BOP manually initiates Main Steam Line Isolation.

TRG 3 'DMF VL V-MSS003A' TRGSET 4 'XC2I028C = l' BOP identifies that 2MSS-AOV101A did not close TRG 4 'DMF VLV-MSS003A' and manually closes valve from BB-C.

(all above commands pre-loaded)

CRITICAL TASK FR-S.1.A Crew isolates the main turbine from the SGs before WR SG level is less than 10%

CRITICAL TASK ATC identifies that the control rods are not inserting in Auto, selects MANUAL and begins FR-S.l.C Crew inserts negative Control Rods are inserting in Manual inserting Control Rods.

reactivity into the core by inserting RCCAs before completing the immediate action steps ofFR-S.1.

Verify AFW Status BOP verifies 2FWE*P23A & B both running 2FWE*P22 steam supply valves all open AFW Throttle valves all full open Crew initiates Emergency Boration ATC verifies at least 1 Charging Pump is running and SI is actuated with HHSI flow indicated.

ATC verifies PRZR pressure is < 2330 psig.

BVPS - 2 Scenario 3, Rev AG 10 of 19

BEAVERVALLEr POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE PZR Pressure < 2330 PSIG ATC checks PZR pres < 2330 PSIG Plant personnel alerted of ATWS Crew alerts plant personnel by sounding the standby alarm and announcing Unit 2 reactor trip without SCRAM.

ROLEPLAY: Crew notifies and dispatches a field operator to locally trip the Unit 2 reactor by opening the When a crew member directs a field reactor trip breakers or open the rod drive MG sets operator to locally trip the Unit 2 output breakers.

Reactor, insert TRG! 30, this will initiate a timed sequence for the operator to get to the rx trip breakerslMG sets and open them.

Report to the control room when the Actions have been completed.

Verify turbine tripped and reheat steam isolated. BOP reports that turbine is not completely TRIPPED, previously required a MSLI.

Verifies 2MSS-MOV 1OOA and B closed Depresses Reheater Controller RESET push button Check SI signal status ATC determines SI is actuated.

SRO directs a crew member to complete the First NINE steps of E-O when time and manpower permit.

BVPS - 2 Scenario 3, Rev AG 11 of 19

BEAVER VALLEy POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES =r=. pLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: Check if reactor is subcritical ATC verifies; Scenario assumes the reactor has been All power range channels indicate <5%

locally tripped by this time Both IR NI channels indicate a negative SUR Safety Injection actuated - Emergency Boration is not required.

SRO returns to E-O step 1 Crew enters E-O, performs immediate Crew performs lMAs ofE-O.

operator actions.

A5-6D, - ' TURBINE TRIP DUE TO REACTOR ATC verifies reactor tripped.

TRIP' - LIT Power range indication - LESS THAN 5%

Neutron flux - DROPPING Throttle Valves - ALL CLOSED BOP previously verified that the turbine did not trip OR and initiated MSLI.

Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency Buses.

ENERGIZED Check SI ACTUATED ATC checks S1 status CNMT Pressure - > 5PSIG PZR Pressure - < 1860 PSIG SG Steam Pressure - < 500 PS1G CREW DETERMINES SI REQUIRED Crew continues E-O Manually actuate SI (both trains) ATC manually actuates SI, both trains.

E-O Immediate Actions completed.

BVPS - 2 Scenario 3, Rev AG 12 of 19

BEAVER VALLI:: f POWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Alert Plant Personnel ATCIBOP sound Standby Alarm, announce reactor trip and safety injection.

Leak collection filtered exhaust fan status SAT. Crew verifies leak collection filtered exhaust fan 2HVS-FN204A or B running.

Verify SI Status ATC verifies SI System status.

2CHS*P21A & 2CHS*P21B running.

HHSI flow indicated on 2SIS-FI943 Both LHSI pumps running.

Verify AFW Status BOP verifies 2FWE*P23A & B both running 2FWE*P22 steam supply valves all open AFW Throttle valves all full open And total AFW flow is > 340 gpm.

SRO directs an operator verify automatic actions by performing Attachment A-O.II when time permits.

Attachment A-O.ll included with List of Attachment A-O.ll Discrepancies:

scenario beginning on Pg 18. Operator assigned to perform Attachment A-O.II MANUAL MSLI was required on initial trip reports status of attachment to the SRO and any 2MSS-AOVIOIA failed to close on MSLI signal. actions taken when completed.

RCS temperature trending to 547°F. ATC reports Tavg status, SRO directs crew to control steam/feed flow as necessary to achieve RCPs OPERATING - MONITOR Tavg desired status.

RCPs STOPPED - MONITOR Tcold BVPS - 2 Scenario 3, Rev AG 13 of 19

SEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Cheek CIB - NOT ACTUATED ATC checks Recire Spray Pump status, CIB NOT actuated, Recire spray pumps not running.

Recire Spray HXs - SERVICE WATER FLOW TOALL4HXs Check Recire Spray Pumps - ANY RUNNING Check Recirc Spray Pumps - ALL RUNNING Check Recirc Spray Pumps NOT CAVITATING PORVs - CLOSED(not leaking). ATC verifies PZR isolated.

Spray Valves CLOSED Safety relief valves (PSMS Detailed Data Page 1)

CLOSED Check PRT conditions - CONSISTENT WITH EXPECTED VALUES Power to at least one block valve - AVAILABLE Block valves - AT LEAST ONE OPEN SVPS - 2 Scenario 3, Rev AG 14 of 19

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE DIP between RCS pressure and highest SG pressure ATC checks ifRCPs should be stopped LESS THAN 205 PSID [220 PSID ADVERSE CNMT] ATC detennines RCP DIP trip criteria NOT met.

AND RCPs remain in service.

HHSI Flow-INDICATED Stop All RCPs Pressures in all SGs - ANY DROPPING IN AN BOP checks if any SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED "A" SG is faulted SRO determines transition to E-2 is necessary.

Crew transitions to E-2 STEP 1 SRO directs transition to E-2 As U-I operator, when requested, Check CREVS actuated: BOP verifies CREVS actuated, requests Unit 1 report proper CREVS actuation. Control room air intake and exhaust dampers CREVS verification.

CLOSED

[2HVC*FN24IA(B)] - ONE RUNNING Request UI operator to verify CREVS actuation Commence Control Room ventilation actions IAW ATT A-2.4 BVPS - 2 Scenario 3, Rev AG 15 of 19

BEAVER VALLEy POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check All yellow SLI marks - LIT Crew verifies steam line isolation.

Check all SG pressures - ANY STABLE OR BOP checks for any non-faulted SO, determines RISING that "B" and "C" SO's are not faulted.

Check all SGs pressure - ANY SG PRESSURE BOP identifies "A" SO as faulted.

DROPPING IN AN UNCONTROLLED MANOR OR ANY SG COMPLETELY DEPRESSURIZED "A" SG pressure dropping uncontrollably.

Check FWI - PREVIOUSLY VERIFIED Crew verifies faulted SO (A) isolated 2FWS*HYV-157A closed BOP verifies "A" SO CNMT isolation vlv closed.

(mo - close 2FWS-MOV154A, 155A) 2FWS*FCV478 closed. BOP verifies "A" MFRV closed.

(mo - close 2FWS-MOV154A) 2FWS*FW479 closed. BOP verifies "A" BPFRV closed.

(mo - close 2FWS-MOV155A) 2FWE*HCVIOOE, F closed. BOP closes 2FWE*HCVIOOE, F.

Check Residual Heat Release valve - CLOSED BOP verifies 2SVS*HCV104 closed.

IRF LOA-MSS009 (0 0) 0 Check Residual Heat Release Valve from faulted Crew dispatches an operator to close 2SVS*27.

SG - PREVIOUSLY ISOLATED:

SO 21A [2SVS*27]

BVPS - 2 Scenario 3, Rev AG 16 of 19

BEAVER VALLc.Y POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELlNE~:'--T PLANT STATUS OR RESPONSE - - =r. EXPECTED STUDENT RESPONSE IF REQUESTED: Close Turbine driven AFW pump steam supply BOP closes [2MSS*SOVI05A,D]

isolation valves from faulted SO:

IRF LOA-AFW025 (0 0) 0 [2MSS*SOVI05A,D]

To close [2MSS*15] (mo - close [2MSS*15]

IF REQUESTED: Close atmospheric steam dump on faulted SO BOP closes "A" SO atmospheric steam dump

[2SVS*PCVlOIA] [2SVS*PCVlOIA]

IRF LOA-MSS016 (0 0) 0 (mo - close [2SVS*23]

To close [2SVS*23]

Verify SO blowdown isolation valve from faulted BOP verifies SO blowdown isolated from "A" SO.

SO CLOSED:

[2BDO*AOVI OOAI] OR

[2BDO*AOV 10 1AI]

CRITICAL TASK Close [2SSR*AOV117A] SO blowdown sample BOP isolates SO blowdown sample from "A" SO E-2.A Crew isolates the faulted SG outside CNMT isolation valves and directs operator to close isolation (mo - close[2BDO*AOVI02Al,A2]

valve(s) operated from outside the control room before transition out of E-2.

Tenninate Drill upon completion of isolation of the faulted SO per E-2 Classify Event:

SITE AREA EMERGENCY due to Tab 2.3, Failure ofRx Protection.

BVPS - 2 Scenario 3, Rev AG 17 of 19

BEAVER VALLt:: ( POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Attachment A-O.II 'Verification of SRO directs operator to perfonn Attachment A Automatic Actions' perfonned as time 0.11 as time & manpower pennit

& manpower pennit Diesel generators - BOTH RUNNING Check both EDGs running CNMT pressure - GREATER THAN 7 PSIG Check if MSLI is required OR (MANUAL MSLI required on initial trip)

SG Steam Pressure - LESS THAN 500 PSIG If not required, go to step 4 OR Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIT Verify steamline isolation STEP 4 Open [2CCS-AOV118] Domestic Water to Station Establish Domestic Water System Cooling to Air Compressor Station Air Compressors At least one Station Air Compressor - RUNNING Start 1 Station Air Compressor as required CCP pumps - AT LEAST 1 RUNNING Check CCP Pump status

[2NME-NR45] Nuclear Recorder selected to Align neutron flux monitoring for shutdown operable source and intennediate range displays BVPS - 2 Scenario 3, Rev AG 18 of 19

BEAVER VALLt.. ( POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ -INSTRUCTIONAL GUIDELINES . --PLANTSTAtUS OR RESPONSE-*_** -C - EXPECTEDSfuDENT RESPONSE CNMT pressure - HAS REMAINED LESS THAN Check CIB status 11 PSIG IF NOT Actuate CIB if required Manually initiate CIB - BOTH SWITCHES FOR BOTH TRAINS Manually align equipment as required All RCPs - STOPPED Stop ALL RCPs BV-1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps - 2 RUNNING Verify Service Water System in service Service Water Header Pressure - GREATER THAN 55 PSIG SWS Seal Water Pressure - NOT LOW

[2HCS*SOVI00Al, Bl] - CNMT Sample amber Verify both CNMT hydrogen analyzers running light- LIT All Red SIS Marks - LIT Verify ESF Equipment status - Start/align All Orange CIA Marks - LIT equipment as required All Green FWI Marks - LIT Power available to both Emergency AC Busses Verify power to both AC Emergency busses Restore power as required Attachment A-O.ll COMPLETE Report any discrepancies to SMIUS BVPS - 2 Scenario 3, Rev AG 19 of 19

A~ppen d'IX 0 . 0 utrme S cenaflo Form ES 0 1 -

Facility: FENOC BVPS Unit 2 Scenario No.: ~ Op Test No.: 2LOT7NRC Examiners: Candidates: SRO ATC BOP Initial IC 214: Reactor power -E-6 amps, BOL, Equ. Xe Conditions, CB "D" @ 101 steps, RCS Conditions: boron - 1851 ppm, Condensate Polishing Air Compressor - OOS.

Turnover: Raise power to above the POAH (3-5%)

, Critical Tasks: E-1.C, Trip RCPs E-O.I, Manually Start HHSI Pump ECA-l.1.B, Makeup to RWST Event Malf. No. Event Type Event Description No.

1 R(ATC) Raise Reactor power to 3-5%

N(BOP/SRO) 2 2RSS-P21D, Recirculation Spray Pump Seal failure BST-CSS035 C(ATC/SRO) 2RSS-P2ID seal tank level low BST-CSS036 SROTS 2RSS-P21D seal tank level 10 10 3 FLX-CSS05 C(BOP/SRO) 500 gpm suction leak to the "A" Quench Spray Pump.

SROTS 4 PMP-CAS003 C(BOP/SRO) Station Air compressor Trip/auto start failure of standby I 5 FLX-CASIO C(ALL) Instrument Air Header leak - requires manual reactor trip 6 RCS02C M(ALL) 5000 gpm SBLOCA on Loop C upon reactor trip 7 BKR-HIV08 C(BOP/SRO) Inadvertent trip of2DF feeder brk on Rx trip.

DSGOIB 2-2 EDG Auto start failure with subsequent trip 8 PPL07A C(ATC/SRO) Standby HHSI pump fails to auto start (manual start required).

9 LOA-LOV072 C(ALL) Loss of2MCC-Ell, (Both Trains of Transfer to Cold Leg Recirculation are unavailable - ECA-l.1 entry required)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev AG

Appendix 0 Scenario Outline Form ES-O-1 The Crew will continue the reactor startup, raising reactor power to above the POAH, ~3%. The ATC operator vill withdraw control rods and observe startup rate while the BOP controls RCS temperature by manually adjusting 2SVS-HCVI04. The BOP also controls SO level by manually controlling the bypass feed reg valves.

After the Crew has raised power to above the POAH, Al-3H will annunciate due to a low level in the seal tank for 2RSS*P21D. Al-3H will reflash in 5 minutes due to the seal tank for 2RSS-P21D level being LO-LO which indicates a seal failure for 2RSS*P21D. lAW the ARP for AI-3H, the crew will dispatch an operator to fill the seal lAW 20M-13.4.F. The SRO will evaluate TS 3.5.2 & 3.6.7 A 500 gpm isolable leak develops on the suction line to 2QSS*P21A in South Safeguards. The South Safeguards sump Hi level annunciator will alarm followed by annunciator A6-lD due to a low level in the RWST, the crew will monitor RWST level and initiate actions to locate the leak and makeup to the RWST. The SRO will evaluate TS 3.5.4 (RWST level) and TS 3.6.6 for 2QSS*P21A when leak is located)

The running station air compressor will trip requiring manual start of the standby station air compressor.

A slowly developing Instrument Air leak will occur. The air leak will continue to worsen, requiring the crew to determine that a reactor trip is appropriate lAW AOP 2.34.1.

Upon the reactor trip the crew will enter E-O, a 5000 gpm SBLOCA will occur on Loop C. When the reactor trips, one of the 4kv tie breakers, between the "D" and "DF" buses will trip open, 2D1O. The automatic start of the 2-2 EDO will fail and requires the BOP to manually start the 2-2 EDO, it will trip 90 seconds after starting.

~ince the "B" CHSIHHSI pump was in service it will no longer be running, the "A" CHS/HHSI pump will

~quire the ATC to manually start it due to an automatic start failure. The crew will Transition to E-l based upon containment conditions when checking if the RCS is intact. 5 minutes after the reactor trip, the feeder breaker to 2MCC -Ell will trip When the crew performs EOP attachment A-0.6 to verify Cold Leg Recirculation capability, it will be determined that at least one train of recirculation capability cannot be verified requiring the SRO to transition to ECA-l.l. The crew will remain in ECA-l.I; after the crew has initiated actions to add makeup water to the RWST (step 9) the drill will be terminated.

Expected procedure flow path is E-O ~ E-l ~ ECA-1.1.

NUREG*1021. ReviSion 9 Supplement 1 FENoe Facsimile Rev AG

BEAVER VALLEY POWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 0% Power (~E-6 amps), CBD = 101, EQU XE BOL, 1851 PPM Boron, IC-214 ADDITIONAL LINEUP CHANGES STICKERS YOND MARKINGS 2SAS-C22 in PTL YCTonCS None EOUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION(S) 2SAS-C22 OOS 2 days ago None

--~ ............. -..--

SIDFT TURNOVER INFORMATION L 0 % Power (-E-6 amps), CBn = 101, CBC = 229, EQU XE BOL, 1851 PPM Boron

2. Protected Train is Train "B"

3. Raise power to above the POAH (3-5%) lAW 20M-50A.D, Reactor Startup from Mode 3 to Mode 2, Part C Temperature control is via 2SVS-HCV104, with bypass feed reg valves in manual.

4. 2SAS-C22, Condensate Polishing Air Compressor OOS for overhaul.

SCENARIO SUPPORT MATERIAL REQUIRED

1. Plant Startup reactivity plan, Critical with Bank D at 10lsteps.

2. Placard for 2FWE*P22 position stating 2FWE*P22 is aligned to "A" header

3. Place plaque on wall for Protected Train "B"

4. Plant startup procedure - 20M-50A.D completed up through Part B.

BVPS - 2 Scenario 4, Rev AG 1 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Initialize IC Set 214, and establish Reactor plant at 0% power (~E-6 amps), BOL, initial plant conditions. equilibrium conditions. RCS boron 1851 PPM, CBD = 101 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the drill Setup section of the HTML File for this drill:

TRGSET 1 'JPPLP4(1)' Set Trigger 1 on Reactor Trip IMF PPL07A (0 0) 0 Auto Start Failure of2CHS*P21A IMF BKR-mVOS (I 0) 0 ACB-2DIO trips on reactor trip IRF LOA-LOV072 (3 300) 0 Trip of ACB 2N-6C, MCC*2-Ell Feeder bkr IMF AS-6F-Y3510D (3 300) 0 A8-6F alarm for trip ofMCC*2-Ell Feeder bkr IMFDSGOIE Auto start inhibit, EDG 2-2 TRGSET 3 'ODSG02RM > 20' Set trigger 3 on EDG 2-2 start IMF DSGOIB (3 90) TRUE EDG 2-2 trip 90 seconds after manual start IMF RCS02C (I 0) 5000 5000 gpm SBLOCA, Loop "C" upon reactor trip IMF BST-CASOI3 (0 0) 1 2IAS-PSI06B, station air compressor autostart inhibit IMF BST-CASOIO (00) 1 2IAS-PS 108, stby diesel air compressor autostart inhibit IMF BST-CAS035 (2 0) 0 2RSS-LSI56D, RSS*P21D Seal Tk Ivi BELOW L0706D IMF BST-CAS036 (2 300) 0 2RSS-LS156DI RSS*P21D Seal Tk lvl LOLO L0707D BVPS - 2 Scenario 4, Rev AG 2 of 25

BEAVER VALLEY POWER STATION 112 ADM - 1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Assign shift positions SRO:_ _ _ _ _ _ _ __

ATC:

BOP:_ _ _ _ _ _ _ _ __

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless it operators. needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 4, Rev AG 30f25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 1:

Raise Reactor Power to 3-5% A TC withdraws Control rods to raise reactor power As control rods are withdrawn, reactor power rises being observant of 0.1 dpm procedural SUR limit.

and then RCS temperature rises as power increases.

BOP manually controls RCS temperature using 2SVS-HCVI04.

BOP controls SG levels using manual control of the Bypass Feed reg valves.

Proceed with next event at LE discretion EVENT 2:

2RSS*P21D Seal Trouble / Failure IMMEDIATE PLANT RESPONSE:

Al-3H, - 'RECIRC SPRAY SYSTEM TROUBLE' ATC responds with ARP which directs that Seal IMF BST-CAS035 (2 0) 0 - LIT, L0706D, BELOW System be filled lAW 20M-13.4.F.

IMF BST-CAS036 (2 300) 0 (pre-loaded) SRO dispatches an operator to fi1l2RSS*P21D seal lAW 20M-13.4.F, part D.

Initiate by actuating TRG! 2 5 MINUTES LATER:

REFLASHof: ATe reports that IA W ARP, Seal is to be filled.

AI-3H, - 'RECIRC SPRAY SYSTEM TROUBLE' (Fill procedure should be already working by now)

- LIT, L0707D, LOLO BVPS - 2 Scenario 4, Rev AG 40f25

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ~

ROLEPLAY:

5 minutes after being dispatched as SRO to review TS; field operator to fill the seal for TS 3.6.7, RSS Sys, Condition C, Restore in 72 hrs.

2RSS*P21D IA W 20M-13.4.F, Part D. TS 3.5 .2, ECCS, Condition A, Restore in 72 hrs.

Call in to the Control Room SRO and TS 3.6.1, CNMT, Condition A, Restore in 1 hr.

report that "you have completed steps 1 through 5 of20M-13.4.F, Part D, you ATC places the CS for 2RSS*P21D in PTL and can continue with step 6." closes 2RSS*MOV155D and 2RSS*MOV156D.

Field operator is notified to continue with Step 6.[.

Continue with next event at LE discretion BVPS - 2 Scenario 4, Rev AG 50f25

BEAVER VALLE)' POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 3:

IMMEDIATE PLANT RESPONSE: BOP responds with ARP which directs that 500 gpm leak on suction line to All-lOG, - 'SAFEGUARDS AREA SUMP someone be dispatched to investigate leakage into 2QSS*P21A. LEVEL HIGH' - LIT, (L2963D), SOUTH South Safeguards.

IMF FLX-CSS05 (0 0) 500 SRO dispatches field operator to investigate South Safeguards to identify leakage.

ROLEPLAY:

As field operator report in that there is a SRO reviews system VOND and determines that leak on the suction piping for leak can be isolated by closing 2QSS*2 and 2QSS*P21A upstream of 2QSS*MOVIOOA.

2QSS*MOVIOOA.

Crew isolates 2QSS*P21A by placing CS for 2QSS*P21A in PTL & closing 2QSS*MOVIOOA.

SRO directs field operator to close 2QSS*2.

SRO reviews TS 3.6.6 for 1 Train of Quench Spray, ROLEPLAY: Condition A, Restore in 72 hrs.

Insert command 'DMF FLX-CSS05' then as field operator report to SRO that you have closed 2QSS-2.

A6-ID, - 'REFUELING WATER STORAGE BOP reviews ARP; TANK LEVEL OFF NORMAL' - LIT, (L2966D) Verifies actual low level in the R WST.

Determines makeup to RWST is necessary.

Dispatches operator to initiate R WST makeup IAW 20M-7.4.0.

SRO reviews TS 3.5.4 for RWST volume.

Condition B, restore level within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

BVPS - 2 Scenario 4, Rev AG 6 of 25

BEAVER VALLE I POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Continue with next event at LE discretion EVENT 4:

Trip of2SAS-C21A IMMEDIATE PLANT RESPONSE:

A6-3D,* 'STATION AND CONDENSATE BOP determines 2SAS-C21A has tripped and IMF PMP*CAS003 (0 0) 1 POLISHING AIR SYSTEM TROUBLE' - LIT 2SAS*C21B has failed to start, reports to (Y6464D) SRO/Crew.

SRO directs the BOP to start 2SAS*C21B.

ROLEPLAY: BOP starts 2SAS*C21B.

As operator requested to investigate trip of 2SAS-C2 lA, report back that the air SRO notifies maintenance of trip of2SAS-C21A.

compressor has tripped with no apparent reason.

Continue with next event at LE discretion BVPS - 2 Scenario 4, Rev AG 7 of 25

BEAVER VALLEY POWER STATION 1/2-ADM-1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENTS:

IMMEDIATE PLANT RESPONSE:

Instrument Air Header Leak Numerous air system alarms annunciate A6-3D, - "STATION AND CONDENSATE BOP reports Air System alarms to the Crew/SRO.

IMF FLX-CASI0 (0 0) 1200 500 POLISHING AIR SYSTEM TROUBLE' - LIT (P081lD)

A6-3C, - ' STATION INSTRUMENT AIR RECEIVER TROUBLE' - LIT (P0810D) SRO determines AOP 2.34.1, "Loss of Station A6-3C, - 'STATION INSTRUMENT AIR Instrument Air" is applicable, enters and directs RECEIVER TROUBLE' - LIT (P0812D) actions of AOP.

A6-3C, - 'STATION INSTRUMENT AIR RECEIVER TROUBLE' - LIT (P0815D)

A6-3D, - 'STATION AND CONDENSATE POLISHING AIR SYSTEM TROUBLE' LIT (P0814D)

ATC sounds the Standby Alarm and announces "Loss of Station Instrument Air".

BVPS - 2 Scenario 4, Rev AG 8of25

BEAVER VALLEt POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: BOP verifies all available Station Air compressors 2SAS-C2IA previously tripped. are runrung.

2SAS-C21 B running 2IAS-C21 - Did not auto start Verifies 2SAS-C21B is running.

2SAS-C22 OOS on turnover.

BOP dispatches turbine operator to locally start the ROLEPLAY: Diesel Air compressor, (2IAS-C21).

As turbine operator dispatched to start 2IAS-C21, report back in 3 minutes that it appears as though the battery is dead, the Diesel Air compressor will not start.

ROLEPLAY: SRO dispatches operator to place the Instrument As operator dispatched to Bypass the Air Dryer Bypass filters in service and to isolate the Instrument air dryers, report back in 3 Instrument Air Dryers.

minutes that the Bypass filters are inservice and the Dryers are isolated.

Additionally, report that there is an instrument air leak downstream of 2IAS-I026, right at the header.

NOTE: Station instrument air pressure continues to drop. BOP checks for Reactor trip criteria, checks Continuous Action Step, requires Instrument air header pressure not < 55 psig, tripping the Reactor if pressure is <55 however there is a decreasing pressure trend.

pSlg.

BVPS - 2 Scenario 4, Rev AG 9 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE BOP checks Instrument Air header pressure is <86 pSlg.

BOP verifies 2SAS-AOVI05 is closed.

SRO continues attempts to restore station instrument air.

Station instrument air pressure drops to < 55 psig BOP reports to crew that Instrument Air pressure is

< 55 psig SRO directs the crew to Manually trip the reactor, perfonn Immediate Operator Action steps and report when ready to read.

BVPS - 2 Scenario 4, Rev AG 10 of 25

SEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 I n_uINSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENTS 6,7,8,9:

5000 gpm Loop C SBLOCA with inadvertent trip of 2D I 0 breaker, Auto start failure of 2-2 EDG with trip 90 seconds after loading, Loss of2MCC EllS minutes later.

TRGSET 1 'JPPLP4(1),

IMF PPL07A (0 0) 0 IMF BKR-illV08 (1 0) 0 IRF LOA-LOV072 (3 300) 0 IMF A8-6F-Y3510D (3 300) 0 IMFDSGOIE TRGSET 3 'ODSG02RM> 20' IMF DSGOIB (3 90) TRUE IMF RCS02C (1 0) 5000 (all preloaded)

Crew enters E-O, performs immediate Crew performs IMAs of E-O.

operator actions.

A5-6D, - 'TURBINE TRIP DUE TO REACTOR ATC verifies reactor trip.

TRIP' - LIT.

Power range indication - LESS THAN 5%

Neutron flux dropping.

SVPS - 2 Scenario 4, Rev AG 11 of 25

BEAVER VALLE::.. POWER STATION 1/2-ADM-1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE . - ]

Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN ROLEPLAY: AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency Buses.

As operator dispatched to 2-2 EDG, ENERGIZED report back that there is significant mechanical damage to the EDG, a hole is in the side of the diesel with parts laying on the floor.

Check SI - ACTUATED ATC checks SI status.

CNMT Pressure - > 5PSIG PZR Pressure - < 1860 PSIG SG Steam Pressure - < 500 PSIG CREW DETERMINES SI REQillRED Crew continues E-O Manually actuate SI (both trains) ATC manually actuates SI, both trains.

E-O Immediate Actions completed.

NOTE: Alert Plant Personnel A TCIBOP sound Standby Alarm, announce reactor Due to 2DF 4KV bus being de trip and safety injection.

energized, ALL train "B" components will be de-energized with positions unable to be verified.

Leak collection filtered exhaust fan status SAT. Crew verifies leak collection filtered exhaust fan 2HVS-FN204A or B running.

BVPS - 2 Scenario 4, Rev AG 12 of 25

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE CRITICAL TASK Charging Pumps - TWO RUNNING ATC verifies SI System status E-O.I - Crew establishes flow from at ATC identifies that 2CHS*P21A did not Auto least one high head ECCS pump HHSI Flow- INDICATED start on SI signal, and manually starts before transition out of E-O. LHSI Pumps - TWO RUNNING 2CHS*P21A. Reports malfunction to the crew.

Both LHSI pumps running.

Verify AFW Status BOP verifies 2FWE*P23A & B both running 2FWE*P22 steam supply valves all open AFW Throttle valves all full open And total AFW flow is > 340 gpm.

SRO directs an operator to verify automatic actions by performing Attachment A-O.II when time permits.

Attachment A-O.ll included with List of Attachment A-O.ll Discrepancies:

scenario beginning on Pg 22. Operator assigned to perform Attachment A-O.II 2CHS*P21A failed to auto start, manually reports status ofattachment to the SRO and any started - SAT. actions taken when completed.

2-2 EDG failed to auto start, manually started and then subsequently tripped after loading, resulting in ALL "B" Train equipment being de energized.

RCS temperature trending to 547°F. ATC reports Tavg status, SRO directs crew to RCPs OPERATING-MONITOR Tavg control steam/feed flow as necessary to achieve desired status.

RCPs STOPPED - MONITOR Tcold BVPS - 2 Scenario 4, Rev AG 13 of 25

BEAVERVALLE'r rlOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check CIB NOT ACTUATED ATC checks Recirc Spray Pump status, CIB NOT actuated, Recirc spray pumps not running.

Recirc Spray HXs - SERVICE WATER FLOW TO ALL 4HXs Check Recirc Spray Pumps - ANY RUNNING Check Recirc Spray Pumps - ALL RUNNING Check Recirc Spray Pumps - NOT CAVITATING PORVs - CLOSED(not leaking). ATC verifies PRZR isolated Spray Valves - CLOSED Safety relief valves - (PSMS Detailed Data Page 1)

-CLOSED Check PRT conditions CONSISTENT WITH EXPECTED VALVES Power to at least one block valve - AVAILABLE Block valves - AT LEAST ONE OPEN BVPS - 2 Scenario 4, Rev AG 14 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE DIP between RCS pressure and highest SG pressure ATC checks if RCPs should be stopped

- LESS THAN 205 PSID [220 PSID ADVERSE CRITICAL TASK CNMT] ATC determines RCP DIP trip criteria met.

E-1.C - Crew trips all RCPs when ATC verifies HHSI flow.

RCS to highest SG DIP criteria is AND exceeded and SI flow verified prior to HHSI Flow INDICATED ATC STOPS all RCPs.

exiting procedure E-l.

Stop All RCPs Pressures in all SGs - ANY DROPPING IN AN BOP determines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED Check all SG levels - NONE RISING IN AN BOP determines all SG tubes are intact.

UNCONTROLLED MANNER Check Secondary Radiation CONSISTENT WITH PRE-EVENT VALVES

[2ARC-RQIOO] Air Ejector Discharge (1007)

[2SSR-RQI00] SG Blowdown Sample (1062)

[2MSS*RQI0IA,B,C] Main Steamline Discharge (1005, 3005, 5005)

BVPS - 2 Scenario 4, Rev AG 15 of 25

BEAVER VALLE I '"'OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check the following consistent with pre-event Crew checks if RCS is intact values:

CNMT Pressure CREW DETERMINES THAT RCS IS NOT CNMT Sump Level INTACT, TRANSITIONS TO E-l STEP 1.

CNMT Radiation Crew transitions to E-1 STEP 1 SRO directs transition to E-1 NOTE:

With containment pressure greater than 11 psig without any Quench Spray pumps running, an Orange Path exists for Containment which requires entry into FR-Z.l When this condition is reported by the STA; the SRO will implement FR-Z.l, and then exit and return to E-l.

SRO directs STA to monitor status trees.

Crew checks if CREVS should be actuated Crew checks if CREVS should be actuated Control Room radiation monitor [2RMC*RQ201, 202] (1069, 1072) - NOT IN HIGH ALARM CIB - HAS NOT OCCURRED BVPS - 2 Scenario 4, Rev AG 16 of 25

BEAVER VALLE: I POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GOI=DE=L-::IN:-:-:E::-:S~-'-----:P=LA~N=T-=S=TA-:-T=U--:S:-O~R::::-:=R=E~SP=--O=N-:-:S=-=E:::----'----E=X=P=E=C=T=ED=-=ST=U:-:-:D::-::E=N-=T=-=R=E=S=P=07:"N=SE=----,

DIP between RCS pressure and highest SG pressure ATC checks if RCPs should be stopped.

- LESS THAN 205 PSID [220 PSID ADVERSE CNMT] All RCPs previously stopped.

AND HHSI Flow INDICATED Reps STOPPED CIB - ACTUATED ATC checks Recirc Spray Pump status Recirc Spray Hxs - SERVICE WATER FLOW TO ATC verifies 2SWS*MOV103A(B) OPEN and ALL 4 HXS 2SWS*MOV106A(B) CLOSED R WST Level - ~ 381 inches ATC checks RWST level> 381 inches Verify Recirc Spray Pumps - NOT CAVITATING Pressures in all SGs - ANY DROPPING IN AN BOP detennines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED SGs are NOT faulted Narrow Range Levels - GREATER THAN 12% BOP checks intact SG levels

[31 % ADVERSE CNMT]

BOP controls feed flow to intact SGs to maintain NR level between 12% [31% ADVERSE CNMT]

and 50%

BVPS - 2 Scenario 4, Rev AG 17 of 25

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I* EXPECTED STUDENT RESPONSE*

Check all SG levels - NONE RlSING IN AN Crew detennines all SG tubes are intact UNCONTROLLED MANNER Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQI00] (1007) Air ejector discharge

[2SSR-RQIOOJ (1062) SGBD sample

[2MSS*RQI01A,B,C] Main Steamline discharge (1005,3005,5005)

Power to the Block Vlvs - AVAILABLE ATC checks PRZR PORVs and Block Valves:

PORVs - CLOSED All PORVS CLOSED.

Block Vlvs - AT LEAST ONE OPEN All Block valves open and energized.

RCS Subcooling based on core exit TCs > 41F ATCIBOP check if SI flow can be reduced

[59F ADVERSE CNMTJ Secondary heat sink: Crew determines RCS subcooling is ~ required Total feed flow to intact SGs - GREATER THAN from Attachment A-5.1.

340 GPM OR SI FLOW CANNOT BE REDUCED Narrow range level in at least one intact SG GREATER THAN 12% [31-% ADVERSE CNMT]

RCS pressure - STABLE OR RlSING PRZR leveI- GREATER THAN 17% [38% SI TERMINATION CONDITIONS ARE NOT ADVERSE CNMT] SATISIFIED, SRO CONTINUES IN E-l.

BVPS - 2 Scenario 4, Rev AG 18 of 25

BEAVER VALLET POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Any Quench spray or recirc spray pump ATC/BOP check ifCNMT Spray should be RUNNING stopped.

SRO continues with STEP 10.

SI & CIA - RESET ATC resets SI and CIA RCS Pressure - > 225 PSIG [250 PSIG ADVERSE ATC checks ifLHSI Pumps should be stopped CNMT]

RCS Pressure - STABLE OR RISING ATC determines RCS pressure is NOT stable or rising.

LHSI Pumps stopped and in auto ATC determines RCS pressure < 225 psig, LHSI pumps to remain running.

ATCIBOP checks RCS and SG Pressures.

Check pressures in all SGs STABLE OR RISING BOP determines SG pressures are stable or rising.

Check RCS Pressure - STABLE OR DROPPING ATC determines RCS pressure is dropping.

ROLEPLAY: Verify AC emergency busses energized from BOP checks ifEDGs should be stopped.

Ifpreviously requested to investigate offsite loss of 4KV bus, report back that a burnt insulation smell is coming from Stop any unloaded EDG by performing 20M Crew initiates actions to STOP EDGs.

the 2D 10 breaker cubical. 36.4.AF(AG)

BVPS - 2 Scenario 4, Rev AG 19 of 25

BEAVER VALLEy POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7

-:-:-::-:--=-:-::-:::-=:-:::-=-::-----r-----::::-:-:-::-:=-==-:-==-::-:--::-=-==-=-:::-=-::::--:-:-=-=------.------=:-:-=-:=-==-=-=::-:==-::~=:_:=_:_=-___,

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Verify Cold Leg Recirculation Capability. SRO directs operators to perform Att A-O.6 and verify cold leg recirculation capability Due to loss of 2DF 4KV bus along with loss of 2MCC-Ell, the BOP determines that at least one train of cold leg recirc capability can not be verified and reports to SRO that RECIRC CAPABILITY NOT AVAILABLE.

SRO determines entry into ECA-1.1 required.

Crew transitions to ECA-l.l STEP 1 SRO directs transition to ECA-1.1 Recifc Spray Pumps NO SIGN OF ATC determines no Recife Spray pumps are CAVITATION. running.

ATC determines Transfer-to-Recirculation was not initiated.

Reset SI signal. ATC RESETS SI, both trains.

Reset SI Recirc Mode. ATC RESETS SI RECIRC MODE, both trains.

Check Charging Pump Flow ATC verifies HHSI flow on 2SIS-FI943.

BVPS - 2 Scenario 4, Rev AG 20 of 25

BEAVER VALLE: I POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check Emergency Coolant Recirculation BOP perfonns Attachment A-0.8.

Equipment - A V AILABLE Along with unavailability of power to MCC-Ell and 2DF 4KV busses, the BOP detennines RWST level is NOT less than 369 inches, therefore, Cold leg recirc alignment is not required at this time.

Crew continues attempts to restore at least one train.

Check RWST level GREATER THAN 30 ATC verifies RWST level is > 30 inches.

INCHES Detennine Quench Spray Requirements. ATC determines that CIB is ACTIJATED, however NO Quench Spray pumps are running, Quench Spray reduction is not necessary.

Check Recirc Spray System Status. ATC detennines that CIB is ACTUATED, Verifies SWS flow established to "A" train RSS Heat Exchangers.

ATC verifies RWST level is not less than 381 inches, Transfer to Recire not required at this time.

CRITICAL TASK Add Makeup to R WST as Necessary Crew initiates makeup to the RWST lAW 20M ECA-1.1.B -Crew makes up to the 7.4.0, "Makeup To The Refueling Water Storage RWST and minimizes RWST Tank".

outflow.

Tenninate drill when crew initiates actions to Makeup to the R WST in ECA-I.!.

BVPS - 2 Scenario 4, Rev AG 21 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Classify Event SRO evaluates EPP and declares a SITE AREA EMERGENCY due to TAB 1.2.3, Loss of RCS Barrier and Tab 1.3.2, Potential Loss of Containment Barrier due to not having 1 complete Train of Containment Depressurization available BVPS - 2 Scenario 4, Rev AG 22 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRLJCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of US directs operator to perform Attachment A-O.ll Automatic Actions' performed as time as time & manpower permit

& manpower permit Diesel generators - BOTH RUNNING Check both EDGs running, BOP notes the 2-2 EDG did not auto start, BOP manually starts 2-2 EDG. EDG starts, loads and then trips 90 seconds later resulting in loss of power to the 2DF 4KV bus.

CNMT pressure - GREATER THAN 7 PSIG Check if MSLI is required OR SG Steam Pressure - LESS THAN 500 PSIG If not required, go to step 4 OR Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIT Verify steamline isolation STEP 4 Open [2CCS-AOVl18] Domestic Water to Station Establish Domestic Water System Cooling to Air Compressor Station Air Compressors At least one Station Air Compressor - RUNNING Start 1 Station Air Compressor as required CCP pumps - AT LEAST 1 RUNNING Check CCP Pump status BVPS - 2 Scenario 4, Rev AG 23 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE 2NME-NR45 Nuclear Recorder selected to Align neutron flux monitoring for shutdown operable source and intermediate range displays CNMT pressure - HAS REMAINED LESS THAN Check CIB status 11 PSIG IF NOT Actuate CIB if required Manually initiate crn BOTH SWITCHES FOR BOTH TRAINS Manually align equipment as required All RCPs STOPPED Stop ALL RCPs BV-1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps - 2 RUNNING Verify Service Water System in service Service Water Header Pressure - GREATER THAN 55 PSIG SWS Seal Water Pressure - NOT LOW

[2HCS*SOVlOOAl, B1] - CNMT Sample amber Verify both CNMT hydrogen analyzers running light- LIT NOTE: All Red SIS Marks - LIT Verify ESP Equipment status - Start/align Due to 2D F 4KV bus being de All Orange CIA Marks LIT equipment as required energized, ALL train "B" All Green FWI Marks - LIT components will be de-energized with 2CHS*P21A did not auto start, BOP manually positions unable to be verified. starts 2CHS*P21A satisfactorily.

BVPS - 2 Scenario 4, Rev AG 24 of 25

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Power available to both Emergency AC Busses Verify power to both AC Emergency busses Restore power as required 2DF 4KV Bus de-energized Attachment A-O.l1 - COMPLETE Report any discrepancies to SMIUS BVPS - 2 Scenario 4, Rev AG 25 of 25

v t e Letter Sequence Other
TAC:U01821, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML102510196, ML102510217, ML102510235, ML102510316, ML102650433, ML102650445, ML102650459, ML111680049
MONTHYEAR2010-07-03 [Table View]

ML102510316

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4.2. COMMENTS

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