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Beaver Valley Unit 1 - Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML14246A240
Person / Time
Site:	Beaver Valley
Issue date:	07/01/2014
From:	; FirstEnergy Nuclear Operating Co
To:	Brian Fuller; Operations Branch I
Shared Package
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RTL#A5.640U 1/2-ADM-130 l.F04 Page 3 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 AD-007 JPM TITLE p fi A E

d c *

1 p *

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JPM REVISION:

2 : er orm n stlmate ntlca os1t10n a cu atwn KIA

REFERENCE:

2.1.23 (4.3/4.4)

TASK ID: 0011-003-01-013 JPM APPLICATION:

IZI REQUALIFICATION D FAULTEDJPM IZI INITIAL EXAM IZI TRAINING iZ! ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: IZI Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC IZI Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 35 Minutes Actual minutes Critical:

IZI No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-007 JPM REVISION:

2 JPM TITLE: Perform An Estimated Critical Position Calculation TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET Boron concentration for startup calculated within the specified tolerance.

Classroom

A plant startup is being performed exactly 5 days after a reactor trip from 100% power.

Prior to the trip, the plant was at 100% with All Rods @ 227 steps for 3 months.

An RCS Boron sample was taken at 1 00% power one hour prior to the Reactor trip. It indicated that the RCS Boron concentration was 839 ppm.

The Current Core burnup is 10,000 MWD/MTU.

The plant computer is NOT available.

The Unit Supervisor directs you to determine the boron concentration for startup by performing 10M-50.4.F, "Performing An Estimated Critical Position Calculation", steps IV. A through IV.C.l.k.

Control rod position Expected at Criticality is Bank D at 1 00 steps. Reactor Engineering was consulted regarding B-1° Correction for Criticality.

They report that the B-10 correction Factor for criticality (Data Sheet 1 block C.VII) is 0.900. 10M-50.4.F, "Performing An Estimated Critical Position Calculation", Rev. 6 Unit 1 Curve Book, Issue 23, Rev. 0 Calculator 1 OM-50.4.F, "Performing An Estimated Critical Position Calculation", Rev.6 Unit 1 Curve Book, Issue 23, Rev. 0 RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET l/2-ADM-130l.F04 Page 5 of9 Revision 1

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

INITIATING CUE:

A plant startup is being performed exactly 5 days after a reactor trip from 100% power.

Prior to the trip, the plant was at 100% with All Rods @ 227 steps for 3 months.

An RCS Boron sample was taken at 100% power one hour prior to the Reactor trip. It indicated that the RCS Boron concentration was 839 ppm.

The Current Core bumup is 10,000 MWD/MTU.

The plant computer is NOT available.

The Unit Supervisor directs you to determine the boron concentration for startup by performing 10M-50.4.F, "Performing An Estimated Critical Position Calculation", steps IV. A through IV.C.l.k.

Control rod position Expected at Criticality is Bank D at 1 00 steps. Reactor Engineering was consulted regarding B-1° Correction for Criticality.

They report that the B-10 correction Factor for criticality (Data Sheet 1 block C.VII) is 0.900. 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-130 l.F04 Page 6 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-007 I JPM REVISION:

2 JPM TITLE: Perform An Estimated Critical Position Calculation STEP ( "C" Denotes CRITICAL STEP) 1. Input Critical Data Data Sheet 1, (Part A I Prior to Shutdown)

Date/Time Boron Cone. Power Bum up Xenon Samarium Control Rod Position STANDARD 1.1 (Indicate "S" FOR SAT or "U" FOR UN SAT DEVELOPERN ALIDATION NOTES: When updating this JPM for the current plant cycle, use care to choose parameters that will not require interpolation.

Ensure Control Rod Position is updated to reflect actual plant. START TIME: _______ _ Inputs Critical Data Part A I Prior to Shutdown.

Date/Time

= 5 days ago Boron Cone.= 839 ppm Power= 100% Bumup = 10,000 (MWD/MTU)

Xenon= 100% (CB-12) Samarium = 100% (CB-22) Control Rod Position = ARO at 227 steps COMMENTS:

RTL#A5.640U 112-ADM-130l.F04 Page 7 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: IAD-007 JPM TITLE p .c: A E

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JPM REVISION:

2 : er1orm n sttmate ntica osition a cu atwn STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 2. Input Critical Data 2.1 Inputs Critical Data Part A II Data Sheet 1, Expected at Criticality. (Part A II Expected at Criticality)

Date/Time Date/Time

=NOW Burn up Bumup = 10,000 (MWD/MTU)

Xenon Xenon= 0% (CB-23) Samarium Samarium=

135% (CB-22) Control Rod Position Control Rod Position=

Banks A & B @ 227 steps Bank C@ 227 steps Bank D @ 1 00 steps COMMENTS:

3. Determine Effective boron 3.1 Determines the Effective Boron Concentration Concentration Part A III, IV, & V) Data Sheet 1, (Part A III, IV, & V) Part III, Boron Cone. Part III, Boron Cone. = 839 ppm Part IV, B-1 0 Corr factor Part IV, B-10 Correction Factor= 0.894 (CB-29) Part V, Effective Boron Part V Effective Boron Cone. = 839 ppm X 0.894 = Cone. 750 ppm (rounded off) COMMENTS:

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE l/2-ADM-130l.F04 Page 8 of9 Revision I I JPM NUMBER: lAD-007 JPM TITLE p .c: A E

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JPM REVISION:

2 : er1orm n stlmate ntlca osition a cu atwn STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::>

S/U 4. Calculate Reactivity Balance 4.1 Calculates Part B, Item 5. (Data Sheet 1, Part B) Part B.1

Power Defect=-0-2400 =-2400 pcm (CB-21) Part B.2

Control Rods= 925-0 = + 925 pcm (CB-24B) Part B.3

Xenon= 0-2701 =-2701 pcm (CB-23) Part B.4

Samarium=

851-630 = + 221 pcm (CB-22) Part B.5

Reactivity Change=-3955 pcm COMMENTS:

5. Calculate Boron Concentration 5.1 Calculates Part C, Line 1, Item V. for Startup (Data Sheet 1, Part C) Part C.I

Reactivity Change=-3955 pcm (from B.5) Part C.II

Differential Boron Worth=-7.33 pcm/ppm (CB-20) Part C.III

Boron Change = + 540 ppm Part C.IV

EffBoron Cone. at Shutdown=

750 ppm Part C.V

EffBoron Cone. For Startup= 1290 ppm COMMENTS:

I RTL#A5.640U 112-ADM-1301.F04 Page 9 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

1AD-007 JPMTITLE p .c: A E . dC .. lP . . C 1 1 .

1 JPM REVISION:

2 : er1orm n stlmate ntlca osition a cu at10n STEP ( "C" Denotes CRITICAL STEP) 6.C Calculate Boron Concentration for Startup (Data Sheet 1, Part C) Part C.1 Part C.II Part C.III Part C.IV Part C.V Part C.VI Part C.VII Part C.VIII STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 6.1 C Calculates Part C, Line 2, Item V.

Reactivity Change=-3955 pcm (from B.5)

Differential Boron Worth=-6.98 pcm/ppm (CB-20)

Boron Change=+ 567 ppm

Eff. Boron Cone. at Shutdown=

750 ppm (from A.V)

Eff. Boron Cone. For Startup = 1317 ppm (+/-50 ppm)

Eff. Boron Cone. For Startup= 1317 (from C.V)

B-1 0 Correction Factor for Criticality=

0.900

Boron Concentration for Startup= 1463 (+/-50 ppm) COMMENTS:

EVALUATOR NOTE: Grader Discretion Required.

TERMINATING CUE: When the Candidate completes the calculation, the evaluation for this JPM is complete.

STOP TIME: ______ _

BVPS-SBS Operating Procedures Unit 1 PERFORMING AN ESTIMATED AN 5 U) .l'l l< y CRITICAL POSITION CALCULATION DATA SHEET 1: FORM ECP-1 A. Critical Data (I) (II) 10M-50.4.F Revision 6 Page 17 of 30 f2..a A-1. I PRIOR TO SHUTDOWN EXPECTED AT CRITICALITY A-GO Time Boron Cone. 8 3 9 ppm PowerlOO % Burnup LO J OoO Xenon to&% (Use or N/A) Samarium I Otl % (Use Fig *WOr N/A) Control Rod Position A '2. 't.7 c t27 B D 22..., Ill Boron Concentration (Part A, Column I) (MWD/MTU)

Date T ,o.,,y Time NoW Burn up (Ol 00 0 (MWDIMTU)

Xenon 0% (Use Fig @or N/A) Samarium f 3 r % (Use N/A) Control Rod Position CZ2.'1 B D .(00 B. Reactivity Balance -(Record absolute values in Columns I and II) (I) (II) {Ill) Reactivity Defects Prior to Shutdown Expected at (II -I) Criticality Difference

1. Power (Fig 24oo ... 0 OR Consult Rx Engr) pcm 0 (zero) pcm (--:-)2 ;o pcm 2. Control Rods (Circle Fig. ..f (Fig. CB-24A, 4B 24C 0 91 OR Consult Rx Engr) pcm pcm 3. Xenon 7..70\ pcm 0 pcm ;,1.'TO \pcm 4. Samarium

(, 3 0 8S \ i pcm pcm pcm 5. Reactivity Change (Sum of 1-4) = -'31 pcm -DATA SHEET 1: FORM ECP-1 AJOT c v r il t -rc BVPS-SBS Operating Procedures Unit 1 10M-50.4.F Revision 6 AN !'W 1\ '( Page 18 of 30 PERFORMING AN ESTIMATED CRITICAL POSITION CALCULATION y P-o A-1.1 1. 2. C. Critical Boron Concentration Reactivity Change (B.S) (VI) II Differential Boron (Fig. <<.§:W .. '"7 .l'3 pcm ppm pcm ppm (VII) Ill Boron Change (I) + (II) ... S"'-10 IV Eff. Boron Cone. At Shutdown (SO m m m 7SO m (VIII) v Eff. Boron Cone. For Startup Ill + I m m Eff. Boron Cone. For B-10 Correction Factor Boron Concentration Startup for Criticality for Startup (Part C, Column V, line 2) (from Rx Eng) (VI)+ (VII) \3\1 ppm o.a.oo t"/{,"3 ppm . \eo\ D. Estimated Rod Position Correction (I) (II) (Ill) (IV) Boron Cone. For Boron Deviation Differential Boron Boron Sample Startup C.1.k (I)-(II) Worth (Fio. CB-20) pcm ppm ppm (t) ppm (-) ppm (V) (VI) (VII) (VIII) Rod Worth Rod Worth Corrected Rod Worth Corr Critical Rod Pos. (Circle Figure Used) Correction Expected At Expected At Criticality (Fig CB-24A, 24B, 24C (Ill) x (IV) Criticality (B.2) (V) +(VI) OR Consult Rx Enor) (+/-) pcm pcm ( -) pcm Steps DATA SHEET 1: FORM ECP-1 RTL#A5.640U TPM NUMBER: 1AD-O 16 L JPM REVISION:

1 JPM TITLE: Plot and Evaluate liM Data 1/2-ADM-1301.F04 Page 3 of7 Revision 1 Kl A

REFERENCE:

2.1.43 4.1/4.3 TASK ID: 0011-003-01-013 IZI INITIAL EXAM IZI TRAINING JPM APPLICATION:

iZI REQUALIFICA TION D FAULTED JPM iZI ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: r2J Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC r2J Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 30 Minutes Actual minutes Critical:

IZI No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET 112-ADM-1301.F04 Page 4 of7 Revision 1 Determine that 1/M data predicts >500 pcm below ECP value for critical rod height. Recommend No further rod withdraw!.

Classroom The unit is in Mode 2. A reactor startup is in progress.

Control Bank C is at 94 steps. Control Bank D is at 0 steps. RCS Boron concentration is 123 8 ppm. Your Supervisor directs you to complete and evaluate the 1/M plot per 1 OM-50.4.F data sheet 3 using the SR count rate data provided.

Compare the 1/M data with the predicted ECP data and make a recommendation for further rod withdrawal.

Document your recommendation in the box below. (Located on candidate direction sheet) 10M-50.4.F, Performing An Estimated Critical Position Calculation, Rev.6 10M-50.4.D, Reactor Startup from Mode 3 to Mode 2, Rev. 56. Calculator; Ruler/straight edge. 10M-50.4.F, Performing An Estimated Critical Position Calculation, Rev. 6 partially completed Data Sheet 3 & Figure 1 1 OM-50.4.D, Rev 6, Reactor Startup from Mode 3 to Mode 2, Rev. 56.

RTL#A5.640U l/2-ADM-130l.F04 Page 5 of7 Revision I CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The unit is in Mode 2. A reactor startup is in progress.

Control Bank C is at 94 steps. Control Bank D is at 0 steps. RCS Boron concentration is 1238 ppm. INITIATING CUE: Your Supervisor directs you to complete and evaluate the 1/M plot per 10M-50.4.F data sheet 3 using the SR count rate data provided.

Compare the 1/M data with the predicted ECP data and make a recommendation for further rod withdrawal.

Document your recommendation in the box below. RECOMMENDATION:

D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 AD-016 JPM TITLE: Plot and Evaluate 1/M Data JPM REVISION:

1 1. Refer to data sheet 3 2. Refer to 1/M plot 3.C Evaluate 1/M plot data STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> START TIME: ______ _ 1.1 Refers to data sheet 3 for count rate data. COMMENTS:

2.1 Evaluates count rate data from data sheet 3 and plots on the liM for 250, 300, AND 350 total steps. EVALUATOR NOTE: See attached Answer Key for liM plot values. It is not necessary to plot both SR curves since the data is identical.

COMMENTS:

3.1C Determines that the 1/M plot predicts criticality

>500 pcm below ECP. Minimum rod height is Bank D at 50 steps versus ECP of Bank D 100 steps. COMMENTS:

RTL#A5.640U 112-ADM-130l.F04 Page 7 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE iPM NUMBER: 1AD-016 I JPM REVISION:

1 STEP ( "C" Denotes CRITICAL STEP) 4.C Inform SMIUS JPM TITLE: Plot and Evaluate 1/M Data STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 4.1 C Applicant informs SMIUS that liM data indicates that criticality will occur >500 pcm below the ECP. Recommends NO FURTHER ROD WITHDRAWALS.

4.2 Immediately insert ALL control banks to ZERO steps per 10M-50.4.D.

COMMENTS:

TERMINATING CUE: When the applicant makes a recommendation on continued startup, the evaluation for this JPM is complete.

STOP TIME: ______ _

., G5 c ;u m ...... '"U r 0 -I AtJSw Source Range Channel-N-31 Initials/Date

/, ___ _ 1/m PLOT 1.0 """' 0.9 0.8 -0.7 0 2. 0 0.6 :;::; til 0::: CD .... 0.5 til 0::: .... s:::: ::s 0.4 0 0 CD e 0.3 CD > E 0.2 0.1 0 0 50 100 150 200 250 300 350 40) 450 5 0 550 600 65 @ bumulative Steps Withdrawr 0 50 16o" zbo 6) Control Bank B 0 50 1 .1M . ?fi,' Control Bank A Control Bank C 0 50 100. 1 o." 2!'K>.

100 zOO 1. The last two data points shall be used to determine Line Slope to the horizontal axis. -S 2. When determining Control Rod Position, a straight vertical line should be drawn from the horizontal axis to the control bank steps. ()'"U ;urn -;u ::!., oo )>;u ':s:: -u-oz ooG1 :::j)> -z om zoo ()-j )>-r:S:: ())> c-1 );:gj ::! 0 z I ., Q c ;u I m ..... .. ..... -3: "tJ r 0 -1 0 om -o< CD'"U @00 !:t I ::s(f) <Om '"U(f) a () CD a. s:::: ..... CD (/) c ::s ;::; ..... <0 ...... CD::UO 01 (ij" &. 0 -*0 -o.

00>,

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: IAD-04 7 1 JPM REVISION:

0 JPM TITLE: Prepare a Clearance Tagout (1FW-P-3B)

KIA

REFERENCE:

2.2.13 4.1/4.3 TASK ID: 0481-007-03-043 INITIAL EXAM 112-ADM-130l.F04 Page 3 of6 Revision I TRAINING JPMAPPLICATION: REQUALIFICATION D FAULTEDJPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: rime D Yes Allotted 25 Minutes Actual minutes Critical: No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U l/2-ADM-130l.F04 Page 4 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-047 1 JPM REVISION:

0 JPM TITLE: Prepare a Clearance Tagout (1FW-P-3B)

TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET Identify the tags, required position, and clearance sequence for 1FW-P-3B Auxiliary Feedwater Pump. Classroom

The plant is in Refueling Mode, no fuel is in the reactor.

1FW-P-3B Auxiliary Feedwater Pump is to be placed on clearance.

You are to identify the required clearance points (equipment), position (placement configuration), and sequence for clearing 1FW-P-3B, Auxiliary Feedwater Pump for work specified on the clearance coversheet using the references provided.

ESOMS is out of service. Document your results on the table provided. (Located on Candidate Direction Sheet) NOBP-OP-1001, Manual Clearance Generation, Rev. 4 NOP-OP-1001, Clearance/Tagging Program, Rev. 20 OP Manual Fig. No. 24-2, 8700-RM-424-2, Rev. 18 10M-24, Steam Generator Feedwater System Operating Manual. None NOBP-OP-1001, Manual Clearance Generation, Rev. 4 NOP-OP-1001, Clearance/Tagging Program, Rev. 20 OP Manual Fig. No. 24-2, 8700-RM-424-2, Rev. 18 1 OM-24, Steam Generator Feedwater System Operating Manual. Clearance coversheet 1R00-24-FW-001 RTL#A5.640U l/2-ADM-130l.F04 Page 5 of6 Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The plant is in Refueling Mode, no fuel is in the reactor.

1FW-P-3B Auxiliary Feedwater Pump is to be placed on clearance.

INITIATING CUE: You are to identify the required clearance points (equipment), position (placement configuration), and sequence for clearing 1FW-P-3B, Auxiliary Feedwater Pump for work specified on the clearance coversheet using the references provided.

D D D D ESOMS is out of service. Document your results on the table provided. (Located on Candidate Direction Sheet) At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-130 l.F04 Page 6 of6 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: lAD-04 7 JPM REVISION:

O JPM TITLE: Prepare a Clearance Tagout (1FW-P-3B)

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> START TIME: ______ _ EVALUATOR NOTE: This task is normally performed using the ESOMS clearance computer and signed electronically.

For this JPM, the ESOMS computer is NOT available.

EVALUATOR NOTE: Provide JPM handout references and student copy of table. EVALUATOR CUE: Ifthe candidate asks about the work scope, you can respond that that the Feedwater System will NOT be breached (i.e.: the system will NOT be opened/ drained.)

l.C Candidate completes the table. 1.1 C Candidates table matches the ANSWER KEY. COMMENTS:

EVALUATOR CUE: When the candidate identifies and reports that all tags are identified, the evaluation for this JPM is complete.

Grader discretion will be required.

STOP TIME: ______ _

ANSWER KEY (DO NOT GIVE TO STUDENTS)

Component ID Description Position Sequence 1FW-P-3B-CS "B" Auxiliary Feedwater Pump Control Pull-To-Lock 1 Switch on Control Board (PTL) C*l). 4KVS-1 DF-4 I 125 VDC Control BRKR for the 4KV Bus OFF 2 1F16 1DF BRKR 1F16 4KVS-1H-1F16 Supply to Auxiliary Feedwater Pump Racked Out 3 1FW-P-3B 1FW-38 1FW-P-3B "A" Header Discharge Shut 4 Isolation 1FW-41 1FW-P-3B "B" Header Discharge Shut 4 Isolation 1FW-608 Or FCV-1FW-103B Outlet Isolation Or Shut 5 (**2) 1FW-607 FCV-1FW-103B Inlet Isolation 1FW-55 1FW-P-3B Recirculation and Cooler Shut 5 (**2) Isolation Evaluator NOTE: Student may identify additional points. The points listed above are the minimum required for this JPM. All additional points must be evaluated to ensure the clearance is correct. Component Descriptions may vary. C*l). DC Control PWR is optional and not required.

C**2) This Sequence may be either 4 or 5, or 4,5,6,7.

> 0. 0 u 1-z w Q ::::>> 1-U) c 0 *-..., *-<<ft 0 A. c 0 *-*-.... u <<ft cu Q ..., c cu c & E 0 u Q ..... ..., c cu c & E 0 u R fL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 1/2-ADM-130 l.F04 Page 3 of8 Revision I l JPM NUMBER: lAD-0°4 JPM TITLE: Perform Decay Tank Discharge Pre-Release Verification JPM REVISION:

2 KIA

REFERENCE:

2.3.11 3.8/4.3 TASK ID: 0191-006-01-011 071 A4.26 3.1/3.9 [g] INITIAL EXAM D TRAINING JPM APPLICATION:

[g] REQUALIFICA TION D FAULTED JPM [g] ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: [g] Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC [g] Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 10 Minutes Actual minutes Critical:

[g] No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 112-ADM-1301.F04 Page 4 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-004 JPM TITLE p fi D Tank D" h p R l V "fi

1 JPM REVISION:

2 : er orm ecay 1sc arge re-e ease en 1cat10n TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET Identifies 1GW-TK-1A gas release cannot occur until a second sample and analysis are performed and independently verified by two technically qualified facility staff. Classroom

An unplanned shutdown of Unit 1 has resulted in the need to discharge Gas Decay Tank 1GW-TK-1A.

All other equipment is in NSA except for the Gaseous Waste Gas Monitor RM-1GW-108B, which is out of service.

Gas Decay Tank 1GW-TK-1A pressure is 51.8 psig.

RadPro has taken a sample and has generated an RWDA-G for 1GW-TK-1A release. You are to perform 1GW-TK-1A Decay Tank Discharge Pre-Release Verification in accordance with 10M-19.4.E, "Decay Tank Discharge", beginning at step IV.D. Coordinate the completion of RWDA-G for release of 1GW-TK-1A AND make a recommendation for continuing the discharge in the box below, INCLUDING any justification. (Provided in the candidate direction sheet) 10M-19.4.E, Decay Tank Discharge, Rev. 10 1/2-ENV-05.05.F01, Rev. 0 (RWDA-G) 1/20DC-3.03, "ODCM: Controls for RETS/REMP Programs", Rev. 11 None 10M-19.4.E, Decay Tank Discharge, Rev. 10 place kept through step IV.C. Partially completed pre-release RWDA-G for 1GW-TK-1A.

1/20DC-3.03, "ODCM: Controls for RETS/REMP Programs", Rev. 11 (Provide when asked)

RTL#A5.640U 1/2-ADM-130 l.F04 Page 5 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

An unplanned shutdown of Unit 1 has resulted in the need to discharge Gas Decay Tank lGW-TK-lA.

All other equipment is in NSA except for the Gaseous Waste Gas Monitor RM-1GW-108B, which is out of service.

Gas Decay Tank lGW-TK-lA pressure is 51.8 psig.

RadPro has taken a sample and has generated an RWDA-G for lGW-TK-lA release. 'NITIA TING CUE: You are to perform lGW-TK-lA Decay Tank Discharge Pre-Release Verification in accordance with 10M-19.4.E, "Decay Tank Discharge", beginning at step IV.D. Coordinate the completion of RWDA-G for release of lGW-TK-lA AND make a recommendation for continuing the discharge in the box below, INCLUDING any justification.

RECOMMNEDATION(S):

D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 1.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE 1 JPM TITLE: Perform Decay Tank Discharge Pre-Release Verification

1. Review 10M-19.4.E, "Decay Tank Discharge" and partially completed RWDA-G. STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> START TIME: ______ _ EVALUATOR CUE: Provide candidate a place kept copy of 10M-19.4.E place kept up to step IV.C and partially completed RWDA-G. 1.1 Candidate reviews 10M-19.4.E and RWDA-G provided.

EVALUATOR NOTE: The purpose ofthe JPM is to check for an understanding of meeting the ODCM by relying on an Action Statement.

EVALUATOR NOTE: If the candidate requests more information:

The US has notified Chemistry

1GW-276 is closed.

TV-1GW-103A1, 103B1, and 103C1 are all closed.

FR-1GW-108, GW Flow to Cooling Tower indicates 1200 SCFM.

1GW-F-1A is operating.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-004 JPM TITLE p -i': ank D" 1 *

JPM REVISION:

2 : er1orm Decay T 1scharge Pre-Re ease Venficat10n STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U EVALUATOR CUE: If asked, RM-1 GW -109 alarms were adjusted ONLY. EVALUATOR NOTE: If candidate requests a copy ofthe ODCM, ensure 1/20DC-3.03 is available for reference.

2.C Verify [RM-1GW-108B]

is 2.1C Determines

[RM-1GW-108B]

is NOT operable from operable as specified by Yz-initial conditions. (this is satisfied as long as the ODC-3.03, 3.3.3.10, candidate does not recommend that the discharge can Attachment F OR the continue using this radiation monitor).

provisions of the action statement will be satisfied 2.2C Determines Yz-ODC-3.03, Attachment F on Table 3.3-AND Initial the RWDA-G on 13, Action 27 is applicable and at least two the (Prerequisites of ODCM Yz-independent samples of 1GW-TK-1A contents must ODC-3.03, 3.3.3.10, be analyzed and at least two technically qualified Attachment F, Table 3.3-13 are members ofthe Facility Staff independently verify the met) block. release rate calculations and discharge vent lineup. 2.3 Recognizes that RM-1GW-109 Ch 5 cannot be used as the comparable alternate monitoring channel for batch releases via this pathway. (this is satisfied as long as the candidate does not recommend that the discharge can continue using this radiation monitor).

COMMENTS:

RTL#A5.640U l/2-ADM-130l.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 AD-004 JPM REVISION:

2 JPM TITLE: Perform Decay Tank Discharge Pre-Release Verification STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 3.C Makes recommendation to the SM that a second sample and analysis is required prior to continuing the procedure.

3.1 C Recognizes the second sample and analysis has NOT been performed and recommends to the Shift Manager that a second sample and analysis are required, but have not been performed yet in order to continue the procedure.

EVALUATOR CUE: When recommendations are provided to the SM, this JPM is complete.

EVALUATOR NOTE: Grader discretion may be required.

COMMENTS:

STOP TIME: ______ _

I RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 112-ADM-130l.F04 Page 3 of6 Revision 1 JPM NUMBER: 1AD-011 JPM REVISION:

3 JPM TITLE: Review An Estimated Critical Position Calculation (SRO Only) KJ A

REFERENCE:

2.1.23 ( 4.3/4.4) TASK ID: 0011-003-01-013 INITIAL EXAM TRAINING JPM APPLICATION: REQUALIFICA TION D FAULTEDJPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 20 Minutes Actual minutes Critical: No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: I Evaluator Signature:

RTL#A5.640U 112-ADM-130l.F04 Page 4 of6 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 AD-O 11 JPM REVISION:

3 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Review An Estimated Critical Position Calculation (SRO Only) EVALUATOR DIRECTION SHEET Determines the following errors exist in the completed Estimated Critical Position Calculation:

Wrong Control rod pin block B.2.II (1090 pcm instead of925)

Wrong Samarium values in blocks B.4.I and II (851 pcm in block I instead of 630 pcm AND 630 pcm in block II instead of 851 pcm)

Wrong Boron Concentration for Startup in block C.VIII (block C. VI should have been divided by block C. VII versus multiplied)

Calculates that the corrected Boron Concentration for Startup is 1463 ppm (+/-50 ppm). Classroom

A plant startup is being performed exactly 5 days after a reactor trip from 100% power.

Prior to the trip, the plant was at 100% with All Rods @ 227 steps for 3 months.

An RCS Boron sample was taken at 100% power just prior to the Reactor trip. It indicated that the RCS Boron concentration was 839 ppm.

Current Core burnup is 10,000 MWD/MTU.

The plant computer is NOT available.

Reactor Engineering was consulted regarding B-1° Correction for Criticality.

They report that the B-10 correction Factor for criticality (Data Sheet 1 block C. VII) is 0.900.

RCS Tavg is 54 7 °F The Shift Manager directs you to perform a review of the completed ECP calculation in accordance with 10M-50.4.F, "Performing An Estimated Critical Position Calculation," steps IV.A through IV.C. Report your results in the box below, if any discrepancies are identified, correct the ECP. (Provided on the candidate direction sheet) 1 OM-50.4.F, "Performing An Estimated Critical Position Calculation", Rev.6 Unit 1 Curve Book, Issue 23, Rev. 0 Calculator 10M-50.4.F, (with DATA SHEET 1 blocks A, Band C completed with the errors listed in the task standard.)

Unit 1 Curve Book, Issue 23, Rev. 0 Blank copies of ECP Data Sheet 1 RTL#A5.640U l/2-ADM-130l.F04 Page 5 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

INITIATING CUE: RESULTS OF REVIEW:

A plant startup is being performed exactly 5 days after a reactor trip from 100% power.

Prior to the trip, the plant was at 100% with All Rods @ 227 steps for 3 months.

An RCS Boron sample was taken at 100% power just prior to the Reactor trip. It indicated that the RCS Boron concentration was 839 ppm.

Current Core burnup is 10,000 MWD/MTU.

The plant computer is NOT available.

Reactor Engineering was consulted regarding B-1° Correction for Criticality.

They report that the B-10 correction Factor for criticality (Data Sheet 1 block C.VII) is 0.900.

RCS Tavg is 54 7 op The Shift Manager directs you to perform a review of the completed ECP calculation in accordance with 10M-50.4.F, "Performing An Estimated Critical Position Calculation," steps IV.A through IV.C. Report your results in the box below, if any discrepancies are identified, correct the ECP. 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 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-O 11 JPM REVISION:

3 JPM TITLE: Review An Estimated Critical Position Calculation (SRO Only) STEP ( "C" Denotes CRITICAL STEP) 1.C Review the ECP calculation. (Data Sheet 1) STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT => DEVELOPERIV ALIDATION NOTES: When updating this JPM for the current plant cycle, use care to choose parameters that will not require interpolation.

Ensure rod heights reflect current core. START TIME: ----------------

1.1 C Determines the following errors exist in the completed Estimated Critical Position Calculation:

Wrong Control rod p in block B.2.II ( 1090 pcm instead of 925)

Wrong Samarium values in blocks B.4.1 and II (851 pcm in block I instead of 630 pcm AND 630 pcm in block II instead of 851 pcm)

Wrong Boron Concentration for Startup in block C.VIII (block C. VI should have been divided by block C.VII versus multiplied)

Calculates that the corrected Boron Concentration for Startup is 1463 ppm (+/-50 ppm). COMMENTS:

TERMINATING CUE: When the Candidate completes the review of the calculation and reports the results, the evaluation for this JPM is complete.

Grader Discretion is Reauired.

STOP TIME: ______ _

BVPS -SBS Unit 1 Operating Procedures 10M-50.4.F Revision 6 Page 17 of 30 PERFORMING AN ESTIMATED ANSu:J \< y CRITICAL POSITION CALCULATION S fUl A-I. I DATA SHEET 1: FORM ECP-1 A. Critical Data (I) (Ill PRIOR TO SHUTDOWN EXPECTED AT CRITICALITY A-6-0 Time #Qv.a Date :!.J I£/ Time Nou.J Boron Cone. 8 J 9 ppm PowerfOO%

Burnup LOJ 000 (MWDIMTU)

Bum up (Olooo (MWDIMTU)

Xenon to&% (Use Fig QEj) or N/A) Samarium I 00 % (Use Fig @r N/A) Control Rod Position A "Z.l-7 c 2.27 B 'lt] 0 2!.., Ill Boron Concentration (Part A, Column I) Xenon 0% (Use Fig N/A) Samarium I l % (Use or N/A) Control Rod Position A 1 c e 2.1. '1-o .rofl Effective Boron Concentration Ill X I 7 s-o ppm -B. Reactivity Balance -(Record absolute values in Columns I and II) (I) (II) Reactivity Defects Prior to Shutdown Expected at Criticar 1. Power(Fig 2"' 00 OR ConsuH Rx En r 2. Control Rods (Circle Fig. (Fig. CB-24A, 4B 24C cr's-OR Consult Rx n r 0 em 3. Xenon

'270\ 0 4. Samarium (Fig. G,30*pcm 8S \-ltocm 5. Reactivity Change (Sum of 1-4) =

e"' -. vt -l: 'M'"' (;"' ), Y"' DATA SHEET 1: FORM ECP-1 Unit 1 BVPS-SBS Operating Procedures PERFORMING AN ESTIMATED CRITICAL POSITION CALCULATION 10M-50.4.F Revision 6 Page 18 of 30 C. Critical Boron Concentration Reactivity Change (8.5) (VI) Differential Boron Worth (Fig. CB-20) (VII) Boron Change (I)+ (II) Jr. 1.1 Eff. Boron Cone. At Shutdown (VIII) Eff. Boron Cone. For Startup lj f 7 Eff. Boron Cone. For B-10 Correction Factor Boron Concentration Startup for Criticality for Startup (Part C, Column V, line 2) (from Rx Eng) (VI)+ (VII) tl\( ppm 0 .ct 00 1'1 '3 ppm D. Estimated Rod Position Correction (I) (II) (Ill) (IV) Boron Sample Boron Cone. For Boron Deviation Differential Boron Startup C.1.k (I) -(II) Worth (Fig. CB-20) pcm ppm ppm (:t) ppm (-) ppm (V) (VI) (VII) (VIII) Rod Worth Rod Worth Corrected Rod Worth Carr Critical Rod Pos. Correction Expected At Expected At Criticality (Circle Figure Used) (Fig CB-24A, 24B, 24C (Ill) X (IV) Criticality (B.2) (V) +(VI) OR Consult Rx Engr) (+/-) pcm pcm (-) pcm Steps DATA SHEET 1: FORM ECP-1 RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 1/2-ADM-130 l.F04 Page 3 of7 Revision 1 I JPM NUMBER: 1AD-048 JPM REVISION:

O JPM TITLE: Determine Availability For Call-in (3 ROs) SRO ONLY KIA

REFERENCE:

2.1.3 3.9 TASK ID: 0481-002-03-043 JPM APPLICATION:

i:8J REQUALIFICATION D FAULTED JPM i:8J INITIAL EXAM 0 TRAINING i:8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: I:8J Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC I:8J Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS ')erformer Name: Performer SSN: Time D Yes Allotted 15 Minutes Actual minutes Critical:

I:8J No Time: Time: D SAT JPM RESULTS: D UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: I Evaluator Signature:

RTL#A5.640U 1/2-ADM-130l.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET 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. Classroom Both Units have been in Mode 1 for the past 100 days. Today is 6114/14. The daylight RO for 6/15/14 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 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on 6/15/14. The available RO replacements have the listed work hour history. As the Unit Supervisor, determine which one(s), if any ofthe 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 6115114 without violating the 10CFR 26 Work Hour Limits specified in LP-4011, FENOC Work Hour Control. Explain why or why not. Document your results on the sheet provided.

NOP-LP-4011, FENOC Work Hour Control, Rev. 7 Calculator.

Working hour history; NOP-LP-4011, FENOC Work Hour Control, Rev. 7 RTL#A5.640U 1/2-ADM-130l.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

Both Units have been in Mode 1 for the past 100 days. Today is 6/14/14. The daylight RO for 6/15/14 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 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on 6/15/14. 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 6/15/14 without violating the 10CFR 26 Work Hour Limits specified in LP-4011, FENOC Work Hour Control. Explain why or why not. Document your results on the sheet provided.

D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-130 l.F04 Page 6 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-048 JPM REVISION:

O JPM TITLE: Determine Availability For Call-in (3 ROs) SRO ONLY STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => 1. Evaluate work hour history. 1.1 EVALUATOR CUE: PROVIDE WORK HISTORY SHEET (LAST PAGE OF JPM) START TIME: ______ _ Compares work hour history against NOP-LP-4011, FENOC Work Hour Control requirements of section 4.2. COMMENTS:

2.C Determines working hour 2.1C Determines that RO Bill may NOT be called in. limit will be exceeded for RO 2.2C Determines that RO Bill will not have a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months Bill, and documents on the sheet provided.

2.3 break between successive work periods. Determines that RO Bill 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 on 6115. 2.4C Documents the result in the space provided.

COMMENTS:

RTL#A5.640U 112-ADM-130l.F04 Page 7 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: lAD-048 JPM REVISION:

O JPM TITLE: Determine Availability For Call-in (3 ROs) SRO ONLY STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT =:> 3.C Determines working hour 3 .1 C limit will be exceeded for RO 3.2C Joe, and documents on the Determines that RO Joe may NOT be called in. 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 days. sheet provided.

3.3C Documents the result in the space provided.

4.C Determines working hour limit will NOT be exceeded for RO Sam, and documents on the sheet provided.

COMMENTS:

4.1C Determines that RO Sam may be called in. 4.2C Determines that RO Sam meets all ofthe call-in requirements 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 /0 = Turnover time Joe, Sam, and Bill are all 8-hour Operations Shift workers. Date Joe Sam Bill 5/18/14 through Vacation Vacation Vacation 6/7/14 6/8/14 OFF 0600-1400 1400-2200 T/0 20 min T/0 20 min 6/9/14 0600-1800 0600-1800 1400-2200 T/0 20 min T/0 20 min T/0 20 min 6/10/14 0600-1800 1000-2200 OFF T/0 20 min T/0 20 min 6/11/14 0600-1800 1400-2200 OFF T/0 20 min T/0 20 min 6/12114 0600-1800 1400-2000 0600-1400 T/0 20 min T/0 20 min T/0 20 min 6/13/14 0600-1800 0600-1400 1100-2200 T/0 20 min T/0 20 min T/0 20 min 6/14114 0600-1800 0600-1800 0900-2100 T/0 20 min T/0 20 min T/0 20 min 6/15/14 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 5118114 through Vacation Vacation Vacation 6/7114 6/8/14 OFF 0600-1400 1400-2200 T/0 20 min T/0 20 min 6/9114 0600-1800 0600-1800 1400-2200 T/0 20 min T/0 20 min T/0 20 min 6110/14 0600-1800 1000-2200 OFF T/0 20 min T/0 20 min 6/11114 0600-1800 1400-2200 OFF T/0 20 min T/0 20 min 6112114 0600-1800 1400-2000 0600-1400 T/0 20 min T/0 20 min T/0 20 min 6/13114 0600-1800 0600-1400 1100-2200 T/0 20 min T/0 20 min T/0 20 min 6/14114 0600-1800 0600-1800 0900-2100 T/0 20 min T/0 20 min T/0 20 min 6/15/14 OFF OFF OFF RESULTS: 1. RO Bill may NOT be called in. He will not have a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months break between successive work periods. (NOTE: 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 on 8115-not required for full credit). 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 OPERATIONS JOB PERFORMANCE MEASURE 112-ADM-130 1.F04 Page 3 of7 Revision 1 I JPM NUMBER: 1AD-041 JPM REVISION:

0 JPM TITLE: Perform a Risk Assessment

[1FW-P-3A Maintenance] (SRO Only) KIA

REFERENCE:

2.2.17 3.8 TASK ID: 1300-027-03-023 JPM APPLICATION:

[gj REQUALIFICATION D FAULTEDJPM

[gj INITIAL EXAM [gj TRAINING [gl ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: [gl Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC [gl Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: rime D Yes Allotted 15 minutes Actual minutes Critical:

[gl No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-041 JPM REVISION:

0 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Perform a Risk Assessment

[1FW-P-3A Maintenance] (SRO Only) EVALUATOR DIRECTION SHEET Determines Risk Level is ORANGE and the Director of Site Operations (or designee) is the required approver for this condition.

Classroom

The Unit is in Mode 1.

PRA Risk & Traffic Light are GREEN.

Protected Train is "B".

Currently the Unit is in Nuclear Safety YELLOW Risk due to ongoing scaffold erection over the operable # 1 Emergency Diesel Generator (EDG).

Auxiliary Feedwater Pump 1FW-P-3A, will be taken out of service for repairs to address increasing pump vibrations.

The planned repairs will render the pump inoperable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Weather conditions are stable.

The electrical grid is stable. As Shift Manager you are to evaluate the risk level based on initial plant conditions for upcoming activities (1FW-P-3A repairs) AND determine who must approve this risk level in accordance with OP-1007, "Risk Management".

Report the results of your risk assessment and required approver of this risk level in the "Candidate Answer" Box (provided on candidate direction sheet) NOP-OP-1007, "Risk Management", Rev. 18 Technical Specifications Beaver Valley Power Station Units 1 & 2 None NOP-OP-1007, "Risk Management", Rev. 18 Technical Specifications Beaver Valley Power Station Units 1 & 2 (Need to be available in the event the candidate wants to reference)

RTL#A5.640U 1/2-ADM-130 l.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The Unit is in Mode 1.

PRA Risk & Traffic Light are GREEN.

Protected Train is "B".

Currently the Unit is in Nuclear Safety YELLOW Risk due to ongoing scaffold erection over the operable # 1 Emergency Diesel Generator (EDG).

Auxiliary Feedwater Pump 1FW-P-3A, will be taken out of service for repairs to address increasing pump vibrations.

The planned repairs will render the pump inoperable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Weather conditions are stable.

The electrical grid is stable. INITIATING CUE: As Shift Manager you are to evaluate the risk level based on initial plant conditions for upcoming activities (1FW-P-3A repairs) AND determine who must approve this risk level in accordance with OP-1007, "Risk Management".

Report the results of your risk assessment and required approver of this risk level in the "Candidate Answer" Box (provided on candidate direction sheet) D D D D CANDIDATE ANSWER(S):

At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130l.F04 Page 6 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-041 I JPM REVISION:

0 JPM TITLE: Perform a Risk Assessment

[1FW-P-3A Maintenance] (SRO Only) STANDARD (Indicate "S" FOR SAT or "U" FOR START TIME: ______ _ EVALUATOR CUE: Provide a copy ofNOP-OP-1 007, "Risk Management".

1. Refers to NOP-OP-1 007, "Risk 1.1 Refers to NOP-OP-1007.

Management" provided.

2.C Refers to Attachment 3, Risk Assessment Worksheet, to determine risk. COMMENTS:

EVALUATOR NOTE: The candidate may want to refer toTS 3.7.5 as part of this JPM step. Ensure Technical Specifications Beaver Valley Power Station Units 1 & 2 is available for reference.

TS 3.7.5 Condition B applies since 1FW-P-3A is inoperable.

Condition D requires a plant shutdown if 1FW-P-3A cannot be returned to service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The 50% time limit is applicable since the action is less than 14 days, not the 75% limit, which is for> 14 day action statements.

2.1 C Determines that this activity is ORANGE risk level. This is based on Attachment 3, Section E.5 answer is YES because 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is greater than half of the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months allowed Technical Specification (TS) Action Statement for any TS which requires a Unit Shutdown if not exited. 2.2 Records approver in the candidate answer box of the candidate direction sheet. COMMENTS:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 7 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 AD-041 I JPM REVISION:

0 JPM TITLE: Perform a Risk Assessment

[1FW-P-3A Maintenance] (SRO Only) STEP ( "C" Denotes CRITICAL STEP) 3.C Refers to Attachment 2, Plant Risk Matrix or to section 4.3.3.3, to determine required approval.

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 3 .1 C Determines that based on an Orange Risk, the Director of Site Operations (or designee) is the required approver for this risk level. 3.2 Records approver in the candidate answer box of the candidate direction sheet. COMMENTS:

EVALUATOR CUE: When the candidate determines risk level and approver, This JPM is COMPLETE.

STOP TIME: ______ _

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE l/2-ADM-1301.F04 Page 3 of7 Revision I I JPM NUMBER: 1AD-042 JPM REVISION:

0 JPM TITLE: Determine Compensatory Actions for RM-P-1GW-108 and 02A-1GW-110-1 Being OOS. (SRO ONLY) KIA

REFERENCE:

2.3.11 4.3 TASK ID: 1300-029-03-023 1:8:] INITIAL EXAM 1:8:] TRAINING JPM APPLICATION:

1:8:] REQUALIFICATION D FAULTED JPM 1:8:] ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: 1:8:] Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC 1:8:] Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 20 Minutes Actual minutes Critical:

1:8:] No Time: Time: D SAT JPM RESULTS: D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 112-ADM-130l.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-042 JPM REVISION:

0 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Determine Compensatory Actions for RM-P-1GW-108 and 02A-1GW-110-1 Being OOS. (SRO ONLY) EVALUATOR DIRECTION SHEET The compensatory actions required are determined to be: At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months take grab samples and analyze for Oxygen concentration AND, provided at least two independent samples of the tank's content are analyzed and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup Classroom A batch discharge of Gaseous Waste Decay Tank 1GW-TK-1A is to be performed per 10M-19.4.E, "Decay Tank Discharge".

It is desired to fill the Gaseous Waste Decay Tank 1GW-TK-1B in accordance with 10M-19.4.G, "Transfer Waste Gas from Unit 1 Surge Tank to Unit 1 Decay Tank".

The plant is operating at 1 00% power with all system in NSA.

Gross Activity of the primary coolant is 75 uCi/ml.

Gaseous Waste Decay Tank (1GW-TK-1A) pressure is 60 psig and slowly lowering due to the discharge.

Gaseous Waste Decay Tanks (1GW-TK-1B, 1C) pressures are 8 psig and STABLE.

Gaseous Waste Surge Tank (1GW-TK-2) pressure is 62 psig and slowly RISING.

The Gaseous Waste Radiation Monitor [RM-1GW-108]

Sample Pump [RM-P-1GW-108]

is out of service (OOS).

Oxygen Analyzer (02A-1GW-110-1 is OOS.

Oxygen Analyzer (02A-1GW-110-2) is OPERABLE.

For these plant conditions, determine the REQUIRED LRM/ODCM compensatory actions for the Decay Tank Discharge and for filling the Gaseous Waste Decay Tank. Document any compensatory actions in the block below (provided on the candidate direction sheet). LRM 3.3.12, Rev. 56, TS 5.5.8, Amend 278/170 1/2 ODCM Section 3.0.3, Rev. 11 OM Fig. 19-1 Rev. 17, 10M-43.5, Figure 43-5 Rev 8 None 10M-19.5, Figure 19-1, 10M-43.5, Figure 43-5, Unit 1 LRM 1/2-0DCM, Section 3.0.3 RTL#A5.640U 112-ADM-130l.F04 Page 5 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

A batch discharge of Gaseous Waste Decay Tank lGW-TK-lA is to be performed per 10M-19.4.E, "Decay Tank Discharge".

It is desired to fill the Gaseous Waste Decay Tank 1GW-TK-1B in accordance with 10M-19.4.G, "Transfer Waste Gas from Unit 1 Surge Tank to Unit 1 Decay Tank".

The plant is operating at 100% power with all system in NSA.

Gross Activity of the primary coolant is 75 uCi/ml.

Gaseous Waste Decay Tank (1GW-TK-1A) pressure is 60 psig and slowly lowering due to the discharge.

Gaseous Waste Decay Tanks (1GW-TK-1B, 1C) pressures are 8 psig and STABLE.

Gaseous Waste Surge Tank (IGW-TK-2) pressure is 62 psig and slowly RISING.

The Gaseous Waste Radiation Monitor [RM-lGW-108]

Sample Pump [RM-P-1GW-108]

is out of service (OOS).

Oxygen Analyzer (02A-1GW-110-1 is OOS.

Oxygen Analyzer (02A-1GW-110-2) is OPERABLE.

INITIATING CUE: For these plant conditions, determine the REQUIRED LRM/ODCM compensatory actions for the Decay Tank Discharge and for filling the Gaseous Waste Decay Tank. Document any compensatory actions in the block below. Required compensatory actions, if any: D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130l.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-042 JPM REVISION:

0 JPM TITLE: Determine Compensatory Actions for RM-P-1GW-108 and 02A-1GW-110-1 Being OOS. (SRO ONLY) STANDARD START TIME: ______ _ EVALUATOR CUE: Provide the Candidate with the Candidate Direction Sheet and a current copy of OM Fig. 19-1, OM Fig 43.5, LRM, AND 112 ODCM Section 3.0.3. EVALUATOR NOTE: These steps may be performed in any order. EVALUATOR NOTE: The next step may not be necessary.

The candidate may already be familiar enough with the system to know the impact ofRM-P-1GW-108 being OOS. 1.1 Determines the impact of 1.1 Refers to OM Fig. 19-1 & OM Fig 43-5 and determines that Gaseous Waste Gas Monitor (RM-1 GW -1 08B) is out of service as a result of lGW-108 being OOS. RM-P-1GW-108 being OOS. COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 7 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-042 JPM REVISION:

0 JPM TITLE: Determine Compensatory Actions for RM-P-1GW-108 and 02A-1GW-110-1 Being OOS. (SRO ONLY) STEP STANDARD ( "C" Denotes CRITICAL STEP) 2.C Determines 1/2 ODCM 2.1 compensatory actions for Refers to 112 ODCM Section 3.0.3, Att. F item 1, Table 3.3-13 Item 1 Gaseous Waste/ Process Vent System (PV -1/2) Noble Gas Activity Monitor on page 38. Gaseous Waste Gas Monitor (RM-1GW-108B) being out of service. 3.C Determines LRM compensatory actions for Oxygen Analyzer (02A-1GW-110-1) being OOS. 2.2C Determines that per action 27, the Decay Tank Discharge may be initiated provided at least two independent samples of the tank's content are analyzed and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup. COMMENTS:

3.1 Refers to LRM 3.3.12 Condition B.l. 3 .2C Determines at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months take grab samples and analyze for oxygen content. COMMENTS:

EVALUATOR CUE: That completes this JPM. STOP TIME: ______ _

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 1/2-ADM-130 l.F04 Page 3 of 9 Revision I I JPM NUMBER: 1 AD-046 JPM REVISION:

0 JPM TITLE: Classify an Emergency Event (Scenario Specific)

Kl A

REFERENCE:

2.4.41 4.6 TASK ID: 1350-004-03-023 INITIAL EXAM TRAINING JPM APPLICATION: REQUALIFICA TION D FAULTED JPM ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: Perform D Plant Site D Annual Requal Exam D BVT D Simulate Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: fime Yes Allotted 15 Minutes Actual minutes Critical:

D No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of 9 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1AD-046 JPM REVISION:

0 JPM TITLE: Classify an Emergency Event (Scenario Specific)

TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET The correct EPP classification is made for the associated scenario AND all "critical" steps of the initial notification form are correctly completed.

Simulator The simulator scenario just completed.(1LOT14 NRC Exam) As the Unit Supervisor, you are to classify the events in the scenario just completed in accordance with EPP/I-1a, 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 "Simulator" Unit 2 is at 100% steady state power Wind direction at 150' is 135° Wind speed at 35' is 15 mph THIS IS A TIME CRITICAL JPM EPP /I -1 a, Recognition and Classification of Emergency Conditions, Rev. 16 112-EPP-IP-l.l.F01, FENOC Nuclear Power Plant Initial Notification Form Rev. 6 None EPP/I-1a, Recognition and Classification ofEmergency Conditions, Rev. 16; 112-EPP-IP-l.l.F01, FENOC Nuclear Power Plant Initial Notification Form Rev. 6 RTL#A5.640U l/2-ADM-130l.F04 Page 5 of 9 Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The simulator scenario just completed.(1LOT14 NRC Exam) INITIATING CUE: As the Unit Supervisor, you are to classify the events in the scenario just completed in accordance with EPP/I-1a, Recognition and Classification of Emergency Conditions AND complete the initial notification form. D D D D For the purpose of filling out the initial notification form the following conditions exist: * * *

The code word is "Simulator" Unit 2 is at 100% steady state power Wind direction at 150' is 135° Wind speed at 35' is 15 mph THIS IS A TIME CRITICAL JPM At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U l/2-ADM-1301.F04 Page 6 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 AD-046 JPM REVISION:

0 JPM TITLE: Classify an Emergency Event (Scenario Specific) 1.C Classify the event in accordance with the Emergency Plan. Step 1 (continued on the next page) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> START TIME: ______ _ EVALUATOR NOTE: The Candidate is being evaluated on classifying the events in the scenario just completed.

(1LOT14 NRC Exam) It may be necessary to review the events before beginning the JPM. 1.1 C Candidate correctly classifies the event.

Scenario #1: Site Area Emergency SS3 Automatic and Manual Trip Actions taken from the Control Room Bench Boards failed to Shutdown the Reactor. An Automatic reactor trip failed to shutdown the reactor as indicated by reactor power >5%. AND Manual trip actions taken at the CONTROL ROOM benchboards failed to shutdown the reactor as indicated by reactor power >5%.

Scenario #2 Alert F A1 Any Loss or any Potential Loss of either Fuel Clad or RCS. RUPTURED SG results in an SI actuation.

Scenario #3 Alert HA4 FIRE or EXPLOSION affecting the operability of plant safety systems required to establish or maintain safe shutdown.

FIRE or EXPLOSION resulting in EITHER of the following:

VISIBLE DAMAGE to ANY structures in Table H-1 containing safety systems or components.

CONTROL ROOM indication of degraded performance of those safety systems. (Steam Break inside Containment)

RTL#A5.640U 112-ADM-130 l.F04 Page 7 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: lAD-046 JPM REVISION:

0 JPM TITLE: Classify an Emergency Event (Scenario Specific)

STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S!U

Scenario #4 Alert F Al Any Loss or any Potential Loss of either Fuel Clad or RCS. RCS leak exceeding the capacity of one charging pump in the normal charging mode. OR Alert SA3 Automatic trip failed to shutdown the reactor and Manual Actions taken from the Control Room Bench Boards are successful in shutting down the reactor. COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 8 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: IAD-046 JPM REVISION:

0 JPM TITLE: Classify an Emergency Event (Scenario Specific)

STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 2.C Completes the initial 2.1 Places the following information on the space notification form. provided on the initial notification form:

C Item 1 places a checkmark in BV 1 block and records 0% power for Unit 1 and 100% power for Unit 2.

Places/verifies the word "Simulator" in the code word space.

Item 2 places a checkmark in the "A Drill" box .

Item 3, places a checkmark in box 3.a

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 current time in the declaration time space, places the date in the date space.

C Item 3 places the appropriate EAL number in the EAL number space (as identified in step 1 of the JPM above).

Item 4 places the appropriate EAL description in the space provided (as identified in step 1 of the JPM above).

Item 5 places checkmark(s) in the none or in the non-routine AND airborne radiological release in progress due to this event box.

C Item 6.c places a checkmark in NONE box for the PAR.

C Item 7 places 135° and 15 mph in the wind speed and direction spaces. 2.2 Places candidate name in the approved space. COMMENTS:

RTL#A5.640U 112-ADM-130l.F04 Page 9 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 AD-046 JPM REVISION:

0 JPM TITLE: Classify an Emergency Event (Scenario Specific)

STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT :::> S/U EVALUATOR NOTE: Refer to Answer Key for initial notification form critical steps. TERMINATING CUE: That completes this JPM STOP TIME: ______ _

FENOC NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM USE FOR:

INITIAL CLASSIFICATIONS,

CHANGES IN CLASSIFICATIONS, STATE I COUNTY USE ONLY DATE: TIME: Beaver Valley

CHANGES IN PROTECTIVE ACTION RECOMMENDATIONS.

MESSAGE NO: 1/2-EPP-IP-1.1.F01 Rev. 6

EVENT TERMINATION

1. This is applicable to : 1tJ BVPS Unit 1 OR 0 BVPS Unit 2 OR 0 Both BVPS Units 1 & 2 Current Reactor Power Levels are: Unit 1: 0 %, Unit 2: 100 %. Code Word is: SIMULATOR

2. This is: 3. ltJ a. A(n) D An Actual Emergency 0 GENERAL ltJ A Drill ltJ SITE AREA EMERGENCY 0 ALERT 0 UNUSUAL EVENT was declared at: NOW on TODAY based on EAL(s): (TIME) (DATE) D b. The Emergency situation has been terminated at: on (TIME) (DATE) D c. The Protective Action Recommendation is being changed at: on (TIME) (DATE) 4. Brief non-technical description of event: Site Area Emergency -Automatic and Manual Trip Actions taken from the Control Room Bench Boards failed to Shutdown the Reactor. 5. The radiological conditions are: D a. A non-routine release of radioactive material, as a result of this event, is in progress.

The release is: D Airborne D Liquid D b. The release of radioactive material associated with this event has been terminated.

ltJ c. NO Radiological Release is in progress as a result of this event. 6. Utility Protective Action Recommendations (PAR's): D a. Evacuation:

D N/A D 2 Miles-360° D 5 Miles-360° D 10 Miles-360° AND Evacuate Downwind Wedge D N/A D 5 Miles (check applicable sectors) D 10 Miles (check applicable sectors) DA DB oc DD DE OF OG DH OJ OK DL OM ON DP Do DR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

D b. Sheltering:

D N/A D Remainder of 10 Mile EPZ D 10 Mile EPZ D 0-2 Miles 360° and 5 Mile Downwind Wedge (check applicable sectors) DA DB oc OJ OK OL OD OM DE ON OF OP OG Do DH OR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

ltJ c. None 7. Wind Direction is FROM: 135 ° degrees at 150' Wind Speed is: __ 1.....,5,___

mph at 35' Callback number is 724-643-8000 For Utility Use Only Approved:

NAME FENOC NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM USE FOR:

INITIAL CLASSIFICATIONS,

CHANGES IN CLASSIFICATIONS, STATE I COUNTY USE ONLY DATE: TIME: Beaver Valley

CHANGES IN PROTECTIVE ACTION RECOMMENDATIONS.

MESSAGE NO: 1/2-EPP-IP-1.1.F01 Rev. 6

EVENT TERMINATION

1. This is applicable to : li1 BVPS Unit 1 OR 0 BVPS Unit2 Current Reactor Power Levels are: Unit 1: 0 %, Unit 2: 100 %. OR D Both BVPS Units 1 & 2 Code Word is: SIMULATOR

2. This is: 3. li1 a. A(n) D An Actual Emergency 0 GENERAL li1 A Drill 0 SITE AREA EMERGENCY li1 ALERT 0 UNUSUAL EVENT was declared at: on TODAY (DATE) based on EAL(s): (TIME) D b. The Emergency situation has been terminated at: on (TIME) (DATE) D c. The Protective Action Recommendation is being changed at: on (TIME) (DATE) 4. Brief non-technical description of event: Any Loss or any Potential Loss of either Fuel Clad or RCS. RUPTURED SG results in an Sl actuation.

5. The radiological conditions are: li1 a. A non-routine release of radioactive material, as a result of this event, is in progress.

The release is: li1 Airborne D Liquid D b. The release of radioactive material associated with this event has been terminated.

D c. NO Radiological Release is in progress as a result of this event. 6. Utility Protective Action Recommendations (PAR's): D a. Evacuation:

D N/A D 2 Miles -360° D 5 Miles -360° D 10 Miles -360° AND Evacuate Downwind Wedge D N/A D 5 Miles (check applicable sectors) D 10 Miles (check applicable sectors) DA DB DC DD DE OF DG DH OJ OK DL OM ON DP Do DR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

D b. Sheltering:

D N/A D Remainder of 10 Mile EPZ D 10 Mile EPZ D 0-2 Miles 360° and 5 Mile Downwind Wedge (check applicable sectors) DA DB DC OJ OK DL DD OM DE ON OF DP DG DO DH DR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

li1 c. None 7. Wind Direction is FROM: 135 o degrees at 150' Wind Speed is: __ 1_,_,5:___

mph at 35' Callback number is 724-643-8000 For Utility Use Only Approved:

NAME FENOC NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM USE FOR:

INITIAL CLASSIFICATIONS,

CHANGES IN CLASSIFICATIONS, STATE I COUNTY USE ONLY DATE: TIME: Beaver Valley

CHANGES IN PROTECTIVE ACTION RECOMMENDATIONS.

MESSAGE NO: 112-EPP-IP-1.1.F01 Rev. 6

EVENT TERMINATION

1. This is applicable to : 1iJ BVPS Unit 1 OR 0 BVPS Unit2 Current Reactor Power Levels are: Unit 1: 0 %, Unit 2: 100 %. OR D Both BVPS Units 1 & 2 Code Word is: SIMULATOR

2. This is: 3. lt'J a. A(n) D An Actual Emergency 0 GENERAL lt'J A Drill 0 SITE AREA EMERGENCY lt'J ALERT 0 UNUSUAL EVENT was declared at: NOW on TODAY based on EAL(s): _H ..... A::-:4_,__

__ (TIME) (DATE) D b. The Emergency situation has been terminated at: on (TIME) (DATE) D c. The Protective Action Recommendation is being changed at: on (TIME) (DATE) 4. Brief non-technical description of event: FIRE or EXPLOSION affecting the operability of plant safety systems required to establish or maintain safe shutdown.

5. The radiological conditions are: D a. A non-routine release of radioactive material, as a result of this event, is in progress.

The release is: D Airborne D Liquid D b. The release of radioactive material associated with this event has been terminated.

lt'J c. NO Radiological Release is in progress as a result of this event. 6. Utility Protective Action Recommendations (PAR's): D a. Evacuation:

D N/A D 2 Miles-360° D 5 Miles-360° D 10 Miles-360° AND Evacuate Downwind Wedge D N/A D 5 Miles (check applicable sectors) D 10 Miles (check applicable sectors) DA DB oc Do DE OF DG DH OJ OK DL OM ON DP Do DR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

D b. Sheltering:

D N/A D Remainder of 10 Mile EPZ D 10 Mile EPZ D 0-2 Miles 360° and 5 Mile Downwind Wedge (check applicable sectors) DA DB DC OJ OK DL DD OM DE ON OF DP DG Do DH DR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

lt'J c. None 7. Wind Direction is FROM: 135 o degrees at 150' Wind Speed is: __

mph at 35' Callback number is 724-643-8000 For Utility Use Only Approved:

NAME FENOC NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM USE FOR:

INITIAL CLASSIFICATIONS,

CHANGES IN CLASSIFICATIONS, STATE I COUNTY USE ONLY DATE: TIME: Beaver Valley

CHANGES IN PROTECTIVE ACTION RECOMMENDATIONS.

MESSAGE NO: I/2-EPP-IP-1.1.F01 Rev. 6

EVENTTERMINATION

1. This is applicable to : 1i::f BVPS Unit 1 OR D BVPS Unit2 Current Reactor Power Levels are: Unit 1: 0 %, Unit 2: 100 %. OR 0 Both BVPS Units 1 & 2 Code Word is: SIMULATOR

2. This is: li:1 A Drill 3. li:1 a. A(n) D An Actual Emergency 0 GENERAL 0 SITE AREA EMERGENCY li:1 ALERT 0 UNUSUAL EVENT was declared at: NOW on TODAY based on EAL(s): _,F:....:.A.:...:1"--(TIME) (DATE) D b. The Emergency situation has been terminated at: on (TIME) (DATE) D c. The Protective Action Recommendation is being changed at: on (TIME) (DATE) 4. Brief non-technical description of event: Any Loss or any Potential Loss of either Fuel Clad or RCS. RCS leak exceeding the capacity of one charging pump in the normal charging mode. 5. The radiological conditions are: D a. A non-routine release of radioactive material, as a result of this event, is in progress.

The release is: D Airborne D Liquid D b. The release of radioactive material associated with this event has been terminated.

1i:1 c. NO Radiological Release is in progress as a result of this event. 6. Utility Protective Action Recommendations (PAR's): D a. Evacuation:

D N/A D 2 Miles-360° D 5 Miles-360° D 10 Miles-360° AND Evacuate Downwind Wedge D N/A D 5 Miles (check applicable sectors) D 10 Miles (check applicable sectors) DA DB De DD DE OF DG DH OJ OK DL OM ON DP oa DR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

D b. Sheltering:

D N/A D Remainder of 10 Mile EPZ D 10 Mile EPZ D 0-2 Miles 360° and 5 Mile Downwind Wedge (check applicable sectors) DA DB DC OJ OK DL DD OM DE ON OF DP DG oa DH DR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

1i:1 c. None 7. Wind Direction is FROM: 135 o degrees at 150' Wind Speed is: __ 1,_,5,____

mph at 35' Callback number is 724-643-8000 For Utility Use Only Approved:

NAME R'i'L#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 112-ADM-1301.F04 Page 3 of8 Revision 1 JPM NUMBER: 1 CR-072 JPM REVISION:

7 JPM TITLE: Shift from Main Feedwater Regulating Valves to Bypasses KIA

REFERENCE:

059Kl.04 3.4/3.4 TASK ID: 0241-004-01-013

[8] INITIAL EXAM D TRAINING JPM APPLICATION:

[8] REQUALIFICATION D FAULTEDJPM 0 ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: [8] Perform D Plant Site D Annual Requal Exam D BVT D Simulate [8] Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 15 Minutes Actual minutes Critical:

[8] No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RtL#A5.640U 112-ADM-130 l.F04 Page 4 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-072 JPM REVISION:

7 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Shift from Main Feedwater Regulating Valves to Bypasses EVALUATOR DIRECTION SHEET FCV-1FW-489, "1B" S/G FW Bypass FCV has been placed in service in automatic mode and FCV-1FW-488, 1B Main Feedwater Reg Valve is Closed and placed in Manual. Simulator The plant is at power and conducting a normal shutdown.

All systems are in normal arrangement for this plant condition.

Your supervisor directs you to transfer feed water flow control for the 'B' S/G from the Main Feedwater Regulating Valve to the Bypass Valve. You are to use 10M-52.4.R.1.F, "Station Shutdown From 100% Power to Mode 5", Attachment 10 beginning at step B.2.a. 1 OM-52.4.R.1.F, "Station Shutdown From 100% Power to Mode 5", Revision 28, Attachment

10. None 10M-52.4.R.l.F, "Station Shutdown From 100% Power to Mode 5", Revision 28, Attachment 10, place kept up to step B.2.a.

RTL#A5.640U 1/2-ADM-130 l.F04 Page 5 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The plant is at power and conducting a normal shutdown.

All systems are in normal arrangement for this plant condition.

INITIATING CUE: Your supervisor directs you to transfer feedwater flow control for the 'B' S/G from the Main Feedwater Regulating Valve to the Bypass Valve. You are to use "Station Shutdown From 100% Power to Mode 5", Attachment 10 beginning at step B.2.a. D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

R"fL#A5.640U 1/2-ADM-130 l.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-072 JPM REVISION:

7 JPM TITLE: Shift from Main Feedwater Regulating Valves to Bypasses STEP ( "C" Denotes CRITICAL STEP ) 1. Reviews procedure.

2.C Place FCV-1FW-489, "1B S/G FW Bypass FCV", controller in MANUAL AND slowly Open the 1B Bypass Valve. STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT::) SIMULATOR SETUP: Start with IC-27 (or equivalent), with 'B' Main Feedwater Regulating Valve in service. Ensure 'B' Bypass FCV is closed and MOV-155B is open. To cause some leakby: TRG 1 'X09D097M

<= 0.03' lOR XS05A04 (1 5) 0 IMF FWM07B (1 0) 4 EVALUATOR CUE: Provide candidate with place kept copy of 10M-52.4.R.l.F, "Station Shutdown From 100% Power to Mode 5", Revision 28, Attachment

10. Place simulator in RUN when candidate is ready to begin. START TIME: ______ _ 1.1 Reviews procedure provided.

COMMENTS:

2.1 Verifies FCV -1 FW -489 Manual red light-LIT; AUTO red light-NOT LIT. 2.2C Intermittently depresses the Bypass Control Valve FCV -1 FW -489 output pushbutton.

2.3 Verifies feed flow increases.

COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 7 of8 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-072 JPM REVISION:

7 JPM TITLE: Shift from Main Feedwater Regulating Valves to Bypasses STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 3. As the 1B Bypass FCV is 3.1 Verifies FCV-1FW-488, demand signal is decreasing being opened, close FCV-and "1B" S/G level is being maintained WITHIN 1FW-488, 1B Main Feedwater 60%to 70%. Reg Valve, in MANUAL OR AUTO to maintain "1B" S/G COMMENTS:

level WITHIN 60% to 70%. EVALUATOR NOTE: It is acceptable if candidate places [FCV-1FW-488]

controller in manual and intermittently closes valve. 4.C Continue to Open the 1 B 4.1C Intermittently depresses FCV-1FW-489

.._ Bypass FCV UNTIL the 1B pushbutton.

Main Feed Reg Valve is closed. 4.2 Verifies FCV -1 FW -489 % output signal is rising. 4.3 Verifies FCV -1 FW -488 GREEN light -LIT and RED light-NOT LIT. COMMENTS:

S.C WHEN the 1 B Main Feed S.lC Places FCV-1FW-488 controller to MAN. Reg Valve is fully closed, Verify the 1B Main Feed Reg 5.2 Verifies MAN RED light-LIT and AUTO WHITE Valve controller in MAN. light-NOT LIT. COMMENTS:

S/U RTL#A5.640U 1/2-ADM-130 l.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-072 JPM REVISION:

7 JPM TITLE: Shift from Main Feedwater Regulating Valves to Bypasses STEP ( "C" Denotes CRITICAL STEP ) 6. Observe Feedwater flow, steam flow and S/G level for evidence of leakage past the STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)=> 6.1 Identifies small step change in feed flow, steam flow remains stable. 1B Main Feed Reg Valve. 6.2 Places MOV-1FW-154B control switch to CLOSE. Close MOV-1FW-154B, 1B 6.3 Verifies green light-LIT and red light-NOT LIT. S/G Main Feedwater Isol Vlv. 7.C Place controller for the 1B Bypass FCV in AUTO AND Monitor S/G level AND flow. 6.4 Observes step change (reduction) of feedwater flow when MOV-1FW-154B fully closes. 6.5 Reports to US that there was evidence of leakby on FCV-1FW-488, a work request is needed. COMMENTS:

7.1C Places FCV-1FW-489 controller in AUTO. 7.2 Verifies MAN red light-NOT LIT and AUTO red light-LIT. 7.3 Determines S/G NR level is being maintained between 60% and 70%. COMMENTS:

EVALUATOR CUE: After the candidate verifies "B" S/G NR level being maintained state, "That completes this JPM." STOP TIME: ______ _

RTL#A5.640U 112-ADM-130 l.F04 Page 3 of 14 Revision 1 'JPM NUMBER: 1CR-658 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A 1 JPM REVISION:

0 I Kl A

REFERENCE:

068 A4.03 068 A4.04 073 A4.01 3.9 I 3.8 3.8 I 3.7 3.9 I 3.9 TASK ID: 0171-020-01-011 0171-016-01-013 0431-033-04-011 IZI INITIAL EXAM D TRAINING JPM APPLICATION:

IZI REQUALIFICATION

[8J FAULTED JPM 0 ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: IZI Perform D Plant Site D Annual Requal Exam D BVT D Simulate IZI 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 15 Minutes Actual minutes Critical:

IZI No Time: Time: JPM RESULTS: 0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS NameiSSN:

NameiSSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RJL#A5.640U EVALUATOR DIRECTION SHEET 1/2-ADM-1301.F04 Page 4 of14 Revision 1 TASK STANDARD:

Laundry and Contaminated Shower Drain Tank 6A discharge commenced, then isolated from Unit 1 Cooling Tower Blowdown by closing FCV-1LW-103 and securing 1LW-P-6A.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS:

RWDA-L for Laundry and Contaminated Shower Drain Tank 6A has been completed and approved 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

RM-RR-400, Radiation Monitor Recorder No. 4 Out of Service. INITIATING CUE: Your supervisor directs you to discharge Laundry and Contaminated Shower Drain Tank 6A in accordance with section IV.D of 10M-17.4.A, Laundry And Contaminated Shower Drains Subsystem Startup.

REFERENCES:

1 OM-17 .4.A, Laundry And Contaminated Shower Drains Subsystem Startup Rev. 5 10M-43.4.ACR, Local-High-High

([RM-1LW-116]

Liquid Waste Contaminated Drain Monitor) Rev. 5 1/20M-17.4A.D, Unit 1 Liquid Waste Discharge To Unit 1 Cooling Tower Blowdown Rev. 12 TOOLS: NONE HANDOUT: 10M-17.4.A, Laundry And Contaminated Shower Drains Subsystem Startup Rev. 5 place kept up to step IV.D including Attachment A. RWDA-L for discharging Laundry and Contaminated Shower Drain Tank 6A. 1/20M-17.4A.D, Unit 1 Liquid Waste Discharge To Unit 1 Cooling Tower Blowdown Rev. 12 place kept up to step IV.C.8. DO NOT HANDOUT 10M-43.4.ACR, Local-High-High

([RM-1LW-116] Liquid Waste Contaminated Drain Monitor) Rev. 5 until the student references the Control Room procedures.

RJ'L#A5.640U 112-ADM-130 l.F04 Page 5 of 14 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

RWDA-L for Laundry and Contaminated Shower Drain Tank 6A has been completed and approved 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago.

RM-RR-400, Radiation Monitor Recorder No. 4 Out of Service. INITIATING CUE: Your supervisor directs you to discharge Laundry and Contaminated Shower Drain Tank 6A in accordance with section IV.D of 10M-17.4.A, Laundry And Contaminated Shower Drains Subsystem Startup. D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RJL#A5.640U 1/2-ADM-130 1.F04 Page 6 of 14 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-658 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A

JPM REVISION:

0 STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 1. Review 10M-17.4.A, Laundry And Contaminated Shower Drains Subsystem Startup SIMULATOR SETUP:

Initialize Simulator

Raise 1LW-TK-6A level to 40% alpslaw( 1 )=807 5

IRF AUX111 (0 0) 0 (Close 1LW-74)

IRF AUX112 (0 0) 1 (Open 1LW-75)

IRF AUX118 (0 0) 1 (Open 1LW-101)

lOR XRID056M (1 0) 5.55 60

lOR XRI0056Y (1 50) 1

lOR XRI0056R (1 58) 1

IMF XN04071 (1 50) 1

IMF XN04072 (1 58) 1

TRGSET 1 'X13D036 <= 39'

Place RM-RR-400, Radiation Monitor Recorder No. 4 Out of Service.

Verify RM-1LW-116 Hi and Hi-Hi stpts match the values stated in the RWDA-L.

Remove the Caution Tag on LW-P-6A EVALUATOR CUE: Provide candidate a copy of 10M-17.4.A and RWDA-L for discharging Laundry and Contaminated Shower Drain Tank 6A. When candidate is ready to begin the JPM, Place the Simulator in RUN. START TIME: ______ _ 1.1 Reviews 10M -17.4 .A and verifies section IV .D is the correct step to begin. COMMENTS:

RTL#A5.640U l/2-ADM-130l.F04 Page 7 of14 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPMNUMBER:

1CR-658 JPM REVISION:

0 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu 2.C Stop [1LW-P-6A], 2.1C Places CS for 1LW-P-6A to STOP Laundry/Contaminated Shower 6A Drain Tk 2.2 Verifies GREEN light-LIT and RED light-NOT Transfer Pump 6A. LIT COMMENTS:

3. Verify Closed [TV-1LW-116], 3.1 Verifies TV -1 L W -116, Contaminated Drs Disch Hdr Contaminated Drs Disch Hdr High Rad Trip Vlv GREEN light -LIT and RED light High Rad Trip Vlv. (BB-A) -NOT LIT COMMENTS:

4. Open [1LW-83], 1LW-P-6A, 4.1 Requests Operator to Open 1 L W -83 Discharge Vlv for the pump being used for the discharge.

EVALUATOR CUE: (Aux. Bldg., 722') Role-play the Auxiliary Building Operator and report 1LW-83 is Open. COMMENTS:

5. Verify Open [1LW-85], 5.1 Requests Operator to verify Open 1 L W -85 Contaminated Drain Filters 2A EVALUATOR CUE: and 2B Inlet Isol Vlv. (Aux. Role-play the Auxiliary Building Operator and report Bldg., 722') 1 L W -85 is verified Open. COMMENTS:

}\TL#A5.640U 1/2-ADM-130l.F04 Page 8 of 14 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-658 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A JPM REVISION:

0 STEP ( "C" Denotes CRITICAL STEP ) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I S/U EVALUATOR CUE: Role-play the Unit Supervisor and inform student that Contaminated Drains Filter 2A is to be used. 6. If[1LW-FL-2A], Contaminated 6.1 Drains Filter 2A, is to be used, Requests Operator to verify Open 1 L W -86 and 1 L W-88 align the following valves as indicated: (Aux. Bldg. 722') 1) Verify Open [1LW-86], Cont Drains Filter 1LW-FL-2A, Inlet Isol Vlv. 2) Verify Open [1LW-88], Cont Drains Filter 1LW-FL-2A, Outlet Isol Vlv. 7. If [ 1 L W -FL-2B], Contaminated Drains Filter 2B, is to be used, align the following valves, as indicated: (Aux. Bldg., 722') 8. Verify Open [1LW-91], Cont Drains Filters Comb Outlet Isol Vlv. (Aux. Bldg., 722') EVALUATOR CUE: Role-play the Auxiliary Building Operator and report 1LW-86 and 1LW-88 are verified Open. COMMENTS:

7.1 N/A COMMENTS:

8.1 Requests Operator to verify Open 1L W -91 EVALUATOR CUE: Role-play the Auxiliary Building Operator and report 1 L W -91 is verified Open. COMMENTS:

RJL#A5.640U 112-ADM-130 1.F04 Page 9 of 14 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

lCR-658 I JPM REVISION:

0 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu 9. Open [1LW-92], RM-1LW-116, 9.1 Requests Operator to verify Open 1LW-92. 10. Inlet Isol Vlv. (Aux. Bldg., 722') If a flush of the discharge header to the floor drain is not desired, Close [1LW-321], RM-1LW-116, Flush Outlet Isol to Floor Drain. (Aux. Bldg., 722') EVALUATOR CUE: Role-play the Auxiliary Building Operator and report 1 L W -92 is Open. COMMENTS:

EVALUATOR CUE: Role-play the Unit Supervisor and inform student that a flush of the discharge header to the floor drain is not desired. 1 0.1 Requests Operator to Close 1 L W-3 21. EVALUATOR CUE: Role-play the Auxiliary Building Operator and report 1LW-321 is Closed. COMMENTS:

11. If a flush of the discharge 11.1 N/ A header is desired, perform the following:

COMMENTS:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 10 of 14 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE

JPMNUMBER:

1CR-658 I JPM REVISION:

0 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U 12. If required, Refer to 1OM-12.1 Verifies RM -1 L W -116 background reading is below 43.4.ACR, LOCAL HI-HI Hi alarm setpoint value of 1.2E 5 cpm. RM-1LW-116, Alarm Response Procedure, to 12.2 Determines no action required reduce background activity level. COMMENTS:

13. Verify Open [1LW-93], RM-13.1 Requests Operator to verify Open 1 L W -93. 1LW-116, Outlet Isol Vlv. (Aux. Bldg., 722') EVALUATOR CUE: Role-play the Auxiliary Building Operator and report 1 L W -93 is verified Open. COMMENTS:

14.C Start [1LW-P-6A], 14.1CPlaces CS for 1LW-P-6A to START. Laundry/Contaminated Shower 6A Drain Tk Transfer Pump 14.2 Verifies RED light-LIT and GREEN light-NOT 6A. LIT 14.3 Verifies TV -1 L W -116, Contaminated Drs Disch Hdr High Rad Trip Vlv RED light-LIT and GREEN light -NOT LIT COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page II of I4 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-658 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A JPM REVISION:

0 STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::::)

Stu 15.C Raise output on [AM-1LW-103], Contaminated Drains Disposal Flow Control, NOT to exceed the maximum discharge rate designated by the RWDA-L, AND Observe upscale indication on [FRC-1LW-103], Laundry And Contaminated Drains Flow Recorder. (VB-A) 16. Observe indication on [RM-1 L W -116], Contaminated Drains Disch Radiation Monitor, to verify proper response.

15.1 Verifies AM-1LW-103 controller in MAN. 15.2 Verifies MAN RED light-LIT and AUTO WHITE light-NOT LIT. 15.3C Intermittently depresses AM-1LW-103 A pushbutton to indicate .:s_15 GPM on FRC-1LW-103 (VB-A). EVALUATOR CUE: If candidate is discharging at a low flowrate, role-play the Unit Supervisor and inform candidate to discharge at a minimum of 10 gpm. COMMENTS:

FAULT STATEMENT:

Alternate Path begins here. Annunciator A4-71 Radiation Monitoring High, and A4-72 Radiation Monitoring High-High will alarm when tank level lowers to approx. 38". Candidate is expected to refer to 10M-43.4.ACR, High-High RM-1LW-116 Liquid Waste Contaminated Drain Monitor. 16.1 Observes indication on RM-1LW-116 EVALUATOR NOTE: Student may not observe RM-1 L W -116 IA W 1OM-17.4.A, prior to the High-High radiation monitor alarming.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 12 of14 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-658 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A JPM REVISION:

0 STEP ( "C" Denotes CRITICAL STEP) 17. Acknowledge and respond to annunciators A4-71 Radiation Monitoring High, and/or A4-72 Radiation Monitoring High. 18. Verify the alarm by pushing and releasing the Reset pushbutton on [RIS-1 L W -116] Liquid Waste Contam Dr Effluent Monitor at MON #4], Radiation Monitoring System Rack 4. a. Verify that the alarm is energized.

b. Mark [RM-RR-400], Radiation Monitor Recorder No. 4, Chart with time and date of alarm. STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)::)

I S/U 17.1 Refers to 10M-43.4.ACR, High-High RM-1LW-116 COMMENTS:

18.1 Pushes reset pushbutton on [RIS-1 L W -116] Liquid Waste Contam Dr Effluent Monitor. 18.2 Verify that the alarm is re-energized.

EVALUATOR NOTE: Initial conditions have RM-RR-400, Radiation Monitor Recorder No. 4 Out of Service. COMMENTS:

EVALUATOR NOTE: FCV -1 L W -103 auto closure is inhibited and must be manually closed.

RTL#A5.640U 112-ADM-1301.F04 Page 13 of 14 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

1CR-658 I JPM REVISION:

0 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A STEP ( "C" Denotes CRITICAL STEP ) 19.C Verify that [FCV-1LW-103]

Flow Control Valve is closed by observing its indicating lights, (BB-A). 20. Verify [TV-1LW-116]

is closed by observing its indicating light. STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I Stu 19.1 Observes RED light-LIT and GREEN light-NOT LIT. (BB-A) 19 .2C Depresses AM -1 L W -103 T pushbutton until zero (0) GPM is indicated on FRC-1LW-103 A). 19.3 Observes GREEN light-LIT and RED light-NOT LIT. (BB-A) COMMENTS:

EVALUATOR NOTE: TV -1 L W -116 auto trip closure is inhibited and can not be closed. 20.1 Observes that TV -1 L W -116 did not trip on the High Radiation alarm. 20.2 Observes RED light-LIT and GREEN light-NOT LIT. COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 14 of 14 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-658 JPM REVISION:

0 JPM TITLE: Discharge Laundry and Contaminated Shower Drain Tank 6A STEP STANDARD ( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR 21.C Stop [1LW-P-6A and 6B] 21.1CPlaces CS for 1LW-P-6A to STOP. Contaminated Drain Transfer Pumps (BB-A). 21.2 Verifies GREEN light-LIT and RED light-NOT LIT. 21.3 Verifies 1LW-P-6B is not running. 21.4 Verifies GREEN light-LIT and RED light -NOT LIT. COMMENTS:

EVALUATOR CUE: That completes this JPM STOP TIME: ______ _

ltTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 1/2-ADM-130l.F04 Page 3 of9 Revision I JPMNUMBER:

lCR-596 JPM REVISION:

3 JPM TITLE: Control Rod Assembly Partial Movement Test KIA

REFERENCE:

001A4.03 4.0/3.7 TASK ID: 0535-005-04-013 JPM APPLICATION:

C8J REQUALIFICATION C8J FAULTED JPM C8J INITIAL EXAM D TRAINING 0 ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: C8J Perform D Plant Site D Annual Requal Exam D BVT D Simulate C8J Simulator D Initial Exam D NRC D Classroom D OJT/TPE 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: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 112-ADM-130l.F04 Page 4 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-596 JPM REVISION:

3 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Control Rod Assembly Partial Movement Test EVALUATOR DIRECTION SHEET Perform 1 OST -1.1, and take appropriate action for Continuous Rod motion by placing the Control Rod selector switch to Auto to stop rod insertion per AOP-1.1.3.

Simulator The Unit is in Mode 1. The Unit Supervisor directs you to verify CB-D is operable by performing steps VILA & VII.B of 1 OST -1.1, using Manual control. The procedure Initial Conditions are complete.

10ST-1.1, "Control Rod Assembly Partial Movement Test", Rev. 18 10M-53C.4.1.1.3, "Unexpected Control Rod Movement", Rev. 13. None 10ST-1.1, "Control Rod Assembly Partial Movement Test", Rev. 18, place kept up to step VILA and mark step VILB.2 as being N/ A. (Have copies available to replace procedure in binder if used) 10M-53C.4.1.1.3, "Unexpected Control Rod Movement", Rev. 13.

RT-L#A5.640U 1/2-ADM-130 l.F04 Page 5 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The Unit is in Mode 1. INITIATING CUE: The Unit Supervisor directs you to verify CB-D is operable by performing steps VII. A & VII.B of 1 OST -1.1, using Manual control. The procedure Initial Conditions are complete.

D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-130 l.F04 Page 6 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-596 I JPM REVISION:

3 JPM TITLE: Control Rod Assembly Partial Movement Test STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT => START TIME: ______ _ SIMULATOR SETUP: INIT to any 100% IC Set trigger 1 to insert control rods at 219 steps:

TRGSET 1 'MCRFNS(44)

<=219'

IMF CRFOSB (1 0) 0 EVALUATOR NOTE: Provide candidate a place kept copy of 1 OS T -1.1 up to procedure step VILA and upon procedure review and candidate indicating readiness to begin, place the simulator in RUN and begin JPM. EVALUATOR CUE: Role-play Unit Supervisor and direct candidate to energize all BIU Heaters. 1. Energize sufficient pressurizer 1.1 Places all BIU Heaters control switches to ON. heaters prior to rod movement to prevent lowering of pressurizer 1.2 Verifies RED light-LIT and WHITE light-NOT LIT for BIU heater banks. pressure to the DNB limit during rod insertion.

COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 7 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

1CR-596 1 JPM REVISION:

3 JPM TITLE: Control Rod Assembly Partial Movement Test STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu 2. Record initial Control Bank D 2.1 Records Control Bank D rod step counters for Group position from the Rod Step 1 and Group 2. Counter for Group 1 AND Group 2 readings below. COMMENTS:

3. Record individual Control 3.1 Records individual RPI indicators for Control Bank D Bank D rod positions.

as specified in step VII.B.3.

Record individual RPI 3.2 Records IPC computer points as specified in step indicators for Control Bank VII.B.4. D. (VB-B) COMMENTS:

Record IPC Computer points. (IPC) 4.C Verify the Control Rod Bank 4.1C Places Control Rod Bank selector switch in MAN Sel Sw is in the desired position.

position.

4.2 Circles MAN on the space provided in the OST. EVALUATOR NOTE: Initiating cue directed using MANUAL rod control. COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 8 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-596 JPM REVISION:

3 JPM TITLE: Control Rod Assembly Partial Movement Test STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu 5.C Using the ROD MOTION 5.1C Inserts Control Bank D control rods 5 steps in using lever, Insert OR Withdraw CB-the In-Out-Hold switch on BB-B. D at least 10 steps (in 5 step increments).

5.2 Verifies Rod insertion

! arrow light is-LIT. 5.3 Verifies Group Step counters decreasing.

COMMENTS:

FAULT STATEMENT Rods will continue to move when the step counter reaches 219 steps, candidate is expected to perform the lOA's of AOP-1.1.3.

5.4C Inserts Control Bank D control rods 5 steps in using the In-Out-Hold switch on BB-B. 5.5 Verifies Rod insertion

! arrow light is -LIT. 5.6 Verifies Group Step counters decreasing.

COMMENTS:

RT-L#A5.640U 1/2-ADM-130 l.F04 Page 9 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-596 JPM REVISION:

3 JPM TITLE: Control Rod Assembly Partial Movement Test STEP ( "C" Denotes CRITICAL STEP ) 6.C Recognizes control rods are continuously inserting.

STANDARD 6.1 6.2 Recognizes Control Rods are inserting.

In accordance with AOP-1.1.3, "Unexpected Control Rod movement", checks Controls Rods in Auto. 6.3C Places Control Rod Bank selector switch in Auto. 6.4 Candidate recognizes rod movement has stopped. COMMENTS:

EVALUATOR CUE: This completes the JPM. STOP TIME: ----------------

ltT'L#A5.640U OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A 1/2-ADM-1301.F04 Page 3 of 16 Revision 1 KIA

REFERENCE:

006 Al.l3 3.5/3.7 TASK ID: 0111-059-01-013 IZI INITIAL EXAM D TRAINING JPM APPLICATION:

IZI REQUALIFICATION IZI FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: IZ! Perform D Plant Site D Annual Requal Exam D BVT D Simulate IZI Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 20 minutes Actual minutes Critical:

IZI No Time: Time: D SAT JPM RESULTS: D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: I Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET Accumulator "A" is drained and system is returned to normal alignment with no low pressure or high level annunciators in alarm. Simulator

The Plant is in Mode 1, all systems are in normal alignment for this power level.

The "A" Accumulator high level annunciator was received, due to overfilling.

The SMIUS directs you to drain the "A" SI accumulator by using 10M-11.4.F.

Drain accumulator "A" to a level of75% to 80%. 10M-11.4.F, Draining Safety Injection Accumulator

[1SI-TK-1A (1B) (1C)], Rev. 6 10M-11.4.G, Pressurizing Safety Injection Accumulator

[1SI-TK-1A (1B) (1C)], Rev. 14 10M-11.4.AAM, Safety Injector Accumulator

1 Press High-Low Chi, Rev. 5 None 10M-11.4.F, Draining Safety Injection Accumulator

[1SI-TK-1A (1B) (1 C)], Rev. 6 HAVE COPIES AVAILABLE TO REPLACE SIMULATOR COPY FOR: 10M-11.4.G, Pressurizing Safety Injection Accumulator

[lSI-TK-lA (lB) (lC)], Rev. 14 10M-11.4.AAM (N), Safety Injector Accumulator

1 Press High-Low Ch 1(11), Rev. 5 RTL#A5.640U 112-ADM-130 l.F04 Page 5 of 16 Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The Plant is in Mode 1, all systems are in normal alignment for this power level.

The "A" Accumulator high level annunciator was received, due to overfilling.

INITIATING CUE: The SMIUS directs you to drain the "A" SI accumulator by using 10M-11.4.F.

Drain accumulator "A" to a level of75% to 80%. D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-130 l.F04 Page 6 of 16 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

lCR-659 JPM REVISION:

0 1. Reviews 10M-11.4.F JPM TITLE: Drain SIS Accumulator A STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT => START TIME: ______ _ SIMULATOR SETUP: Any IC will suffice for this JPM. Gradually raise tank mass to 65400lbm, while monitoring pressure (vent tank to maintain <665psig to prevent lifting relief and discharging to cnmt) Set Accumulator pressure at 656 psig and level of91.3% for start of JPM ACCMASSTANK(2)=65400 IRF AUX058 (10 0) 100 EVALUATOR CUE: Provide candidate with copy of 10M-11.4.F, Draining Safety Injection Accumulator

[lSI-TK-lA (lB) (lC)], Place simulator in RUN when candidate is ready to begin. 1. Reviews procedure, determines Step 1 is N/ A and notes caution regarding

'A' Accumulator inoperability, and reports to US that SIS 'A' accumulator will be inoperable when MOV -1 SI-852A is opened for draining.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 7 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP ( "C" Denotes CRITICAL STEP ) 2. Note initial accumulator level. 3.C. Open [MOV-1SI-852A(B)(C)], 1A(B)(C) SI ACC DRAIN, (BB-A). STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I Stu 2. EVALUATOR CUE: Role-play the Unit Supervisor and acknowledge the report. Inform candidate that you will make the appropriate TS log entries. Notes initial level in "A" Accumulator.

). COMMENTS:

3.l.C Places CS for 1A SI Ace Drain Isol Vlv MOV-1SI-852A to OPEN. 3.2 Verifies RED light-LIT and GREEN light-NOT LIT. 3.3 Verifies LI-1SI-920 and LI-1SI-922lowering level in 'A' Accumulator.

COMMENTS:

EVALUATOR NOTE: Annunciators A1-78 and A1-79 are expected to clear during the performance of this step. However the initiating cue directed draining the Accumulator to 75%to 80%.

RTL#A5.640U 1/2-ADM-1301.F04 Page 8 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

1CR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP ( "C" Denotes CRITICAL STEP) 4. Refers to ARP for A1-76 and/or A1-77 5. Check pressure indicator

[PI-1SI-921 and 923] to verify the accumulator pressure. (VB-A) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu FAULT STATEMENT Annunciator A1-76 and/or A1-77 will alert candidate to an accumulator low pressure condition during draining.

This will require the candidate to review ARP's and restore accumulator pressure lAW 10M-11.4.G, Pressurizing Safety Injection Accumulator

[1SI-TK-1A (1B) (1C)]. 4.1 Refers to ARP for A1-76 and/or A1-77 [10M-11.4.AAM(N)]

COMMENTS:

5.1 Verifies [PI-1SI-921 and 923] less than 633 psig. COMMENTS:

6. If draining accumulator to 6.1 normal level, Perform the Determines draining of accumulator is to continue until high level alarm is clear. following:

1) Bring accumulator level to operating range. 2) Refer to 10M-11.4.G, "Pressurizing Safety Injection Accumulator".

RTL#A5.640U 112-ADM-130 l.F04 Page 9 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 7.C Close [MOV-lSI-7.1C Places CS for lA SI Ace Drain Isol Vlv MOV-1SI-852A(B)(C)], 1A(B)(C) SI 852A to CLOSE. ACC DRAIN, (BB-A). 7.2 Verifies GREEN light -LIT and RED light -NOT LIT. 7.3 Verifies LI-1SI-920 and LI-1SI-922level in 'A' Accumulator is STABLE. COMMENTS:

8. Independently verify [MOV-8.1 Requests independent verification on MOV-1SI-1 SI-852A(852B)(852C)]

is 852A. closed and document in the Daily Journal. COMMENTS:

EVALUATOR CUE: Another operator will perform the independent verification on MOV-1SI-852A.

9. If level rise is suspected to 9.1 N/ A from Initial conditions.

have been caused by check valve leakage from the RCS, have the SI accumulator boron COMMENTS:

concentration checked. Stu I RTL#A5.640U 1/2-ADM-1301.F04 Page 10 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 10. Refers to 10M-11.4.G, 10.1 Refers to 10M-11.4.G, "Pressurizing Safety "Pressurizing Safety Injection Injection Accumulator".

Accumulator".

COMMENTS:

11. Verifies initial conditions.

11.1 Verifies the following:

Sufficient nitrogen is available from one of the following sources: ( 50% of one Nitrogen Truck is required to pressurize one Accumulator from atmosphere to 640 psi g.)

The nitrogen makeup system is aligned in accordance 1/20M-11.4.A, "Placing Nitrogen Trailer In Service At Unit 1 Or Unit 2".

The Unit 1 AND Unit 2 SM/US have granted permission for the performance of this procedure.

COMMENTS:

EVALUATOR CUE: Role-play the Unit Supervisor and report all initial conditions are met. ALSO use the Unit 1 truck supply of nitrogen to pressurize the accumulator.

EVALUATOR NOTE: If asked, pre-job brief for aligning Nitrogen makeup system has been completed.

SIU RTL#A5.640U 112-ADM-1301.F04 Page 11 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

lCR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR

12. If [lSI-TK-lA], SI 12.1 N/A Accumulator 1 A, was filled following maintenance or COMMENTS:

following the performance of lBVT-1.11.3, THEN Verify [lSI-TK-lA], SI Accumulator 1 A, temperature is :::: 62F by using a contact pyrometer prior to pressurizing

[lSI TK lA], SI Accumulator 1 A. 13. If using the Unit 1 'sTruck 13.1 Dispatches operator to verify [lSI-66], Nitrogen supply, Verify [lSI-66], Supply Isolation, is closed. Nitrogen Supply Isolation, is closed. COMMENTS:

EVALUATOR CUE: Role-play the local operator and report [1 SI-66], Nitrogen Supply Isolation, is CLOSED. 14.C Open [TV-lSI-101-1], 14.1C Places CS SI Ace N2 Sup Isol Vlv TV-lSI-101-1 to Nitrogen Supply to the Safety OPEN. Injection Accumulators. (BB-A) 14.2 Verifies RED light -LIT. and GREEN light-NOT LIT COMMENTS:

SIU RTL#A5.640U 112-ADM-130l.F04 Page 12 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

1CR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 15.C Open [TV-1SI-101-2], 15.1C Places CS SI Ace N2 Sup Isol Vlv TV-1SI-101-2 to Nitrogen Supply to the Safety OPEN. Injection Accumulators. (BB-A) 15.2 Verifies RED light -LIT. and GREEN light-NOT LIT COMMENTS:

16. If using the Unit 1 'sTruck 16.1 Dispatches operator to slowly open [1 SI-66], supply, Slowly Open [1SI-66], Nitrogen Supply Isolation.

Nitrogen Supply Isolation COMMENTS:

BOOTH CUE: When requested, Trigger 10 will Open 1SI-66, Nitrogen Supply Isolation.

Annunciator A2-31, 'Nitrogen Supply System Available' will light when 1SI-66 is opened. EVALUATOR CUE: Role-play the local operator and report [1SI-66], Nitrogen Supply Isolation, has been slowly OPENED. Stu RTL#A5.640U 112-ADM-1301.F04 Page 13 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

1CR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 17.C Open [MOV-1SI-853A], 1A SI 17.1C ACC N2 Sup Isol Vlv. (BB-A) Places CS for 1A SI Ace N2 Sup Isol Vlv MOV-1SI-853A to OPEN. 18.C When [1SI-TK-1A], SI Accumulator 1 A, reaches desired pressure, (635 to 660 psig) as read on [PI-1SI-921

& 923] OR the IPC, Close [MOV-1SI-853A].

17.2 17.3 Verifies RED light -LIT. and GREEN light-NOT LIT Verifies 1A Accumulator Pressures PI-1SI-921

& 923 rising. COMMENTS:

EVALUATOR CUE: (For time compression)

Inform candidate annunciator A1-76 and A1-77 are clear, and accumulator pressure is 650 psig on PI-1SI-921

& 923, and the IPC. 18.1 Verifies Annunciator A1-76 and A1-77 are clear. 18.2C Places CS for 1A SI Ace N2 Sup Isol Vlv MOV-1 SI-853A to CLOSE. 18.2 Verifies GREEN light-LIT and RED light-NOT LIT. COMMENTS:

Stu I RTL#A5.640U 112-ADM-1301.F04 Page 14 of 16 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

1CR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I Stu ( "C" Denotes CRITICAL STEP) 19. Independently Verify [MOV-19.1 Requests independent verification on MOV -1 SI-1SI-853A]

closed AND 853A. Document in Narrative Log COMMENTS:

EVALUATOR CUE: Another operator will perform the independent verification on MOV-1SI-853A.

20. If nitrogen supply is from Unit 20. Dispatches operator to Close [1NG-302], Nitrogen 1's Truck, THEN Perform the Supply Manifold Isol and [1NG-301], Nitrogen Truck following: (Otherwise N/A) Fill Connection

Close [1NG-302], Nitrogen Supply COMMENTS:

Manifold Isol.

Close [1NG-301], Nitrogen Truck Fill Connection.

EVALUATOR CUE: . Role-play the local operator and report [1NG-302 and 1NG-301], are CLOSED.

RTL#A5.640U 112-ADM-130 l.F04 Page 15 of 16 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-659 JPM REVISION:

0 JPM TITLE: Drain SIS Accumulator A STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 2l.C Close [TV-lSI-101-1], 21.1C Places CS SI Ace N2 Sup Isol Vlv TV-lSI-101-1 to Nitrogen Supply to the Safety CLOSE. Injection Accumulators. (BB-A) 21.2 Verifies GREEN light-LIT and RED light-NOT LIT. COMMENTS:

22.C Close [TV-lSI-101-2], 22.1C Places CS SI Ace N2 Sup Isol Vlv TV-lSI-101-2 to Nitrogen Supply to the Safety CLOSE. Injection Accumulators. (BB-A) 22.2 Verifies GREEN light-LIT and RED light-NOT LIT. COMMENTS:

23. Independently Verify [TV-lSI-23.1 Requests independent verification on [TV -1 SI -1 01-101-1 and 101-2] are closed 1 and 101-2]. AND Document in Narrative Log. COMMENTS:

EVALUATOR CUE: Another operator will perform the independent verification on [TV-1SI-101-1 and 101-2]. Stu R:rL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1 CR-659 JPM REVISION:

0 STEP ( "C" Denotes CRITICAL STEP) JPM TITLE: Drain SIS Accumulator A STANDARD EVALUATOR CUE: That completes this JPM STOP TIME: ______ _ 1/2-ADM-1301.F04 Page 16 of 16 Revision 1 RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION:

10 112-ADM-1301.F04 Page 3 of 11 Revision 1 KIA

REFERENCE:

004A1.11 004A3.01 004A3.02 3.0/3.0 3.5/3.7 3.6/3.6 TASK ID: 0071-019-01-013 C8J INITIAL EXAM D TRAINING JPM APPLICATION:

C8J REQUALIFICA TION D FAULTED JPM 0 ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: C8J Perform D Plant Site D Annual Requa! Exam D BVT D Simulate C8J Simulator D Initial Exam D NRC D Classroom D OJT/TPE 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: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RtL#A5.640U 112-ADM-130 l.F04 Page 4 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-OS 6 JPM TITLE: Place Excess Letdown in Service JPM REVISION:

10 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET Maximum excess letdown flow with minimum charging and seal injection flow established, normal letdown secured with PRZ level stable. Simulator The Unit is in Mode 1 with all systems in NSA. All systems are operating normally except for a leak on the CCR supply line to the non-regenerative heat exchanger.

Isolation of the leak will require that normal letdown be secured. Your supervisor directs you to place excess letdown in service from the "A" RCS loop to the VCT, secure normal letdown and stabilize PZR level in accordance with 10M-7.4.H, Excess Letdown Heat Exchanger Operation.

1A RCL Drain Valve, MOV-1RC-557A is energized.

10M-7.4.H Excess Letdown Heat Exchanger Operation, Rev 6 None 10M-7.4.H Excess Letdown Heat Exchanger Operation, Rev 6, place kept up to step IV .A.2.

RTL#A5.640U 1/2-ADM-130 l.F04 Page 5 of II Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The Unit is in Mode 1 with all systems in NSA. All systems are operating normally except for a leak on the CCR supply line to the non-regenerative heat exchanger.

Isolation of the leak will require that normal letdown be secured. INITIATING CUE: Your supervisor directs you to place excess letdown in service from the "A" RCS loop to the VCT, secure normal letdown and stabilize PZR level in accordance with 10M-7.4.H, Excess Letdown Heat Exchanger Operation.

D D D D lA RCL Drain Valve, MOV-1RC-557A is energized.

At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

R'fL#A5.640U 112-ADM-1301.F04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-OS 6 JPM TITLE: Place Excess Letdown in Service JPM REVISION:

10 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> START TIME:--*-----

SIMULATOR SETUP: Use any Mode 1, 2, or 3 IC. Energize MOV-1RC-557A:

Select Remote Functions

-Enter EPS094 and select T EVALUATOR CUE: Provide candidate a copy of 10M-7.4.H.

When candidate is ready to begin the JPM, Place the Simulator in RUN. 1. Review 10M-7.4.H, "Excess 1.1 Reviews 10M-7.4.H.

2.C Letdown Heat Exchanger Operation".

COMMENTS:

Open one of the following loop drain valves as directed by SM: (BB-A) a. [MOV-1RC-557A], lA RCL Drain Vlv. b. [MOV-1RC-557B], 1B RCL Drain Vlv. c. [MOV-1RC-557C], 1C RCL Drain Vlv. EVALUATOR NOTE: In accordance with initiating cue, it is desired to OPEN [MOV-1RC-557A]

and this valve is already energized.

2.1C Places [MOV-1RC-557A]

CS to OPEN. 2.2 Verifies RED light-LIT and GREEN light-NOT LIT. COMMENTS:

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 112-ADM-130 l.F04 Page 7 of 11 Revision 1 I JPM NUMBER: 1 CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION:

10 STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu 3.C Place [HCV-1CH-389], 3.1C Places [HCV-1CH-389]

CS to "PDT TANK" Divert to Drain Sys Vlv position.

control switch to the PDT TANK position (BB-A). 3.2 Verifies [HCV-1CH-389] "POT TANK" RED light-LIT and "VC TANK" RED light-NOT LIT. COMMENTS:

4.C Place [MOV-1CH-201], 4.1C Places [MOV-1CH-201]

CS to OPEN. Excess Ltdn HX Isol Vlv control switch to OPEN (BB-4.2 Verifies RED light -LIT and the GREEN light-A) NOT LIT. COMMENTS:

5.C Slowly adjust [MOV-1CH-5.1C Slowly turns [MOV-1CH-137]

potentiometer in the 137], Excess Ltdn HX Flow clockwise direction to OPEN the valve. Control Vlv. to maintain<

140 °F on [TI-1CH-139], 5.2 Verifies pressure on [PI-1CH-138]

rises and Excess Letdown Temp AND maintains pressure<

135 psig. < 135 psig on [PI-1CH-138], Excess Letdown Press, 5.3 Verifies temperature on [TI-1CH-139]

rises and is allowing for warm-up of the controlled

<140 °F. excess letdown heat exchanger.

COMMENTS:

I RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 112-ADM-1301.F04 Page 8 of 11 Revision 1 I JPM NUMBER: 1 CR -056 JPM TITLE: Place Excess Letdown in Service JPM REVISION:

10 I STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I Stu 6.C 7. If excess letdown flow is to be diverted to the charging pump suction AND after flow has been directed to the reactor plant vents and drains EVALUATOR CUE: When candidate recognizes a 10 min. purge to PDT is required, inform the candidate that 1 0 minutes has elapsed. EVALUATOR NOTE: When HCV-1CH-389 is placed in VC TANK position be aware that a pressure increase on PI-1CH-138 will occur. The candidate should adjust to ensure parameter(s) are not exceeded as necessary.

6.1C Places [HCV-1CH-389]

CS to "VC TANK" position.

6.2 Verifies [HCV-1CH-389] "VC TANK" RED LIT and "POT TANK" RED light-NOT LIT. system for 10 minutes, Place COMMENTS:

[HCV-1CH-389], Divert to Drains System Vlv control switch to the VC TANK position.

Monitor the following plant 7.1 Monitors following parameters on VB-A and determines that all parameters are normal: parameters to ensure proper system operation:

a. [TR-1RC-448A]

RCP Pump Radial Brg Temps. b. [TI-1CH-133], Seal Water Return Temp. c. Pressurizer level d. [TR-1RC-448A]

RCP Pumps Seal Leakoff Temps. e. [FR-1CH-154A, (B)], No.1 Seal Leakoff Wide (Narrow).

[TR-1RC-448A]

RCP Pump Radial Brg temps. * [TI-1CH-133], Seal Water Return temp.

Pressurizer level * [TR-1RC-448A]

RCP Pumps Seal Leakofftemps.

[FR-1CH-154A, (B)], No.1 Seal LeakoffWide (Narrow) COMMENTS:

RTL#A5.640U 112-ADM-I30I.F04 Page 9 of II Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION:

10 STEP ( "C" Denotes CRITICAL STEP) 8.C If normal letdown is to be isolated, Perform the following:

a. Place [TV-1CH-200A], 45 GPM Ltdn Orifice Cnmt Isl Vlv control switch to CLOSE on BB-A. b. Place [TV -1 CH-200B], 60 GPM Ltdn Orifice Cnmt lsi Vlv control switch to CLOSE on BB-A. c. Place [TV -1 CH-200C], 60 GPM Ltdn Orifice Cnmt lsi Vlv control switch to CLOSE on BB-A. d. Monitor pressurizer level for rising trend. e. Place [FCV-1CH-122], Chg Flow to Regen HX Inlet Control Vlv controller in MAN and close. f. Evaluate the need to raise RCS activity/chemical analysis since purification and hydrogen addition capabilities are impaired.

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I SIU EVALUATOR NOTE: In the next step, it is NOT critical that [TV-1CH-200A]

or [TV-1CH-200B]

are closed in any particular order. 8.1C Places [TV-1CH-200A]

to CLOSE. 8.2 Verifies GREEN light-LIT and RED light-NOT LIT. 8.3C Places [TV-1CH-200B]

to CLOSE. 8.4 Verifies GREEN light-LIT and RED light-NOT LIT. 8.5 Verifies [TV-1CH-200C]

GREEN light-LIT and RED light-NOT LIT. 8.6 Monitors pressurizer level for rising trend. 8.7C Places [FCV-1CH-122], Chg Flow to Regen HX Inlet Control Vlv controller in MANUAL. 8.8C Depresses A PB and verifies demand increases to 100%. 8.9 Evaluates the need to raise RCS activity/chemical analysis.

COMMENTS:

RtL#A5.640U 112-ADM-130 l.F04 Page 10 of 11 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR -056 JPM TITLE: Place Excess Letdown in Service JPM REVISION:

10 STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu EVALUATOR CUE: Shift Manager will contact chemistry to evaluate increasing RCS sampling.

9. If in Mode 1, 2, or 3, Perform 9.1 Notifies Unit Supervisor that 10ST-6.4 must be 1 OST -6.4, "Measurement of performed to verify seal injection flow is :5 28 gpm to Seal Injection Flow" to comply with TS 3.5.5. verify that reactor coolant pump seal injection flow is less than or equal to 28 GPM COMMENTS: (TS 3.5.5). EVALUATOR CUE: Role-play the Unit Supervisor and report that another operator will perform 1 OST -6.4, "Measurement of Seal Injection Flow".

R1'L#A5.640U l/2-ADM-130l.F04 Page 11 of II Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1CR-056 JPM REVISION:

10 JPM TITLE: Place Excess Letdown in Service STEP STANDARD ( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=> 10.C Adjust [HCV-1CH-186], RCP Seal Sup Vlv as necessary to control pressurizer level. a. If pressurizer level continues to rise, excess letdown flow may be increased until HX outlet temperature is approximately 200 °F as indicated on [TI-1CH-139], Excess Letdown Temp. 10.1C Adjusts [HCV-1CH-186]

until RCP seal injection flow on [FI-1CH-124, 127 and 130] is minimized at 2: 6 gpm/pump.

10.2C Adjusts [MOV-1CH-137]

potentiometer until lCH-139] temperature reaches 200°F, or Pressurizer level is no longer rising. EVALUATOR NOTE: When the candidate has reduced RCP seal injection flow and increased excess letdown flow until HX temperature is 200°F, or Pressurizer level has stopped rising, the evaluation for this JPM is complete COMMENTS:

STOP TIME: _______ _ I

RTL#A5.640U 1/2-ADM-1301.F04 Page 3 of 12 Revision 1 I JPMNUMBER:

1CR-661 JPM REVISION:

0 JPM TITLE: Respond to PRT High Temperature KIA

REFERENCE:

007 A1.01 007 A1.03 007 A4.01 2.9 I 3.1 2.6 I 2.7 2.7 I 2.7 TASK ID: 0063-005-01-013 0063-010-01-013 JPM APPLICATION:

IZI REQUALIFICATION IZI FAULTED JPM IZI INITIAL EXAM D TRAINING D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: IZI Perform D Plant Site D Annual Requal Exam D BVT D Simulate IZI 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 20 Minutes Actual minutes Critical:

IZI No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS NameiSSN:

NameiSSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET PRT High Temperature and level alarms are cleared. Simulator

The plant is operating in Mode 1. 1/2-ADM-130 l.F04 Page 4 ofl2 Revision 1

PRZR PORV ReliefValve, PCV-lRC-456 was identified as leaking by.

PRZR PORV Isol Valve, MOV-lRC-536 was CLOSED and remains ENERGIZED.

PORV tailpipe temperatures are now lowering.

As a result of the leakage, Annunciator A4-38, Pressurizer Relief Tank Temp High has actuated.

Your supervisor directs you to respond to Annunciator A4-38 and take the actions to clear the alarm conditions.

10M-6.4.AAB, Pressurizer Relief Tank Temp High Rev. 2 10M-6.4.AAF, Pressurizer Relief Tank Level High-Low Rev. 8 NONE 10M-6.4.AAB, Pressurizer Relief Tank Temp High Rev. 2 DO NOT HANDOUT 10M-6.4.AAF, Pressurizer Relief Tank Level High-Low Rev. 8 until student references the procedure.

"R.TL#A5.640U 112-ADM-1301.F04 Page 5 of12 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The plant is operating in Mode 1.

PRZR PORV ReliefValve, PCV-lRC-456 was identified as leaking by.

PRZR PORV Isol Valve, MOV-lRC-536 was CLOSED and remains ENERGIZED.

PORV tailpipe temperatures are now lowering.

As a result of the leakage, Annunciator A4-38, Pressurizer Relief Tank Temp High has actuated.

INITIATING CUE: Your supervisor directs you to respond to Annunciator A4-38 and take the actions to clear the alarm conditions.

D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F04 Page 6 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1CR-661 JPM REVISION:

O JPM TITLE: Respond to PRT High Temperature STEP STANDARD ( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)::::>

1. References 10M-6.4.AAB, Pressurizer Relief Tank Temp High. SIMULATOR SETUP:

Initialize Simulator to any Mode 1 IC.

Raise PRT level to 74% by opening TV-RC-519

Lower PRT press to 3.0 psig by opening MOV -RC-549.

Raise PRT temp to l25°F by putting a 15% open signal to any PORV. This will allow PRT level to rise to 76%.

REMOVE the open signal to the PORV AS SOON AS l25°F is reached. PRT temp will drift to

Lower PRT pressure again to 5.0 psig by opening MOV-RC-549.

Clear all alarm EXCEPT A4-38 Pressurizer Relief

To ensure High level alarm will come in, and clear on draining:

TRG 1 (BPRT470 >= 77), command (IMF RCS019)

TRG 2 (BPRT470 <= 76 .and. rrch523 == 1), command (DMF BST-RCS019)

Write SNAP with the following PRT conditions:

Level= 76%

Press= 5.0 psig

Temp= l28°F Place Caution sticker on MOV-lRC-536 for JPM. START TIME: ______ _ 1.1 Reviews 10M-6.4.AAB and verifies PRT temperature

[TI-RC-471]

is> l25°F. COMMENTS:

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 1/2-ADM-130 1.F04 Page 7 of 12 Revision 1 I JPM NUMBER: 1 CR -661 JPM TITLE: Respond to PRT High Temperature JPM REVISION:

0 STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR Stu 2. Check Open [MOV-1RC-2.1 Verifies PRT Spray Valve MOV-1RC-516 RED light 516], PRT Spray Valve, -LIT and GREEN light-NOT LIT (BB-A). COMMENTS:

3.C Open [TV-1RC-519], PRT 3.1C Places CS for PRT Primary Wtr Sup Isol Vlv TV-Primary Wtr Sup Isol Vlv, (BB-1RC-519 to OPEN A), to reduce the temperature below the alarm setpoint.

3.2 Verifies RED light-LIT and GREEN light-NOT LIT 3.3 Verifies PRT temperature

[TI-RC-471]

is decreasing COMMENTS:

4. Vent PR T as required to 4.1 Verifies [PI-1RC-472], Pressurizer Relief Tank Press maintain pressure<

8 psig as remains below 8 psig indicated on [PI-1RC-472], Pressurizer Relief Tank Press, COMMENTS: (VB-B), by Opening [MOV-1RC-549], PRT Vent Vlv, (BB-A). 5. If a PORV or Safety Valve is 5.1 NIA leaking, as indicated by any of the following annunciators, COMMENTS:

THEN refer to appropriate alarm response procedure I

R.TL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 112-ADM-130 l.F04 Page 8 of 12 Revision 1 I JPM NUMBER: 1 CR-661 JPM TITLE: Respond to PRT High Temperature JPM REVISION:

0 I STEP ( "C" Denotes CRITICAL STEP) 6. Refers to 10M-6.4.AAF, Pressurizer Relief Tank Level High-Low 7. Check high PR T level on RC-470], Pressurizer Relief Tank Level, (VB-B). 8.CifPRT level is> 78%, Verify Closed [TV-1RC-519], PRT Primary Wtr Sup Isol Vlv A). STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT):::)

I SIU FAULT STATEMENT:

Alternate Path begins here. Annunciator A4-36 Pressurizer Relief Tank Level High-Low will alarm. Student is expected to stop spraying the PR T and refer to 10M-6.4.AAF, Pressurizer Relief Tank Level Low to address the high level in the PRT. 6.1 Reviews 10M-6.4.AAF, Pressurizer Relief Tank Level High-Low COMMENTS:

7.1 Verifies Pressurizer Relief Tank Level [LI-RC-470]

is >78%. EVALUATOR CUE: If candidate is monitoring the IPC trend, and level is not > 78%, role-play the Unit Supervisor and inform the candidate to drain the PRT in accordance with the ARP. COMMENTS:

8.1C Places CS for PRT Primary Wtr Sup Isol Vlv TV-1RC-519 to CLOSE. 8.2 Verifies RED light-NOT LIT and GREEN LIT COMMENTS:

RTL#A5.640U 1/2-ADM-130 1.F04 Page 9 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-661 JPM REVISION:

O JPM TITLE: Respond to PRT High Temperature STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::>

Stu 9. Independently Verify that [TV-9.1 Requests independent verification of PR T Primary Wtr Sup Isol Vlv TV-1RC-519 in the closed position and log entry. 1RC-519], PRT Primary Wtr Sup Isol Vlv, is Closed AND Document in the Narrative Log. 10.C IfPRT level is> 78%, Open [MOV-1RC-523], PRT Drain Vlv (BB-A) to reduce level to <72%. COMMENTS:

EVALUATOR CUE: Role-play the Unit Supervisor and inform student that another operator will perform the independent verification and make the appropriate log entry. 10.1CPlaces CS for PRT Drain Vlv MOV-1RC-523 to OPEN. 10.2 Verifies RED light-LIT and GREEN light-NOT LIT 10.3 Verifies Pressurizer Relief Tank Level [LI-RC-470]

is decreasing COMMENTS:

EVALUATOR CUE: Student may take actions to correct A3-113, 'Primary Drain Transfer Tank Level High-Low', A2-100, "Degasifier 2A Vapor Press High-Low" or A2-108, "Degasifier 2B Vapor Press High-Low".

If this occurs, inform student that another Operator will address the alarm conditions.

RTL#A5.640U 1/2-ADM-130 1.F04 Page 10 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-661 JPM REVISION:

O JPM TITLE: Respond to PRT High Temperature STEP ( "C" Denotes CRITICAL STEP) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I SIU 11. If required, Maintain PRT 11.1 Verifies Pressurizer Relief Tank Press PI-RC-472 pressure above 0.5 psig on remains above 0.5 psig. [PI-RC-472], Pressurizer Relief Tank Press, (VB-B), by COMMENTS:

Opening [TV-1RC-101], PRT N2 Sup Isol Vlv (BB-A). 12.C When PRT level has been reduced to <72%, Perform the following:

Close [MOV-1RC-523], PRT Drain Vlv. 13. If opened, Close [TV-1RC-101], PRT N2 Sup Isol Vlv. 12.1 Verifies Pressurizer Relief Tank Level [LI-RC-470]

is:::; 72%. 12.2CPlaces CS for PRT Drain Vlv MOV-1RC-523 to CLOSE. 12.3 Verifies GREEN light -LIT and RED light-NOT LIT 12.4 Verifies Pressurizer Relief Tank Level [LI-RC-470]

stops decreasing.

COMMENTS:

13.1 N/A EVALUATOR NOTE: Student is expected to return to 10M-6.4.AAB, Pressurizer Relief Tank Temp High to continue reducing PR T temperature.

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 112-ADM-130 l.F04 Page 11 of 12 Revision 1 I JPM NUMBER: 1 CR-661 JPM TITLE: Respond to PRT High Temperature JPM REVISION:

0 STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu 14. Check Open [MOV-1RC-14.1 Verifies PRT Spray Valve MOV-1RC-516 RED light 516], PRT Spray Valve, -LIT and GREEN light -NOT LIT (BB-A). COMMENTS:

15.C Open [TV-1RC-519], PRT 15.1CPlaces CS for PRT. Primary Wtr Sup Isol Vlv TV-Primary Wtr Sup Isol Vlv, 1RC-519 to OPEN (BB-A), to reduce the temperature below the alarm 15.2 Verifies RED light -LIT and GREEN light-NOT setpoint.

LIT 15.3 Verifies PRT temperature

[TI-RC-471]

is decreasing COMMENTS:

16. Vent PRT as required to 16.1 Verifies [PI-1RC-472], Pressurizer Relief Tank Press maintain pressure<

8 psigas remains below 8 psig indicated on [PI-1RC-472], Pressurizer Relief Tank Press, COMMENTS: (VB-B), by Opening [MOV-1RC-549], PRT Vent Vlv, (BB-A). 17. If a PORV or Safety Valve is 17.1 N/A leaking, as indicated by any of the following annunciators, COMMENTS:

THEN refer to appropriate alarm response procedure I

RTL#A5.640U 112-ADM-130l.F04 Page 12 of 12 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-661 JPM REVISION:

O JPM TITLE: Respond to PRT High Temperature STEP ( "C" Denotes CRITICAL STEP) 18.C When alarm is OFF, perform the following:

Close [TV-1RC-519].

STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)=> 18.1 Verifies A4-38 Pressurizer ReliefTank:

Temp High is NOT LIT 18.2CPlaces CS for PRT Primary Wtr Sup Isol Vlv TV-1RC-519 to CLOSE 18.3 Verifies RED light-NOT LIT and GREEN LIT COMMENTS:

EVALUATOR CUE: That completes this JPM STOP TIME: ______ _

' RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 1/2-ADM-130 l.F04 Page 3 of 12 Revision 1 I JPM.NUMBER:

1 CR-660 JPM REVISION:

O JPM TITLE: Transfer 4KV Emergency Bus from EDG to Normal Feed KIA

REFERENCE:

064 A4.06 3.9/3.9 TASK ID: 0362-007-01-013

[8J INITIAL EXAM D TRAINING JPM APPLICATION:

[8J REQUALIFICA TION [8J FAULTED JPM 0 ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: [8:1 Perform D Plant Site D Annual Requal Exam D BVT D Simulate [8:1 Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 20 Minutes Actual minutes Critical:

[8:1 No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET Bus 1AE is energized from Bus 1A. #1 EDG output BKR and motor operated ground switch are opened. #1 EDG is tripped. Simulator Breaker 1A10 has spuriously tripped open. All normal4KV busses are energized from USST's 1C and 1D. The #1 EDG is running and carrying loads on the 1AE Bus. The 4KV normal to emergency tie breakers, 1A10 and 1E7, are open. The relay crew has replaced a defective relay on breaker 1A10. The EDG has only been operating for 45 minutes. Your supervisor directs you to return 4160 EMER Bus 1AE to Normal Feed in accordance with 10M-36.4.Q, "Transferring Emergency Busses 1AE and 1DF From Emergency Feed To Normal Feed" part IV.A. 10M-36.4.Q, "Transferring Emergency Busses 1AE and 1DF From Emergency Feed To Normal Feed", Rev. 14. 10M-36.4.ADZ, Diesel Gen 1 Overcurrent Protection, Rev. 4. None 10M-36.4.Q, "Transferring Emergency Busses 1AE and 1DF From Emergency Feed To Normal Feed", Rev. 14 Have copies of 10M-36.4.ADZ, "Diesel Gen 1 Overcurrent Protection", Rev. 4 available to replace simulator copy, if necessary.

RTL#A5.640U 1/2-ADM-1301.F04 Page 5 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

Breaker 1A10 has spuriously tripped open. All normal4KV busses are energized from USST's 1C and 1D. The #1 EDG is running and carrying loads on the 1AE Bus. The 4KV normal to emergency tie breakers, 1A10 and 1E7, are open. The relay crew has replaced a defective relay on breaker 1A10. The EDG has only been operating for 45 minutes. INITIATING CUE: Your supervisor directs you to return 4160 EMER Bus 1AE to Normal Feed in accordance with 10M-36.4.Q, "Transferring Emergency Busses 1AE and 1DF From Emergency Feed To Normal Feed" part IV.A. D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 l.F04 Page 6 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-660 JPM REVISION:

O JPM TITLE: Transfer 4KV Emergency Bus from EDG to Normal Feed STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 1. Reviews procedure.

2. If Bus 1A is aligned to System Station Service Transformer 1 A, Perform Data Sheet 1 (otherwise, N/A). SIMULATOR SETUP: Insert malfunction (IMF EPS04E) to trip 1A10, and wait for DIG sequencer to complete loading. Then delete malfunction, and allow plant to stabilize.

Make annunciator A9-4 alarm when EDG load is <= 900 KW by setting Trigger 5 as (X17D049M

<= 900) with command (IMF XN09004 1) then SNAP. START TIME: 1.1 Reviews 1 OM-1.36.4.Q, "Transferring Emergency Busses 1AE and 1DF from Emergency Feed to Normal Feed". COMMENTS:

2.1 N/A COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-660 JPM REVISION:

O JPM TITLE: Transfer 4KV Emergency Bus from EDG to Normal Feed STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U 3.C Place the Emerg Gen 1 3.1C Places EMERG GEN 1 SYNCHRONIZING SEL SW Synchronizing Sel SW to the to the 1E7 position.

ACB 1E7 position and verifies ANN, A9-8, "ACB 1E7 OR 3.2 Verifies Annunciator A9-8 is LIT. 1E9 IN SYNCHRONIZING MODE", is ON. COMMENTS:

4. Verify control switch 4KV Bus 4.1 Places 1E7 breaker control switch to the AFTER-IAE to lA, ACB 1E7 is in the OPEN position. (Green Target). AFTER-OPEN position. (Green Target) COMMENTS:

5.C Close 4KV Bus IA to 1AE 5.1C Places ACB 1Al0 control switch in the CLOSE ACB 1A10. position.

5.2 Verifies RED light-LIT and WHITE light-NOT LIT. COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 8 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-660 JPM REVISION:

O JPM TITLE: Transfer 4KV Emergency Bus from EDG to Normal Feed STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => S/U 6. Adjust the governor speed 6.1 Requests operator at EDG #1 to adjust SPEED droop knob to 55 while DROOP to 55 with frequency being maintained at maintaining frequency at 60Hz. approximately 60hz. (EDG #1 Building)

COMMENTS:

EVALUATOR CUE: Role-play outside operator and report that local EDG #1 Gov. speed droop is set at 55. 7 .C Using the Emerg Gen 1 7.1C Intermittently places the EMERG GEN 1 Governor control switch, adjust GOVERNOR control switch in the RAISE direction the generator speed UNTIL the UNTIL the synchroscope needle is rotating very Synchroscope needle is rotating slowly in the FAST direction.

very slowly in the FAST direction.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 9 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE

JPM NUMBER: 1 CR-660 I JPM REVISION:

O JPM TITLE: Transfer 4KV Emergency Bus from EDG to Normal Feed STEP STANDARD ( "C" Denotes CRITICAL STEP ) 8.C Using the Emerg Gen 1 Volt Adjust, match generator voltage (running) with the voltage in Bus 1A (Incoming).

9.C When both synchronizing lights are completely dark AND the synchroscope needle is at 12 o'clock position, THEN close 4KVBus 1AEtoACB 1E7. (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U 8.1C Intermittently adjusts the EMERG GEN 1 VOLT ADJUST control switch as necessary. (LOWER on CS will lower VOLTAGE) until generator voltage is matched with Bus 1A voltage without exceeding 130 volts on the generator voltmeter.

8.2 Monitors Bus 1A voltage on the SYNCH VOLTS INCOMING NORM voltmeter and EDG voltage on the SYNCH VOLTS RUNNING NORM voltmeters on the Benchboard kickup. COMMENTS:

9.1C Places ACB 1E7 control switch in the CLOSE position when the synchroscope needle is at the 12 o'clock position.

9.2 Verifies RED light-LIT and WHITE light-NOT LIT. COMMENTS:

EVALUATOR CUE: I will provide the Concurrent Verification.

10. Place the Emerg Gen 1 10.1 Places EMERG GEN 1 SYNCHRONIZING SEL SW in the OFF position.

Sychronizing Sel SW to the OFF position and verifies ANN A9-8, "ACB 1E7 or 1E9 10.2 IN SYNCHRONIZING MODE" is OFF. Verifies annunciator A9-8, "ACB 1E7 or 1E9 IN SYNCHRONIZING MODE" is reset. COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 10 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-660 JPM REVISION:

O JPM TITLE: Transfer 4KV Emergency Bus from EDG to Normal Feed STEP ( "C" Denotes CRITICAL STEP) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I SIU 11. Perform the following to clean 11.1 out the exhaust system prior Determines EDG has only been running for minutes and therefore exhaust system does not need to be cleaned out. to shutting down the diesel generator, as necessary 12.C Reduce load on the EDG to less than 200 KW. COMMENTS:

12.1C Intermittently places EMERG GEN 1 GOVERNOR control switch in the LOWER position.

12.2 Monitors/Maintains the following parameters during the load decrease:

a. EMERG GEN 1 VOLTS (<130 volts) b. EMERG GEN 1 POWER FACTOR (0.8 -1.0 lagging) c. EMERG GEN 1 WATTS (Lower to< 200 KW) EVALUATOR CUE: If needed to accelerate the rate of the EDG shutdown, inform candidate that 5 minutes has elapsed. COMMENTS:

FAULT STATEMENT:

At this point the JPM alternate path begins. Annunciator A9-4, "DIESEL GEN 1 OVERCURRENT PROTECTION" will annunciate when EDG #1loading reaches 900 KW. Candidate should respond to ARP and open ACB 1E9, and trip the EDG. BOTH of which failed to automatically occur.

. RTL#A5.640U 112-ADM-130 1.F04 Page 11 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE ( JPM NUMBER: 1 CR-660 JPM REVISION:

O JPM TITLE: Transfer 4KV Emergency Bus from EDG to Normal Feed STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu 13. Refers to ARP for Annunciator 13.1 Reviews procedure.

A9-4, "DIESEL GEN 1 OVER CURRENT COMMENTS:

PROTECTION" 14. If Diesel Generator was 14.1 N/A carrying the bus GO TO 1OM-53C.4.1.36.2, "Loss Of 4KV COMMENTS:

Emergency Bus". 15C. Verify Emerg Gen 1 Output 15.1 Verifies Emerg Gen 1 Output Breaker [ACB-1E9]

Breaker [ACB-1E9]

OPEN, WHITE light-NOT LIT and RED light-LIT. white light ON. (BB-C) 15.2C Places CS Emerg Gen 1 Circuit Breaker [ACB-1E9]

to STOP. 15.3 Verifies Emerg Gen 1 Output Breaker [ACB-1E9]

WHITE light -LIT and RED light-NOT LIT. COMMENTS:

-RTL#A5.640U 112-ADM-130 1.F04 Page 12 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1 CR-660 JPM REVISION:

O JPM TITLE: Transfer 4KV Emergency Bus from EDG to Normal Feed STEP STANDARD ( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => 16. Verify the Emerg Gen 1 Motor 16.1 Operated Gm Sw opened by Verifies Emerg Gen 1 Motor Operated Gm Sw WHITE light-LIT and RED light-NOT LIT. white light ON. (BB-C) COMMENTS:

17.C Verify the engine tripped by 17.1 Verifies Emer Gen 1 RPM tachometer at 900 RPM observing the Emer Gen 1 RPM tachometer coasting 17 .2C Depresses Emer Gen 1 Stop PBs. down to or at 0 RPM. (BB-C) 1 7.3 Verifies Emer Gen 1 RPM tachometer coasting down to or at 0 RPM. COMMENTS:

EVALUATOR CUE: That completes this JPM. STOP TIME: ______ _

RTL#A5.640U

' JPM NUMBER: 1 CR-594 JPM REVISION:

3 JPM Respond to a Loss of the RHR System KIA

REFERENCE:

APE 025 AA1.09 3.2/3.1 TASK ID: 0535-018-04-013 INITIAL EXAM 112-ADM-130 l.F04 Page 3 of 15 Revision 1 D TRAINING JPM APPLICATION: REQUALIFICA TION FAULTED JPM 0 ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: Perform D Plant Site D Annual Requal Exam D BVT D Simulate Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 20 Minutes Actual minutes Critical: No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U I JPMNUMBER:

1CR-594 JPM REVISION:

3 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Respond to a Loss of the RHR System EVALUATOR DIRECTION SHEET 112-ADM-130l.F04 Page 4 of 15 Revision 1 Site personnel are informed of the Loss of Residual Heat Removal Capability. "A" RHR pump is started and Core cooling is restored by starting the 1C reactor coolant pump, 1RC-P-1C, using 10M-53A.l.2-C. Simulator

The plant is in Mode 4, with RCS pressure at psig and RCS temperature (Tc) at

Current Time to Saturation is minutes.

Containment closure is established.

1RH-P-1B has just tripped due to a MEPT condition.

1RH-P-1A is in Standby and available for service.

The RCS loops are all operable, with all RCP' s off. The following annunciators have been received:

A1-126, RESIDUAL HEAT REMOVAL SYSTEM DISCH FLOW LOW A1-127, RESIDUAL HEAT REMOVAL PP AUTO STOP The SM directs you to restore core cooling per AOP 1.10.1, Loss of Residual Heat Removal Capability.

10M-53C.4.1.10.1, Loss ofResidual Heat Removal Capability, Revision 15 10M-53A.l.2-C Starting Reactor Coolant Pump Revision 2 Stopwatch Provide a copy of 10M-53C.4.1.10.1, Loss of Residual Heat Removal Capability, Revision 15 Have copies of 10M-53A.1.2-C Starting Reactor Coolant Pump Revision 2 available for replacement.

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of 15 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The plant is in Mode 4, with RCS pressure at psig and RCS temperature (Tc) at

Current Time to Saturation is minutes.

Containment closure is established.

1RH-P-1B has just tripped due to a MEPT condition.

1RH-P-1A is in Standby and available for service.

The RCS loops are all operable, with all RCP's off. INITIATING CUE: The following annunciators have been received:

D D D D A1-126, RESIDUAL HEAT REMOVAL SYSTEM DISCH FLOW LOW A1-127, RESIDUAL HEAT REMOVAL PP AUTO STOP The SM directs you to restore core cooling per AOP 1.1 0.1, Loss of Residual Heat Removal Capability.

At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

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1CR-594 JPM REVISION:

3 JPM TITLE: Respond to a Loss of the RHR System STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 1. Candidate reviews procedure, AOP 1.10.1 2.C Check IfRHR Pumps Should Be Stopped a. Sound standby alarm AND announce "LOSS OF RESIDUAL HEAT REMOVAL CAP ABILITY" 1.1 SIMULATOR SETUP: Use IC-24 Mode 4, RCS pressure psig, RCS temperature RH-P-1A in STBY, RH-P-1B Tripped due to MEPT. Stop any running RCP's. Insert trigger for 1 A RHR pump to trip 15 seconds after starting.

Remove Permanent Caution Tag from MOV-1CH-142.

Put up the OPPS Placard. START TIME: ______ _ EVALUATOR NOTE: It is the intent that the candidate use the procedure in the Simulator, replace the copy after JPM. Reviews AOP 1.1 0.1. COMMENTS:

2.1 C Sounds the Standby Alarm. 2.2C Using Page party system, announces "LOSS OF RESIDUAL HEAT REMOVAL CAPABILITY" COMMENTS:

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3 STEP ( "C" Denotes CRITICAL STEP) 3. RHR Pumps-ANY RUNNING. STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 3 .1. Determines that no RHR pumps are running. EVALUATOR NOTE: Given in initial conditions

-1RH-P-1A is in standby and 1RH-P-1B has just tripped due to MEPT conditions.

3.2. Determines that the reason for the pump trip is electrical in nature. EVALUATOR CUE: If asked, inform the candidate that an operator at emergency switchgear has reported a ground overcurrent relay is tripped for 1RH-P-1B.

3.3 Performs RNO actions to start 1RH-P-1A.

COMMENTS:

FAULT STATEMENT:

This is where the Alternate path begins, 1RH-P-1A will start as expected; however, the pump will 15 seconds after starting.

It is expected that the Candidate will follow the procedure progression and start the 1 C RCP in response to this event to restore core cooling flow.

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1CR-594 JPM REVISION:

3 JPM TITLE: Respond to a Loss of the RHR System STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu 4C. IF RHR pump trip due to loss 4.1C Throttles MOV-1RH-758 to open by adjusting of power or motor protection, dial pot to 60 units. THEN Start standby RHR pump: 4.2C Throttles MOV-1RH-605 to open by depressing "manual" PB then depressing "Down" PB 1) Verify MOV-1RH-758, until indicating at 15%. throttled open 60%. 2) Verify MOV-1RH-605, 4.3 Verifies MOV-1CH-142 closed, GREEN light-LIT throttled open 15% and RED light NOT LIT. Verify MOV-1CH-142 4.4C Starts 1RH-P-1A by placing CS to START position Closed and verifies RED light -LIT and WHITE light-NOT 3) Start standby RHR pump. LIT, flow and AMPS increasing.

IF standby pump fails to EVALUATOR NOTE: start, THEN GO TO Step lRH-P-lA will trip 15 seconds after starting, this is a 5. continuous action step -candidate should understand

4) Verify the following:

that the standby pump has failed to start and continues Pump amps-STABLE to step 5. Pump flow-> 3200 GPM 4.5 Acknowledges Alarm Al-127, RHR pump Auto Stop 5) Position MOV-ICH-142 as -REFLASH.

directed by SMIUS. 6) Return to procedure and 4.6 Transitions to AOP step 5. step in effect. COMMENTS:

IF RHR pump trip due to unstable flow or loss of inventory, THEN continue with Step I.e.

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3 STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=:>

Stu 5. Initiate Actions To Establish 5.1 Determines from initial conditions that Time to Containment Closure Saturation is < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and that Containment Closure has previously been established as given in Initial a. Time-To-Saturation

-< 1 Conditions.

HOUR. b. Containment Closure -COMMENTS:

ESTABLISHED

6. Check RCS Inventory 6.1 Determines pressurizer level is stable. (NOT DROPPING)

a. RCS/PRZR level -DROPPING.

6.2 Using RNO step-transitions to AOP step 7. COMMENTS:

7. Check PRT Conditions

-7.1 Determines PR T level is stable and conditions are CONSISTENT WITH PRE-consistent with pre-event.

EVENT COMMENTS:

a. PRT level-STABLE.

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3 JPM TITLE: Respond to a Loss of the RHR System STEP STANDARD ( "C" Denotes CRITICAL STEP ) 8. Check RHR Pump status. (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U 8.1. Determines that no RHR pumps are running. 8.2. Determines that the reason for the pump trip is electrical in nature and venting is not required.

EVALUATOR CUE: If necessary, inform the candidate that an operator at emergency switchgear has reported a ground overcurrent relay is tripped for 1RH-P-1A.

8.3 Continues with AOP step 9. COMMENTS:

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1CR-594 JPM REVISION:

3 JPM TITLE: Respond to a Loss of the RHR System STEP ( "C" Denotes CRITICAL STEP ) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I SIU I 9. Verify Component Cooling 9.1 Water System Operation Verifies all 3 CCR pumps are running using following indications:

a. CCR Pumps-AT LEAST ONE RUNNING b. Check MOV-1CC-112A2, 112B2, 112A3, and 112B3 OPEN. c. CCR Flow-FLOW INDICATED

FI-1CC-117, 24-Inch CCRFlow

F051 OA, CCR-24" HEADER FLOW 9.2 9.3 9.4

CS's in AFTER START,

RED lights -LIT and WHITE lights-NOT LIT

current indicated on ammeters.

Verifies CCR Hx Cooling water valves -MOV -1 CC-112A2, 112B2, 112A3, and 112B3 all OPEN via RED lights -LIT and GREEN lights-NOT LIT. Verifies 24" header CCR flow as indicated on FI-1 CC-117 and/or computer point F051 OA. Verifies normal CCR temperature as indicated on TI-1CC-100 and/or computer point T0541A. d. CCR Temp-NORMAL COMMENTS:

TI-1CC-100, CCR Temp

T0541A, CCR HEAT EX OUTLET TEMP 10. Verify RHR System Valve Alignment

a. RHR Inlet Valves-OPEN 10.1 Verifies RHR Inlet and Return valves,-MOV-1RH-700, 701, 720A, and 720B all OPEN via RED LIT and GREEN lights-NOT LIT for all 4 valves. MOV-1RH-700 AND COMMENTS:

MOV-1RH-701.

b. RHR Return Valves -AT LEAST ONE OPEN MOV-1RH-720A OR MOV-1RH-720B.

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3 JPM TITLE: Respond to a Loss of the RHR System STEP ( "C" Denotes CRITICAL STEP) 11. Estimate Time To RCS Saturation

a. RHR pumps-NONE RUNNING. b. Obtain RCS saturation from one of the following:

Request STA to calculate saturation using computer program. 12. Determine Action Based On Time-To-Saturation

a. Based on current saturation-ADEQUATE TIME TO VENT RHR PUMPS. b. VentRHRpump(s)in accordance with Attach 2. STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I SIU I 11.1 As previously checked, confirms that NO RHR pumps are running. 11.2 Requests STA to calculate time-to-saturation EVALUATOR CUE: Role-play the STA and report that current saturation is 45 minutes. COMMENTS:

12.1 Determines there is NOT adequate time to vent RHR pumps. EVALUATOR CUE: If necessary, role play Shift Manager and inform the candidate that there is not enough time to vent the RHR pumps. 12.2 Performs RNO step and determines that there are no available RHR pumps and goes to AOP step 14 to establish alternate cooling. COMMENTS:

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1CR-594 JPM REVISION:

3 JPM TITLE: Respond to a Loss of the RHR System STEP ( "C" Denotes CRITICAL STEP ) 13. Initiate Alternate Core Cooling. a. Plant in MODE 6. STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I S/U 13.1 Determines plant IS NOT in Mode 6. 13.2 Continues to AOP step 15. COMMENTS:

14. Pressurize Or Makeup To RCS 14.1 Recognizes that the RCS is pressurized and therefore the RCS is intact. a. RCS-INTACT

b. LI-1RC-462 PRZR Cold Calib->5% c. RCS Loops-AT LEAST ONE AVAILABLE WITH SG CAPABLE OF REMOVING HEAT d. Check OPPS in service. e. Pressurize RCS UNTIL RCP Seal DIP >215 psid. f. Perform one of the following per SMIUS discretion:

1) Start one RCP. Refer to 1 OM-53A.1.2-C, "Starting Reactor Coolant Pump". 14.2 Verifies PRZR level is> 5% on LI-1RC-462 (BB-B) 14.3 Per initial conditions-ALL RCS loops are operable, at least one RCS loop is available and capable of removing heat. 14.4 Verifies OPPS is in service, by both KEY switches.

14.5 Verifies RCP seal ilP is >215 psid on VB-A EVALUATOR CUE: Role-play SM and Request that the "C" RCP be started. 14.6 Transitions to EOP attachment 2-C for direction to start the "C" RCP. COMMENTS:

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lCR-594 JPM REVISION:

3 JPM TITLE: Respond to a Loss of the RHR System STEP STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT}=> I S/U I ( "C" Denotes CRITICAL STEP) 15. Part C-Starting lRC-P-lC 15.1 Verifies PRZR level, pressure and liquid temperature indicates presence of steam bubble. 1. Check Steam Bubble in PRZR. 15.2 Verifies VCT press> 15 psig on PI-lCH-117, VB-A. 2. Check VCT Press > 15psig. 15.3 Verifies CCR flow to the 1 C RCP on VB-A using 3. Check CCR flow to the FI-1CC-104C, 105C, 106C, & 107C. lCRCP 4. Check No. 1 Seal DP 15.4 Verifies No. 1 Seal DP >215 psid on VB-A using >215 psig. PI-1CH-154A.

5. Check seal injection flow 15.5 Adjusts seal injection flow to 6 -9 gpm on VB-A, 6 to 9 gpm. (FI-lCH-124) by adjusting dial POT on HCV-lCH-6. Check Associated 186 (BB-A) Annunciators NOT in alarm. 15.6 Verifies list of annunciators are ALL CLEAR -7. Verify Voltage on 4 KV NONE IN ALARM. Bus lC > 125 Volts. 15.7 Verifies 4KV Bus lC Voltage is >125V on VB-C. a. Verify 4KV Bus lC aligned to SSST lB. COMMENTS:

b. IF necessary, Adjust voltage on Bus 1 C using Load Tap changer. c. IF adjustment made -return Tap changer to manual.

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3 JPM TITLE: Respond to a Loss of the RHR System STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 16.C Part C-Starting lRC-P-lC 8. Place CS for 1RC-P-1C in START. a. Check Lift Oil pump starts. b. Check RCP Seal leakoffflow

> 0.2 gpm. c. After 2 minutes, Verify RCP starts. 16.1C Places 1RC-P-1C Control Switch to START and starts a stopwatch.

16.2 Verifies the RED running light is lit for RCP Oil Lift Pump. 16.3 Verifies the RCP starts after 2 minutes by checking RED light-LIT and White light-NOT LIT, amps and flow are increasing.

16.4 Verifies RCP motor amps drop off after RCP start. COMMENTS:

EVALUATOR CUE: After 1RC-P-1C is verified running, State "That completes this JPM". STOP TIME: ________ _

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE I. JPM NUMBER: 1PL-003 JPM REVISION:

16 JPM TITLE: Startup a Rod Drive MG Set K/A

REFERENCE:

001 A4.08 3.7/3.4 TASK ID: 0011-001-01-043 IZI INITIAL EXAM 112-ADM-130 1.F04 Page 3 of 11 Revision 1 D TRAINING JPM APPLICATION:

IZI REQUALIFICATION D FAULTED JPM 0 ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: D Perform IZI Plant Site D Annual Requal Exam D BVT IZI Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 10 Minutes Actual minutes Critical:

IZI No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 112-ADM-1301.F04 Page 4 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1PL-003 I JPM REVISION:

16 JPM TITLE: Startup a Rod Drive MG Set TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET #2 Rod Drive MG set is running with the Motor Generator Output Breaker closed. In-Plant The plant is in Mode 3, with the full-length rod control system being started up in accordance with 1 OM-1.4.B, "Full Length Rod Control System Startup", section IV Parts A, Band D have been completed.

The #1 MG set is currently operating and the reactor trip breakers are dosed. All control rods are fully inserted.

Your supervisor directs you to continue with 10M-1.4.B and startup the #2 Rod Drive MG set, beginning with section IV Part C step 3 and synchronize the #2 Rod Control MG Set per Part E. 10M-1.4.B, "Full Length Rod Control System Startup" Rev. 27 None 1 OM-1.4.B, "Full Length Rod Control System Startup" Rev. 27 Place kept with section IV Parts A, B, and D fully completed AND section IV Part C steps 1 and 2 completed.

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THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The plant is in Mode 3, with the full-length rod control system being started up in accordance with 1 OM-1.4.B, "Full Length Rod Control System Startup", section IV Parts A, Band D have been completed.

The #1 MG set is currently operating and the reactor trip breakers are closed. All control rods are fully inserted.

INITIATING CUE: Your supervisor directs you to continue with 1 OM-1.4.B and startup the #2 Rod Drive MG set, beginning with section IV Part C step 3 and synchronize the #2 Rod Control MG Set per Part E. D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

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16 JPM TITLE: Startup a Rod Drive MG Set 1.C Place the [1ROD-MG-2-CS], Control Switch for MG-2, in the CLOSE position, AND Check MG Set #2 starts. STANDARD (Indicate "S" FOR SAT or "U" FOR START TIME: ______ _ EVALUATOR NOTE: During the performance of this JPM, no cabinet, switchgear or cubicle will be opened. Noise levels will be high in this area if the plant is operating, making hearing difficult.

1.1C Places the [lROD-MG-2-CS], Control Switch For 1ROD-MG-2, in the CLOSE position.

1.2 Verifies GREEN light-NOT LIT and RED LIT. 1.3 Verifies MG set reaches normal operating speed by observing the sound emanating from the MG set is a constant pitch as opposed to the steady increase during acceleration.

EVALUATOR CUE: 15 seconds has elapsed, Red light is LIT and Green light is NOT LIT. Sound emanating from the MG set is a constant pitch. COMMENTS:

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16 JPM TITLE: Startup a Rod Drive MG Set STEP STANDARD ( "C" Denotes CRITICAL STEP) 2.C When the MG set has reached 2.1C Depresses Generator No.2, Gen. Field Flash, normal operating speed, pushbutton until Generator Line Voltage rises to Depress AND Hold the approximately 235 VAC. Generator No. 2, Gen. Field Flash, pushbutton until 2.2 Verifies Generator Line Voltage rises to Generator Line Voltage rises approximately 235 V AC. to approximately 235 V AC, EVALUATOR CUE: THEN release. Generator Line Voltage is 260 V AC. 2.3 Releases Generator No. 2, Gen. Field Flash, pushbutton.

COMMENTS:

EVALUATOR NOTE: The following step will NOT close the second generator breaker but will allow the synchronizing relay to close the second generator breaker after the synchronize switch is placed in ON. The second generator is expected to synchronize within approximately 15 seconds. Also, NOTE that the candidate will N/A steps 5 and 6 of Part C and proceed to Part E of the procedure and then N/ A Step 1 since control rods are NOT withdrawn.

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16 JPM TITLE: Startup a Rod Drive MG Set STEP STANDARD ( "C" Denotes CRITICAL STEP ) 3. Check that the following 3.1 Contacts the control room and requests the RO verify annunciators are clear: the following annunciators are clear: A4-97, "ROD CONTROL SYSTEM A4-97, "ROD CONTROL SYSTEM NON-URGENT NON-URGENT ALARM" ALARM" A4-98, "ROD CONTROL MG SET A4-98, "ROD CONTROL MG SET GROUNDED" GROUNDED" A4-99, "ROD CONTROL MG SET 1A TRIP" A4-99, "ROD CONTROL MG SET A4-1 05, "ROD CONTROL SYSTEM URGENT 1A TRIP" ALARM" A4-1 05, "ROD CONTROL A4-107, "ROD CONTROL MG SET 1B TRIP" SYSTEM URGENT ALARM" EVALUATOR CUE: A4-107, "ROD CONTROL MG Role-play the RO and inform the student that the SET 1 B TRIP" following alarms are CLEAR: A4-97, "ROD CONTROL SYSTEM NON-URGENT ALARM" A4-98, "ROD CONTROL MG SET GROUNDED" A4-99, "ROD CONTROL MG SET 1A TRIP" A4-1 05, "ROD CONTROL SYSTEM URGENT ALARM" A4-107, "ROD CONTROL MG SET 1B TRIP" COMMENTS:

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16 JPM TITLE: Startup a Rod Drive MG Set STEP STANDARD ( "C" Denotes CRITICAL STEP) EVALUATOR NOTE: Candidate will N/A Step IV.E.3 since MG Set #1 Breaker is already closed and will proceed to Step IV.E.4. 4.C Place [1ROD-DR-SWGR 4.1C Places [1ROD-DR-SWGR-2-CS], Rod Control MG CS], Rod Control MG Set #2 Set #2 Output Bkr Control Switch, in CLOSE. Output Bkr Control Switch, in the CLOSE position.

4.2 Verifies Rod Control MG Set #2 Output Bkr RED target AND GREEN light-LIT and RED light-NOT LIT EVALUATOR CUE: Rod Control MG Set #2 Output Breaker control switch has a RED target and Control Switch Green light-LIT and Red light-NOT LIT. COMMENTS:

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16 JPM TITLE: Startup a Rod Drive MG Set STEP STANDARD ( "C" Denotes CRITICAL STEP) EVALUATOR NOTE: Candidate may need to obtain T-Handle from other MG set to operate switch. 5.C Place [1ROD-MG-2-SYNC-5.1C Places [1ROD-MG-2-SYNC-CS], Rod Control MG CS], Rod Control MG Set #2 Set #2 Voltage Sync Switch, to ON. Voltage Sync Switch, to the 5.2 Verifies Rod Control MG Set #2 Output Breaker ON position.

RED light-LIT and GREEN light-NOT LIT. EVALUATOR CUE: 15 seconds has elapsed, Rod Control MG Set #2 Output Breaker Red light *-LIT and Green light -NOT LIT COMMENTS:

EVALUATOR NOTE: To prevent an automatic start and synchronization of the second MG set, the Synchronize switches are maintained in the OFF position.

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16 JPM TITLE: Startup a Rod Drive MG Set STEP ( "C" Denotes CRITICAL STEP) 6. When the Generator No.2 circuit breaker Closes, Place [1ROD-MG-2-SYNC-CS], Rod Control MG Set #2 Voltage Sync Switch, to the OFF position.

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 6.1 Places [lROD-MG-2-SYNC-CS], Rod Control MG Set #2 Voltage Sync Switch, to OFF EVALUATOR CUE: Rod Control MG Set #2 Voltage Sync Switch, to OFF COMMENTS:

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

RTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 112-ADM-1301.F04 Page 3 of 10 Revision 1 JPM NUMBER: 1PL-004 JPM REVISION:

10 JPM TITLE: Reset the Terry Turbine Trip Throttle Valve KIA

REFERENCE:

061 A2.04 3.4/3.8 TASK ID: 0241*-024-01-043 IZI INITIAL EXAM D TRAINING JPM APPLICATION:

IZI REQUALIFICATION D FAULTED JPM 0 ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: D Perform IZI Plant Site D Annual Requal Exam D BVT IZI Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 10 minutes Actual minutes Critical:

IZI No Time: Time: D SAT JPM RESULTS: D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 112-ADM-130 l.F04 Page 4 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET lFW-P-2 trip throttle valve is reset. In-Plant The plant is in Mode 1 at 50% power. Annunciator A7-7 "Steam Unavailable to Turbine Driven Feed Pump" is illuminated.

A plant operator has verified that the trip throttle valve is closed. No start signal exists for lFW-P-2, and the pump is stopped. The SMIUS requests that you reset the trip throttle valve for lFW-P-2 lAW 10M-24.4.V, [FW-P-2] Trip Throttle Valve Resetting.

10M-24.4.V, [FW-P-2] Trip Throttle Valve Resetting, Revision 6 None 10M-24.4.V, [FW-P-2] Trip Throttle Valve Resetting, Revision 6 RTL#A5.640U 112-ADM-130l.F04 Page 5 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

The plant is in Mode 1 at 50% power. Annunciator A7-7 "Steam Unavailable to Turbine Driven Feed Pump" is illuminated.

A plant operator has verified that the trip throttle valve is closed. No start signal exists for lFW-P-2, and the pump is stopped. INITIATING CUE: The SMIUS requests that you reset the trip throttle valve for lFW-P-2 lAW 10M-24.4.V, [FW-P-2] Trip Throttle Valve Resetting.

D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

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10 JPM TITLE: Reset the Terry Turbine Trip Throttle Valve 1. Verify TV-1MS-105A and TV-1MS-105B are closed and MOV-1MS-105 is open. 2. Press the Manual Emergency Trip Lever to verify that the Overspeed Trip Mechanism is tripped. STANDARD START TIME: EVALUATOR CUE: Provide candidate a copy of 10M-24.4.V, [FW-P-2] Trip Throttle Valve Resetting 1.1 Contacts control room to verify valve position.

EVALUATOR CUE: Role-play the control room operator and report TV -MS-105A and TV-MS-105B are closed. MOV-1MS-105 is open. EVALUATOR NOTE: Only one of the above isolation paths needs to be closed. COMMENTS:

2.1 Depresses the manual emergency trip lever. EVALUATOR CUE: Manual emergency trip lever is depressed.

COMMENTS:

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10 JPM TITLE: Reset the Terry Turbine Trip Throttle Valve STEP ( "C" Denotes CRITICAL STEP) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I Stu 3. Verify that [1MS-465], 1FW-3.1 T-2 Inlet Stm Isol, is unlatched.

Verifies the valve is unlatched by ensuring trip hook is not engaged (may refer to Figure 1). 4.C Turn the [1MS-465], 1FW-T-2 Inlet Stm Isol, handwheel in the clockwise direction until the sliding nut and trip lever rise to the upper limit of travel. EVALUATOR CUE: Trip hook is not engaged. COMMENTS:

4.1C Candidate turns [1MS-465]

in the clockwise direction until the sliding nut and trip lever rise to the upper limit of travel. EXAMINER CUE: Trip lever and sliding nut are at the upper limit of travel. COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 8 oflO Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-004 JPM REVISION:

10 JPM TITLE: Reset the Terry Turbine Trip Throttle Valve STANDARD C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> 5.C Reset the Overspeed Trip 5.1C a. Overspeed trip lever held to the left. Mechanism by performing the b. Verifies Tappet washer flat side turned toward following:

trip lever. a. Hold the overspeed trip c. Trip lever released. connecting rod to the left. d. Verifies flat side of washer is flush against the b. Verify the overspeed tappet vertical side of overspeed trip lever. washer flat side directly faces e. Verifies trip lever is engaged with the trip hook. the overspeed trip lever. c. Gently release the connecting EXAMINER CUE: rod and allow the spring Flat side of washer is flush against the vertical side of tension to maintain the reset overspeed trip lever. condition.

Trip lever is engaged with the trip hook. d. Verify the flat side of the washer is flush against the vertical side of the overspeed COMMENTS:

trip lever. e. Verify that the trip lever is engaged with the trip hook. S/U RTL#A5.640U 112-ADM-130 l.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-004 JPM REVISION:

10 JPM TITLE: Reset the Terry Turbine Trip Throttle Valve fSTI*p Denotes CRITICAL STEP ) 6.C Slowly open [lMS-465], lFW-T-2 Inlet Stm Isol, by turning the handwheel counterclockwise, and verify that the pump does NOT accelerate in an uncontrolled manner. 7. Requests concurrent verification of [lMS-465]

position.

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I S/U 6.1C Slowly rotates [lMS-465]

handwheel fully counterclockwise slowly to open. EXAMINER CUE: [lMS-465]

handwheel is fully counterclockwise.

6.2 Verifies pump does NOT accelerate in an uncontrolled manner by observing pump shaft. EXAMINER CUE: When asked, indicate that the pump is not accelerating in an uncontrolled manner. COMMENTS:

7.1 Contacts Unit Supervisor and requests concurrent verification of [lMS-465]

position.

EXAMINER CUE: Role-play the Unit Supervisor and report that another operator will perform the concurrent verification.

COMMENTS:

RTL#A5.640U 112-ADM-130l.F04 Page 10 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1PL-004 JPM REVISION:

10 JPM TITLE: Reset the Terry Turbine Trip Throttle Valve Denotes CRITICAL STEP ) 8. WHEN open, THEN adjust [1MS-465], 1FW-T-2 Inlet Stm Isol, 114 tum off of the backseat.

9. Notify the Unit 1 Control Room Operator that [1FW-P-2], Steam Driven Auxiliary Feedwater Pump, is available.

STANDARD Indicate "S" FOR SAT or "U" FOR UNSA 8.1 Rotates [1MS-465]

handwheel in the clockwise direction

'l4 tum off its backseat.

EXAMINER CUE: [ 1 MS-465] handwhee1

'l4 tum clockwise, concurrent verification is complete.

COMMENTS:

9 .1. Contacts the Unit 1 Control Room to report that the trip throttle valve is reset. EXAMINER CUE: Acknowledge the report. COMMENTS:

EXAMINER CUE: That completes this JPM. STOP TIME: ______ _

ltTL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE l/2-ADM-130l.F04 Page 3 of9 Revision 1 I JPM NUMBER: 1PL-031 JPM REVISION:

5 JPM TITLE: Place the Diesel Air Compressor In Service KIA

REFERENCE:

065 AA1.04 3.5*/3.4*

TASK ID: 0341-009-01-013 I:8J INITIAL EXAM I:8J TRAINING JPM APPLICATION:

I:8J REQUALIFICATION D FAULTEDJPM 0 ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: 0 Perform 1:8:1 Plant Site D Annual Requal Exam D BVT 1:8:1 Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted 20 Minutes Actual minutes Critical:

1:8:1 No Time: Time: JPM RESULTS: D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1PL-031 JPM REVISION:

5 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Place the Diesel Air Compressor In Service EVALUATOR DIRECTION SHEET Diesel Air Compressor is running and loading. In-Plant A loss of electrical power has occurred, resulting in loss of the station a1r compressors.

The SM has directed you to place the diesel air compressor in service by performing the applicable steps of 10M-34.4.U, Diesel-Driven Air Compressor

[1IA-C-4]

Operation Section IV.A. 10M-34.4.U, Diesel-Driven Air Compressor

[liA-C-4]

Operation Revision 8 None 1 OM-34.4.U, Diesel-Driven Air Compressor

[liA-C-4]

Operation Revision 8 RTL#A5.640U 112-ADM-130 l.F04 Page 5 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read: INITIAL CONDITIONS:

A loss of electrical power has occurred, resulting in loss of the station a1r compressors.

INITIATING CUE: The SM has directed you to place the diesel air compressor in service by performing the applicable steps of 10M-34.4.U, Diesel-Driven Air Compressor

[liA-C-4]

Operation Section IV.A. D D D D At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". 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". Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 l.F04 Page 6 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 1PL-031 JPM REVISION:

5 JPM TITLE: Place the Diesel Air Compressor In Service 1. Verify that the SMIUS has authorized a precautionary or emergency start of the air compressor before proceeding.

STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)=> I SIU I START TIME: ______ _ EVALUATOR CUE: Provide Candidate a copy of 1 OM-34.4.U, Driven Air Compressor

[liA-C-4]

Operation.

1.1 Reviews procedure and verifies that the SM has authorized starting the compressor.

EVALUATOR CUE: If necessary, role-play the SM and authorized starting the compressor.

COMMENTS:

2.C Place the Load/Unload switch 2.1C Places the Load/Unload switch in the UNLOAD in the UNLOAD position. (down) position.

EVALUATOR CUE: The switch is in the UNLOAD (down) position.

COMMENTS:

R'TL#A5.640U 112-ADM-130l.F04 Page 7 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE

JPM NUMBER: 1 PL-031 JPM TITLE: Place the Diesel Air Compressor In Service I JPM REVISION:

5 STEP STANDARD ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 3.C Place the Manual/Off 3.1C Places the Manual/Off Reset/ Automatic switch in the Reset/ Automatic switch in MANUAL position.

MANUAL, and Check (after a 16 second delay) that the EVALUATOR CUE: starter operates to crank the The switch is in MANUAL. engine until 15 seconds has elapsed OR until the engine 3.2 After 16 second pre-lube delay, verifies Green starts (whichever occurs first). 'Engine Started' LED is lit. EVALUATOR CUE: Green 'Engine Started' LED is lit or Diesel is running. COMMENTS:

EVALUATOR NOTE: Step A.4 of the procedure will be N/ A since the Diesel started. 4.C After the engine has started, 4.1C Places the Load/Unload switch in the LOAD (up) Place the [liA-C-4]

Diesel position.

Driven Air Compressor EVALUATOR CUE: Load/Unload switch in the The switch is in the LOAD (up) position.

LOAD (up) position.

COMMENTS:

R'fL#A5.640U OPERATIONS JOB PERFORMANCE MEASURE 1/2-ADM-130l.F04 Page 8 of9 Revision I I JPM NUMBER: 1PL-031 JPM REVISION:

5 JPM TITLE: Place the Diesel Air Compressor In Service STEP STANDARD ( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR Stu 5. Verify [1VS-F-90], Roof 5.1 Verifies [1 VS-F-90-CS]

Standby lA Vent Fan Ventilator auto started (Red Control Switch RED llight LIT. light ON). EVALUATOR CUE: [1 VS-F-90-CS]

RED light LIT. COMMENTS:

6. When engine has started and 6.1 Verifies that the compressor loads, after a 45 second warmed up for (approximately warm up, and pressure is approximately 115 psig as 45 seconds), Check that the indicated on [PI-IIA-239]

on PNL-IIA-4 Standby compressor loads until pressure Instrument Air Compressor Control Panel. at the compressor discharge EVALUATOR CUE: pressure is approximately 115 psig on [PI-1IA-239].

[PI-IIA-239]

is at 114 psig and stable. (Compressor Instrument Panel). COMMENTS:

7. Verify [1IA-D-1C]

Instrument 7.1 Verifies [1IA-D-1C]

aligned for automatic operation Air Dryer is running. (Green, by observing the Green power light LIT. Power On light is ON). I EVALUATORCUE:

I GREEN light LIT. COMMENTS:

I IUL#A5.640U 1/2-ADM-1301.F04 Page 9 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE 1 JPMNUMBER:

1PL-031 I JPM REVISION:

5 JPM TITLE: Place the Diesel Air Compressor In Service STEP ( "C" Denotes CRITICAL STEP) 8. a. b. c. If desired align [ liA -C-4] to the Instrument Air Header as follows: Verify pressure on [liA-TK-2]

is being maintained 1 OOpsig. Slowly Open or Verify Open [liA-394], Standby Train Inlet Isolation.

Slowly Open or Verify Open [liA 395], Standby Train Inlet Isolation To Instrument Air Header. d. Slowly Open or Verify Open [liA-400], Standby Instrument Air Train Isolation.

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I S/U I 8.1 Contacts SM to determine if it is desired to align [liA-C-4]

to the Instrument Air Header. EVALUATOR CUE: Role-play SM and report that it is NOT desired to align [liA-C-4]

to the Instrument Air Header at this time. COMMENTS:

EVALUATOR CUE: That completes this JPM STOP TIME: _______ _

A d" D lppen IX s

o tr cenano u me 1L14N1 Facility:

BVPS Unit 1 Scenario No. 1 Op Test No.: 1LOT14 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 68(29): 100% power, EOL, Equ. XE Conditions, CB "D"@ 227 steps, RCS boron-100 Conditions:

ppm. Turnover:

Maintain 100% power. "A" Train Priority, 1FW-P-3B is OOS with 1FW-P-2 aligned to the "B" headeriAW TS 3.7.5, Condition B. Critical Tasks: 1. CT -50 (FR-S.l.A)

Crew isolates the main turbine 2. CT -3 (E-O.E) Crew manually actuates CIB 3. CT-11 (E-0.0) Crew closes cnmt isolation valves Event Event Type Event Description No. 1 (TS) SRO RCS loop 1, ch III, flow transmitter, FT-1RC-416 fails low. 2 (C) ATC, SRO River water pump, 1 WR-P-1A trips, requiring manual start of (TS) SRO 1WR-P-1B.

3 (C)ATC, SRO "B" RCP thermal barrier leak/ TV -1 CC-1 07B fails to auto close on high flow, requires manual closure. ' 4 (R) ATC "B" S/G feedwater leak inside CNMT requiring an unplanned (N) BOP, SRO power reduction per AOP 5 "B" feedwater leak increases once power is reduced to 94%. (M)ALL Reactor fails to trip from the control room, requires entry into FR-S.l. 6 (M)ALL Upon Rx trip, all 3 steam lines fault. 7 (I) BOP, SRO Automatic main steam line isolation failure, requires manual main steam line isolation.

8 Train "B" CIA fails to actuate along with train "A" valve (I) ATC, SRO MOV-1CH-378 failing to automatically close, ATC must manually actuate CIA or close MOV-1CH-378.

9 (I) ATC, SRO Automatic CIB actuation failure, requires manual actuation.

10 (C) BOP, SRO Control room dampers, 1VS-D-40-1A, 1B, 1C and 1D fail to automatically close, requires manual closing. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 2 Appendix D Scenario Outline 1L14N1

fter taking the shift at 100% power, RCS loop flow transmitter, FT-IRC-416 fails low. The crew will _agnose the indications and the SRO will address Tech Specs for the failed transmitter.

The IA Reactor Plant River Water Pump, 1 WR-P-IA then trips with an auto start failure of the standby pump, 1 WR-P-IB. The SRO will direct the crew to perform the actions of AOP 1.30.2, River Water/ Main Intake Structure Loss, to start 1 WR-P-IB and restore river water. The SRO will address Tech Specs. A leak will then occur in the "B" RCP thermal barrier heat exchanger.

The isolation valve, TV -1 CC-I 07B, will fail to auto close on high flow and will require manual closure. The BOP will refer to the alarm response procedure and the SRO will direct closure of the valve. A feed water leak will occur inside of the containment, the SRO will direct the crew to commence a rapid power reduction IA W AOP 1.51.1, "Unplanned Power Reduction".

The feedwater leak will increase in size during the power reduction, due to degrading conditions, the SRO will direct the ATC to trip the reactor. The reactor will fail to trip from the control room. The SRO will direct the ATC and BOP to perform the lOA's of FR-S.l, "Response to Nuclear Power Generation-ATWS. The turbine will also fail to automatically trip and must be manually tripped. The reactor will be tripped via a local operator after being dispatched and the crew will return to E-0. When the reactor is tripped, all three main steam lines will fault inside of containment.

main steam line isolation signal will fail to occur and the valves must be manually aligned. The safety injection that occurred as a result of the MSLB will fail to actuate the train "B" CIA signal, and train "A" CIA valve, MOV-ICH-378 will fail to automatically close. The ATC will recognize the failure and isolate the containment penetration via either manually actuating Train "B" CIA or manually closing MOV-ICH-378.

A CIB signal will fail to actuate on high containment pressure requiring the ATC to manually initiate CIB actuation.

The control room ventilation dampers 1 VS-D-40-IA through ID will not close on the CIB signal requiring the BOP to manually close the dampers. The SRO will transition to EOP E-2, "Faulted Steam Generator Isolation" based upon the rapid depressurization of the Steam Generators, then transition to ECA-2.1, "Uncontrolled Depressurization of All Steam Generators".

The scenario will be terminated after the crew transitions to ECA-2.1. Expected procedure flow path is E-0 FR-S. I E-0 E-2 ECA-2.1 NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 2 BEAVER VALLE' JWER STATION INITIAL CONDITIONS:

100% Power, CBD = 227, EQU XE EOL, 100 PPM Boron, IC-68 ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP Safety Status Panel 1FW-P-3B Normal Splash w/ Hi Power Screen, pg 4 on VB-Bl EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 1FW-P-3B OOS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago 3.7.5, Condition B, restore in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months lFW-P-2 aligned to "B" header SHIFT TURNOVER INFORMATION

1. 100% power, EOL equilibrium conditions, shift goal is to maintain 100% power. 2. Protected Train "A". SCENARIO SUPPORT MATERIAL REQUIRED 1. EOL Reactivity Placard 2. Protected Train "A" Placard 3. Safety Status PNL lights LIT for "B" AFW 4. lFW-P-2 aligned to B hdr placard BVPS-1L14 NRC 1, Rev 2 3 of23 PROCEDURES NEEDED 1 OM-6.4.IF Attachment 3 AOP 1.30.2 1 OM-30.4.AG AOP 1.6.8. AOP 1.15.1 AOP 1.51.1 E-0 E-2 ECA-2.1 FR-S.1 Attachment 1-K OST 1.36.7 BEAVER VALLE\ )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE -I Initialize IC-68, and establish initial plant conditions.

Insert the following per the Simulator Preload section of the HTML File for this scenario:

TRGSET 1 'JPPLP4(1)'

TRGSET 2 'JPPLSI(1)'

IMFCRF12A IMFCRF12B IMFINH48 IMFINH51 IMFINH50 IMF INH33 (0 0) TRGSET 4 'FNISPR(3)<=94' TRG 4 'IMF FWM03B 9E5 300' TRGSET 5 'RCCH107B

<= 0.1 IMF FWM03B (5 180) 2E5 300 2E3 IMF INH49 (0 0) TRUE lOR X021018R (0 0) ON TRGSET 8 'X021017C' TRG 8 'DOR X021018R TRGSET 20 'JPPLSI(2)'

lOR X011009C (20 0) 1 TRGSET 21 'X021022R.OR.X041013R' TRG 21 'DOR X011009C' TRGSET 22 'X021022R.OR.X041013R' TRG 22'DMF INH49' IMF VLV-SEA09 (0 0) 100 TRGSET 6 'X0610650' TRG 6 'DMF VLV-SEA09' IMF MSS01A(1 0) 900000 0 0 IMF MSS01B (1 0) 1.5e+006 0 0 BVPS -1L14 NRC 1, Rev 2 Reactor plant at 100% power, EOL, equilibrium conditions.

RCS boron =100 PPM, CBD@ 227 steps. Inserts all pre-loads required to support the scenario.

Trigger 1 = reactor trip Trigger 2 = Safety Injection Inhibit Automatic Reactor trip Inhibit Manual Reactor trip Inhibit Auto turbine trip (both trains) Inhibit Auto MSLI Inhibit CIB Actuation (both trains) WR-P-1B Auto Start Failure, Manual successful Trigger 4 = NIS PR N43 <= 94% "B" Feedwater header rupture Trigger 5 = TV -1 CC-1 07B closed "B" SG feedwater leak inside cnmt. CIA auto actuation inhibited Train B CIA RESET PB on Trigger 8 = Train B CIA actuation PB depressed Train A CIA manual actuation Trigger 20 = Train B SI actuation Train A CIA actuates on SI Trigger 21 = either SI reset pushbutton Reset CIA Trigger 22 =either SI reset pushbutton Reset CIA MOV-1CH-378 failed open Trigger 6 =Manual CS to close, MOV-1CH-378.

Delete malfMOV-1CH-378 failure S/G "A" Stm break inside CNMT. S/G "B" Stm break inside CNMT. 4 of23 BEAVER VALLE'I )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE . EXPECTED STUDENT RESPONSE I IMF MSS01C(1 0) 600000 IMF INH58 (0 0) TRUE IMF VLV-HVA01 (0 0) 100 TRGSET 11 'X19i142C' TRG 11 'DMF VLV-HVA01' IMF VLV-HVA02 (0 0) 100 TRGSET 12 'X19i144C' TRG 12 'DMF VLV-HVA02' IMF VLV-HVA03 (0 0) 100 TRGSET 13 'X19i143C' TRG 13 'DMF VLV-HVA03' IMF VLV-HVA04 (0 0) 100 TRGSET 14 'X19i145C' TRG 14 'DMF VLV-HVA04' IMF CRF14A (10 30) TRUE IMF CRF14B (10 35) TRUE IMF CRF01A (10 40) TRUE IMF CRF01B (10 45) TRUE BVPS -1L14 NRC 1, Rev 2 S/G "C" Stm break inside CNMT. TV -1 CC-1 07B auto close inhibit 1VS-D-40-1A failed open Trigger 11 = Manual CS to close, 1 VS-D-40-1A.

Delete malf 1 VS-D-40-1 A 1VS-D-40-1B Failed Open Trigger 12 =Manual CS to close, 1VS -D-40-1B Delete malf 1 VS-D-40-1 B 1 VS-D-40-1 C Failed Open Trigger 13 = Manual CS to close, 1 VS-D-40-1 C Delete malf 1 VS-D-40-1 C 1VS-D-40-1D Failed Open Trigger 14 =Manual CS to close, 1VS-D-40-1D Delete malf 1 VS-D-40-1D Failed Open Reactor Trip Brk A OPENS Reactor Trip Brk B OPENS SID of"A" Rod Drive MG Set SID of"B" Rod Drive MG Set 5 of23 BEAVER VALLE\ )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Assign shift positions SRO:, ________ _ ATC: ________ _ BOP: ________ _ Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators.

it needs to be run momentarily for an alignment change. When the shift turnover is completed, place the simulator to RUN and commence the scenario.

BVPS -1L14 NRC 1, Rev 2 Simulator running. 6 of23 Crew assumes control of the Unit.

BEAVER VALLE\ )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE *1 EVENT 1: RCS Loop "A" Channel III Flow instrument.

IMF RCS19AC (0 0) 0 30 Proceed to next event after SRO determines TS Action or at LE discretion.

BVPS -1L14 NRC 1, Rev 2 "A" RCS Loop Flow Channel III flow indication ATC recognizes low flow from one "A" loop channel. FI-1RC-416 fails low. BOP refers to ARP. A3-1 04, REACT COOL PUMP 1A Flow Low. SRO enters 1 OM-6.4.IF Attachment 3 to address the Status Panel 64, Bistable 3C, LOOP-1 R.C. Low flow transmitter failure. Flow is lit. SRO references Tech Specs. 7 of23 Tech Spec 3.3.1 Function 10, Condition K. Place channel in trip in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR reduce THERMAL POWER to < P-7 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months .

BEAVER VALLE' )WER STATION [-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENT2: WR-P-1A trips, WR-P-1B fails to auto start. IMF INH33 (0 0) (pre-loaded)

IMF AUXlOA (0 0) 1 WR-P-1A trips, 1 WR-P-1B fails to auto start. ATC recognizes loss of 1 WR-P-1A and reports to SRO. A1-40, CC WTR HT EXCH River WTR PP Disch Line 'A' Press Low. BOP refers to ARPs. A1-48, CC WTR HT EXCH River WTR PP Disch Line 'B' Press Low. A1-59, Intake Struct River WTR PP Disch Line 'A' Press Low. A1-67, Intake Struct River WTR PP Disch Line 'B' Press Low. A1-82, River Water PP Auto Start-Stop.

SRO enters AOP 1.30.2, River Water/Main Intake Structure Loss. ATC recognizes/reports 1 WR-P-1B auto start failure. Crew sounds standby alarm and announces "Loss of River Water" over page party. NOTE: 1WR-P-1B manually started. ATC Starts "B" RPRW Pump as follows; IA W Conduct of Operations guidelines, the crew may have started 1 WR-P-1B prior to AOP entry. It is not necessary to wait until the SRO references Tech Specs swing pump is made available.

Proceed to next event after SRO determines TS Action or at LE discretion.

BVPS -1L14 NRC 1, Rev 2 8 of23

Places discharge valve in CLOSE

Starts RPRW Pump

Opens pump discharge valve ATC checks CCR heat ex RW press-> 20 psig. BOP checks turbine plant river water system status TPRW pump-AT LEAST ONE RUNNING. Tech Spec 3.7.8 Condition A, Restore SWS train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Tech Spec 3.8.1 AC Sources-Operating for EDGs made inoperable by River Water.

BEAVER VALLE'. )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE --I EVENT 2: (continued)

ROLE PLAYS: If dispatched to locally investigate, wait 5 minutes then respond accordingly; SWGR-Breaker 1El0 is tripped, no relays are flagged, however there is an acrid smell around the cubical. SCREENHOUSE-report nothing obvious wrong with 1 WR-P-1A, if requested to check 1WR-P-1B operation

-report running SAT. IRF EPS003 (0 0) 0 IRF EPSOOS (0 0) 1 ROLEPLAY:

1 0 minutes after being dispatched to place WR-P-1C on the AE bus, contact control room and report WR-P-1C is racked onto the AE bus. BVPS -1L14 NRC 1, Rev 2 9of23 SRO directs operator to rack 1 WR-P-1C onto AE bus lAW 10M-30.4.AG.

BEAVER VALLE\ )WER STATION I INSTRUCTIONAL GUIDELINES m-1 PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT3: "B" RCP thermal barrier leak and failure of isolation valve TV -I CC-I 07B to auto close. IMF CCW28 (0 0) 28 180 0 Following command pre-loaded.

IMF INH58 (0 0) TRUE A4-7I, Radiation Monitoring High, RIS-CC-I 00, CCW monitor rising activity A3-8I, React Cool PP Thermal Barrier Cool Water Disch Temp High A3-73, React Cool PP Thermal Barrier Cool Water Discharge Flow High A4-72, Radiation Monitoring High-High NOTE: CCR surge tank level rises, CCR pump Crew may diagnose the Thermal Barrier operation is normal and heat exchanger leak and auto failure of TV -I CC-I 07B operation is normal. to close and take manual action to close the valve prior to procedural direction.

NOTE: SRO may initially enter AOP-1.6.7, Excessive Primary Plant Leakage or AOP LIS. I, Loss ofPrimary Component Cooling Water to diagnose the leak location.

BVPS -ILI4 NRC I, Rev 2 "B" RCP Seal Leakoff flow rises. Depending upon duration of the leak the following may be in alarm: A3-84, React Cool Lower Radial Bearing Temp High A3-87, React Cool Pump Seal LeakoffFlow High RIS-CC-I 00, CCW monitor alarms and indicates rising activity.

IO of23 Crew responds to alarms. BOP references ARPs. SRO enters AOP I.6.8, Abnormal RCP Operation, as the crew diagnoses the thermal barrier leak. Crew evaluates for immediate RCP trip criteria.

Crew determines that the RCP does not need to be secured. Crew monitors RIS-CC-I 00 for activity increase.

SRO directs Chemistry and Radiation Protection to sample CCW.

BEAVER VALLE't >WER STATION I INSTRUCTIONAL GUIDELINES -T PLANT STATUS I PROCE-DURALGLJIDANCE I EXPECTED STUDENT RESPONSE I EVENT 3: (continued)

NOTE: Event 4 is triggered to occur 3 minutes after the crew has isolated the thermal barrier leak. EVENT4: "B" Steam Generator Feedwater leak inside Containment.

Preloaded commands TRGSET 5 'RCCH107B

<= 0.1' IMF FWM03B (5 0) 2E5 300 2E3 BVPS -1L14 NRC 1, Rev 2 Evaluate for possible reactor coolant pump thermal barrier leakage. "B" steam generator feed flow rises as level lowers. Al-49, Containment Sump Level High alarms Al-35, Containment Air Total Press High-Low Chi Al-43, Containment Air Total Press High-Low Chii Al-36, Containment Air Total Press High-High Chi Al-44, Containment Air Total Press High-High Chii 11 of23 BOP verifies that a CCR pump is running. BOP monitors surge tank level trend and notes a rising level. SRO transitions to Attachment

2. A TC checks thermal barrier outlet isolation valves ALL open. Crew verifies high thermal barrier flow for "B" RCP. Crew recognizes that TV -1 CC-I 07B failed to auto close on high flow and manually closes valve. BOP monitors steam generator feedwater flow and level. ATC reviews ARPs. Crew diagnoses leakage inside of containment.

BEAVER VALLE' )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURACG-UIDANCE I EXPECTED STUDENT RESPONSE -] EVENT 4: (continued)

ROLEPLAY:

If necessary, as Shift Manager, direct the crew to perform a 5% per minute rapid load reduction using AOP 1.51.1, Unplanned Power Reduction.

NOTE: Event 5 is triggered to occur when power has been reduced to 94%. BVPS -1L14 NRC 1, Rev 2 SRO enters AOP 1.51.1, Unplanned Power Reduction.

Commence power reduction.

12 of23 SRO directs crew to perform rapid load reduction at 5%/min in accordance with AOP 1.51.1. A TC sounds the standby alarm and alerts plant personnel of the power reduction.

A TC energizes all pressurizer heaters, places backup heaters 2A and 2D to on. A TC develops reactivity plan for rapid downpower.

Sets the blender for amount of boric acid to support the load reduction and commences boration based upon reactivity plan. Monitors the control rods are inserting properly in Auto. Maintains Tavg within+/-5 °F ofTref BOP initiates turbine load reduction;

Depress 1st STG IN pushbutton

Lowers EHC SETTER

Sets LOAD RATE thumbwheel to 5%/minutc

Depresses GO BOP references and performs Attachment 3 to transfer busses to the offsite sources. SRO contacts system and informs them of the power reduction.

Evaluates ifEPP should be initiated.

SRO plans to notify chemistry once 15% power change occurs in less than one hour.

BEAVER VALLE"! )WER STATION I INSTRUCTIONAL GUIDELINES I PLANTSTATUSTPROCEDURALGUIOANC(T=-

EXPECTED STUDENT RESPONSE I EVENTs 5, 6, 7, 8, 9 & 10: Multiple malfunctions occur on reactor trip. All commands preloaded "B" Steam Generator Feedwater leak inside Containment increases once power is less than 94% on NIS Power Range N43. Reactor fails to trip from the Control Room. Auto Turbine trip fails, requires manual trip. All three SGs fault inside cnmt on the Rx trip. Auto Main Steam line isolation signal fails requires manual valve alignment.

CIA Train B fails to Auto actuate and MOV-1CH-378 (Train A) fails to Auto close. CIB both Trains, fails to Auto actuate. Crew identifies degrading "B" Steam Generator level, and steam flow I feed flow mismatch.

Crew determines that a manual reactor trip is warranted.

SRO directs manual Reactor trip. SRO enters E-0. ATC attempts a manual reactor trip, reports trip failure/ ATWS condition.

SRO transitions to FR-S.l. SRO directs operators to perform lOA's ofFR-S.1, implements FR-S.1 at step 1 RNO of E-0. BVPS -1L14 NRC 1, Rev 2 13 of23 BEAVER )WER STATION C-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTs 5, 6, 7, 8, 9 & 10 (continued)

Critical Task CT -50 (FR-S.l.A):

Crew isolates the main turbine from the SGs before WR SG level is less than 1 0% in 2/3 SGs. SAFETY SIGNIFICANCE--

Failure to trip the main turbine under the postulated plant conditions can lead to violation of the RCS emergency stress limit. All malfunctions are preloaded BVPS -1L14 NRC 1, Rev 2 Upon the reactor trip, all three steam generators will fault inside of containment.

14 of23 Crew performs IOAs of FR-S.1. BOP manually trips turbine. A TC verifies rods in Auto and inserting.

BOP verifies AFW status, Notes there is one motor driven AFW pump running. BOP verifies TV-1MS-105A and 105B open and Turbine-driven AFW pump, 1FW-P-2 is running. BOP verifies all AFW throttle valves are open. BOP verifies AFW flow. Crew initiates emergency boration flow by;

Verifying at least 1 charging pump is running

Verifying Safety Injection IS actuated and HHSI flow is indicated with PRZR pressure < 2335 psig BEAVER VALLE'. )WER STATION [ INSTRUCTIONAL GUIDELINES-I PLANT STATUS I PROCEDURALGUIOANCE I EXPECTED STUDENT RESPONSE I EVENTs 6, 7, 8, 9 & 10 (continued)

ROLEPLAY:

When requested to open the reactor trip breakers & trip the rod drive MG set output ACBs, insert: TRG! 10 Following commands are preloaded, activate Trigger 10 as soon as requested, 1st Rx trip breaker will open 30 seconds after actuating Trigger 10. IMF CRF14A (10 30) IMF CRF14B (10 35) IMF CRF01A (10 40) 1 IMF CRF01B (10 45) 1 ROLEPLAY:

When all breakers are open, report actions to the control room. BVPS -1L14 NRC 1, Rev 2 Crew continues in FR-S.1 after dispatching an operator.

15 of23 Crew alerts plant personnel by;

Sounding the standby alarm

Announcing a Unit 1 Rx trip w/o SCRAM

Dispatching an operator to locally trip the Rx BOP verifies turbine is tripped. BOP verifies MOV -1MS-1 OOA, B automatically CLOSED. BOP depresses the RESET Pushbutton on the Reheater Controller.

A TC checks if SI is actuated.

BEAVER VALLE\ )WER STATION [ INSTRUCfiONALGillDELINES PLJ\NTSTATUSfPROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTs 6, 7, 8, 9 & 10 (continued)

NOTE: This is a continuous action step, when the Rx is tripped, the crew will return to this step and then transition back to E-0, Step 1. BVPS -1L14 NRC 1, Rev 2 When the Rx is locally tripped. SRO returns to E-0, step 1. SI automatically actuated due to the Main Steam line breaks. 16 of23 A TC checks if Rx is subcritical

Power range channels < 5%

IR channels -negative startup rate ATC verifies Rx trip;

Rx trip and bypass breakers OPEN

Power range indication

-< 5%

Neutron flux -DROPPING BOP verifies Turbine trip

Throttle OR Governor valves ALL closed

Main Generator output brks -open

Exciter Circuit breaker -open BOP verifies Power to AC Emergency Busses;

Using VB-C voltmeters, verifies either AE or DF has voltage indicated BOP identifies that both emergency busses are energized from off-site power. Check SI status;

ATC checks that SI has previously actuated

A TC manually actuates SI by depressing both Train "A" and Train "B" pushbuttons ATCIBOP alerts plant personnel.

BEAVER VALLE' )WER STATION L INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE J EXPECTED STUDENT RESPONSE I EVENTs 6, 7, 8, 9 & 10 (continued)

ROLEPLAY:

After the crew has opened the control room operated valves and dispatched a field operator; INSERT BAT 10M464G.BAT Command will start the "A" Hydrogen analyzer in 9 minutes and the "B" in 15 minutes. After "B" is started report back to the CR that the WR Hydrogen analyzers have been placed in service. BVPS -1L14 NRC 1, Rev 2 17 of23 Check if SI flow should be reduced;

Verifies CNMT & Secondary radiation is consistent with pre-event

Verifies RCS subcooling

> 46°F

Verifies Secondary Heat sink exists

Verifies RCS pressure is stable or rising

Verifies PZR level< 17% Determines SI is required and continues with step 7. BOP verifies 1 VS-F-4A running. Crew dispatches an operator to perform 1 OM-46.4.0 to place hydrogen analyzers in service. A TC verifies SI system status;

Two charging pumps running

Both LHSI pumps running

BIT flow indicated BEAVER VALLE't >WER STATION I INSTRUCTIONAL GUIDELINES J -PLANT STATUS I GUIDANCE-I -EXPECTED STUDENT RESPONSE I EVENTs 6, 7, 8, 9 & 10 (continued)

NOTE: Crew may have pre-emptively isolated AFW flow to the "B" SG after fault was recognized.

NOTE: Evaluation of BOP performing Attachment 1-K begins on page 21. Critical Task CT -3 (E-O.E): Crew manually actuates at least one train of CIB equipment before an extreme (RED path) challenge develops to the containment CSF. Critical Task CT-11 (E-0.0): Crew closes Cnmt isolation valves such that at least one valve is closed on each critical phase A penetration before the end of the scenario.

NOTE: Main steam line isolation signal was inhibited for this scenario, MSLI should have been already actuated.

BVPS -1L14 NRC 1, Rev 2 List of Attachment 1-K Discrepancies:

Main Steam Line Isolation signal has failed. CIB signal fails to actuate both trains. Control Room Dampers 1VS-D-40-1A, 1B, 1C and 1 D fail to automatically close, must be manually closed from Building Service panel. Train "B" CIA failed to actuate with Train "A" CIA valve, MOV-1CH-378, failing to automatically close. RCS temperature

< 54 7°F and dropping due to Safety Injection flow and main steam line faults. 18 of23 BOP verifies AFW status;

Motor-driven AFW Pumps-ONE RUNNING

Turbine-driven pump TV-1MS-105A, B open A7-7 is NOT LIT, turbine driven pump running

AFW Throttle Vlvs all FULL OPEN

Total AFW Flow-> 370 GPM SRO directs BOP to perform Attachment 1-K. ATC checks RCS Tavg stable at or trending to 547°F;

ATC verifies main steam line isolation valves are closed or actuates MSLI at this time.

A TC reduces total feedflow to minimize C/D ATC checks Recirc Spray Pumps-NONE RUNNING BEAVER VALLE' )WER STATION [-

I PLANT STATUS I PROCE-DURALGUII)ANCE I EXPECTED STUDENT RESPONSE I EVENTs 6, 7, 8, 9 & 10 (continued)

NOTE: By now, CIB will have actuated, ATC will most likely have already tripped RCPs due to loss of CCR cooling. BVPS -1L14 NRC 1, Rev 2 19 of23 ATC verifies PRZR isolated;

PORVs-CLOSED

Spray Valves -CLOSED

Safety relief valves-CLOSED

PR T conditions

-CONSISTENT WITH EXPECTED VALUES

Power to at least one block valve -AVAILABLE (all available)

Block valves-AT LEAST ONE OPEN (all) ATC checks if RCPs should be stopped;

DIP between RCS pressure and highest SG pressure-<

200 PSID (350 PSID ADVERSE CNMT) Crew determines RCP's previously manually shutdown due to CIB actuation.

ATCIBOP checks if any SGs are faulted;

Pressures in all SGs-ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY SG COMPLETELY DEPRESSURIZED Crew determines that SG's are faulted.

BEAVER VALLE\ )WER STATION L-INSTRUCTIONAL GUIDELINES

-, PLANT STATLJS I GUIDANCE I EXPECTED STUDENT RESPONSE --, EVENTs 6, 7, 8, 9 & 10 (continued)

Terminate scenario when the crew determines that all SG's are Faulted and transitions to ECA-2.1. Classify Event: SITE AREA EMERGENCY per SS3, due to a Failure of the reactor protection system. BVPS -1L14 NRC 1, Rev 2 SRO transitions to E-2. All three SG pressures are lowering in an uncontrolled manner. Steam flow is indicated on all three SGs. SRO transitions to ECA-2.1, Uncontrolled Depressurization of All Steam Generators.

EVALUATOR NOTE: Use Administrative JPM, SRO A.4 to document SRO's declaration.

20 of23 ATC/BOP actuates CREVS;

Verifies the control room air intake and exhaust Dampers are CLOSED. SRO requests a BV -2 operator to verify Unit 2 CREVS actuation.

SRO directs STA to commence control room ventilation actions. Refer to Attachment 4-E. ATC/BOP verifies steamline isolation has occurred by checking all YELLOW SLI identified components are in the designated position. (previously verified)

BOP identifies "A", B" and "C" steam generator pressures are not "stable or rising". Crew identifies all SGs as faulted. SRO performs follow-up classification of theE-Plan event, completes an Initial Notification form and declares a Site Area Emergency.

BEAVER VALLE )WER STATION I INSTRUCTIONAL GUIDELINES 1-Pl.ANT STATUS I PROCEDURALGLJIDANCE I EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of Automatic Actions' BVPS -1L14 NRC 1, Rev 2 Both EDG's are running. Ensure Reheat Steam Isolation.

None running due to CIB. 21 of23 BOP performs the verifications/actions of Attachment 1-K 'Verification of Automatic Actions' as follows: Diesel generators-BOTH RUNNING with no Trouble Alarms, RW pumps running supplying cooling water flow. Verifies power to both Emergency 4KV AC busses. Station instrument air header pressure > 100 PSIG. Ensure Reheat Steam Isolation;

Verify MOV-1MS-100A,B-CLOSED

Reset reheater controller

Close MOV-1MS-204, gland stm spillover vlv Verify CCR Pumps-ONE RUNNING with recirc pressure>

100 PSIG. Align Neutron Flux Monitoring for Shutdown;

When operable IR channels <1 E-1 0 amp, check SR channels energized

Transfer NR-1NI-45 recorder to operable source and intermediate range displays Verify River Water System In Service;

RPRW Pumps-TWO RUNNING

Check CCR Heat EX RW pressure -> 20 psig. OR (IF CIB has occurred)

Verify RPR W flow to recirc spray hxs BEAVER VALLE' JWER STATION [---INSTRUCTIONAL GUIDELINES

[ PLANT STATUS I PROCEDURAL GUIDANCE [ EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of Automatic Actions' (continued)

Critical Task CT -3 {E-O.E): Crew Manually actuates at least one Determines Main Steamline Isolation previously completed, or manually aligns valves. train of CIB equipment before an Manually actuates CIB. extreme (RED path) challenge develops to the containment CSF. SAFETY SIGNIFICANCE--

Failure to Control Room Dampers 1 VS-D-40-1A, 1B, 1C manually actuate at least one train of and 1D fail to automatically close, manual containment cooling equipment under closure successful.

the postulated conditions demonstrates the inability of the crew to "recognize a failure or an incorrect automatic actuation of an ESF system or component." BVPS -1L14 NRC 1, Rev 2 22 of23 Check If Main Steamline isolation required;

CNMT pressure->

7 PSIG -OR-* Steamline pressure -< 500 PSIG -OR-* Steamline pressure high rate of change -ANY ANNUNCIATOR LIT (A7-41, A7-49, A7-57) Determines steamline isolation is required and YELLOW SLI marks are lit or manually aligns if necessary.

Check CIB And CNMT Spray Status;

Containment pressure-HAS NOT REMAINED<

11 PSIG and CIB is required

Verifies BLUE CIB marks lit

Verifies RCPs are all stopped

Requests BV-2 to verify CREVS equipment has actuated

Places CR ventilation intake and exhaust damper CS's in CLOSE BEAVER VALLE' JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS fPROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Critical Task CT-11 (E-0.0): Crew closes Cnmt isolation valves such that at least one valve is closed on each critical phase A penetration before the end of the scenario.

SAFETY SIGNIFICANCE--

Closing at least one containment isolation valve on each critical Phase A penetration, under the postulated plant conditions and when it is possible to do so, constitutes a task that "is essential to safety," because "its improper performance or omission by an operator will result in direct adverse consequences or significant degradation in the mitigative capability of the plant." BVPS -1L14 NRC 1, Rev 2 Train "B" CIA failed to actuate, manual actuation successful.

Train "A" CIA valve, MOV-lCH-378 failed to automatically close, manual isolation successful.

Discrepancies:

Automatic Main steam line isolation failed

CIB failed to automatically actuate, manual actuation successful

Train "B" CIA failed to actuate, manual actuation successful

Train "A" CIA valve, MOV-lCH-378 failed to automatically close, manual isolation successful

Control room dampers lVS-D-40-lA, lB, lC and lD failed to auto close 23 of23 Verify ESF Equipment Status;

Verify SI status by checking all RED SIS marks-LIT

Verify CIA by checking all ORANGE CIA marks-LIT

Verify FWI by checking all GREEN FWI marks-LIT When SR's are energized, verify Audible indication;

Verify operating SR Ch selected on Audio Count Rate Channel Selector Switch.

Audible indication functioning properly

Adjust Multiplier Sw & Volume as necessary Upon completion, reports any discrepancies to SRO.

/ A d" D

lppen IX s cenano Outline 1L14N2 Facility:

FENOC BVPS Unit 1 Scenario No.: 2 Op Test No.: 1LOT14 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 67(17): 65% power, MOL, Equ. XE Conditions, CB "D"@ 177 steps, RCS boron-Conditions:

1102 ppm. Turnover:

Maintain current power level. 1FW-P-3B OOS for maintenance, with lFW-P-2 aligned to "B" header lAW TS 3.7.5, Condition B. Control rods are in manual due to I&C MSP in progress .. Critical Tasks: 1. CT -4 (E-O.F) Establish AFW flow 2. CT -18 (E-3.A) Isolate ruptured SG 3. CT -20 (E-3.C) Crew depressurizes RCS 4. CT -21 (E-3.D) Crew terminates SI Event Malf. No. Event Type Event Description No. 1 (C) ATC, SRO lA charging pump trip, requires manual starting of lB. (TS) SRO 2 (C)ATC, SRO 200 gpd "B" steam generator tube leak (TS) SRO 3 (R) ATC Main feed pump, lFW-P-lB trips, requires rapid power (N) BOP, SRO reduction (AOP 1.24.1) 4 (M)ALL "B" Main feed regulating valve, FCV -1 FW -488 fails shut, leads to a Rx trip with a loss of offsite power. 5 Turbine driven aux feed pump, lFW-P-2 trips on overspeed (C) BOP, SRO and motor driven aux feed pump, 1FW-P-3A fails to auto start, requiring manual start of 1FW-P-3A.

6 (M)ALL 500 gpm SGTR in the "B" steam generator.

7 Main steam line isolation valve on the ruptured SG, TV-lMS-(C) BOP, SRO 101B failed open, requires the crew to perform an alternate MSLI alignment.

8 (C) ATC, SRO PRZR PORV fails open during depressurization requires closing of block valve. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 2

, Appendix D Scenario Outline 1L14N2

9:er taking the shift at 65% power, the running charging pump will trip. The SRO will enter AOP 1.7.1 to u.art the standby pump. The standby pump must be started and the backup pump will be aligned to replace the failed pump. Charging and letdown will be isolated per the AOP. The SRO will address Technical Specifications for the failed charging pump. Subsequently, a 200 gpd SG tube leak will develop on the "B" SG. AOP 1.6.4 will be implemented.

AOP 1.6.4 will provide direction to enter Mode 3 within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . The SRO will address Technical Specifications which also will require Mode 3 entry. 1FW-P-1B will trip, requiring the crew to rapidly reduce power to< 52% JAW AOP 1.24.1. The "B" SG main feedwater regulating valve fails closed, resulting in a reactor trip. Following the reactor trip, offsite power is lost. Additionally, the 3A motor driven aux feed pump fails to automatically start but may be started manually, The turbine driven aux feed pump will start but trips during startup and can be recovered if requested.

As a result of the reactor trip, a 500 gpm steam generator tube rupture will occur in the "B" SG. When isolating the "B" SG, the "B" main steam line isolation valve will fail open requiring the crew to close the "A" and "C" MSIV's . ..tbsequently, the PRZR PORV used to depressurize the RCS will fail open and require the motor operated block valve be closed to stop the PORV leakage. The scenario will be terminated when the crew has terminated safety injection.

Expected procedure flow path is EO E3. NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 2 BEAVER VALLE't JWER STATION INITIAL CONDITIONS:

65% Power, CBD = 177, EQU XE MOL, 1102 PPM Boron, IC-67 ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP Safety Status Panel 1FW-P-3B Normal Splash w/ Hi Power Screen, pg 4 on VB-B1 EQUIPMENT STATUS DATEffiME OOS TECHNICAL SPECIFICATION(S) 1FW-P-3B OOS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago 3.7.5, Condition B, restore in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1FW-P-2 aligned to "B" header SHIFT TURNOVER INFORMATION

1. 65% power, MOL equilibrium conditions, shift goal is to maintain 65% power. 2. Protected Train "A". 3. Control rods are in manual due to I&C MSP in progress.

SCENARIO SUPPORT MATERIAL REQUIRED 1. MOL Reactivity Placard 2. Protected Train "A" Placard 3. Safety Status PNL lights LIT for "B" AFW 4. 1FW-P-2 aligned to B hdr placard BVPS-1L14 NRC 2, Rev 2 3 of27 PROCEDURES NEEDED AOP 1.7.1 AOP-1.6.4 AOP-1.24.1 E-0 ES-0.1 E-3 Attach. 1-K, Verification of Automatic Actions Attach. 2-D, AC Power Restoration from Offsite 10M-7.4.AF 10M-7.4.W BEAVER VALLE) JWER STATION c=LNSTRl.JCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Initialize IC-67, and establish initial plant conditions.

Insert the following per the Simulator Setup section of the HTML File for this scenano: IMFFWM11B IMF INH35 (0 0) TRGSET 1 'CFWPSPEED(7)

>= 0.75' IMF FWM11 C (1 0) TRGSET 2 'RRCP445C

>= 0.3' TRGSET 3 'RRCP445D

>= 0.3' TRGSET 4 'RRCP456 >= 0.3' IMF PRS04A (2 0) IMF PRS04B (3 0) IMF PRS04C ( 4 0) TRGSET 6 'X071097C' TRGSET 7 'X071096C' TRGSET 8 'X071095C' IMF PRS03A (6 5) 25 IMF PRS03B (7 5) 25 IMF PRS03C (8 5) 25 TRGSET 5 'JPPLP4(1)'

IMF EPS01 (50) IMF VLV-MSS17 (0 0) 100 TRGSET 9 'JMLRCS3(2)'

TRG 9 'IMF RCS03B (5 0) 500' IRF EPS049 (10 300) 0 IRF AUX068 (10 305) OFF IRF EPS051 (10 315) 1 IRF AUX070 (10 320) ON IRF RWS016 (10 355) 100 0 IRF RWS019 (10 400) 100 0 BVPS-1L14 NRC 2, Rev 2 Reactor plant at 65% power, MOL, equilibrium conditions.

RCS boron 1102 PPM, CBD = 177 steps. Inserts all pre-loads required to support the scenario.

FW-P-3B OOS FW-P-3A auto start failure, manual start successful Set Trigger 1 on FW -P-2 speed FW -P-2 trips during startup Set Trigger 2 on PORV 455C position Set Trigger 3 on PORV 455D position Set Trigger 4 on PORV 456 position PCV -RC-455C reseat failure PCV -RC-455D reseat failure PCV -RC-456 reseat failure Set Trigger 6 on PORV 455C CS to close Set Trigger 7 on PORV 455D CS to close Set Trigger 8 on PORV 456 CS to close PCV -RC-455C leak PCV -RC-455D leak PCV -RC-456 leak Set Trigger 5 on Reactor Trip Station blackout on reactor trip, EDGs pickup emergency busses TV -1 MS-1 01 B failed open Set Trigger 9 on Tube leak initiation 500 gpm "B" SGTR on reactor trip CH-P-1A racked off 1AE bus 1A charging pump aux. oil pump stopped CH-P-1 C racked onto 1AE bus 1 C charging pump aux. oil pump in auto Open 1RW-162, RW Header A supply to 1CH-P-1C Open 1RW-165, RW Header B supply to 1CH-P-1C 4 of27 BEAVER VALLE\ JWER STATION c=INsTRUCTIONALGUIDELft-.fES . I PLANT STATUS I PROCEDURAL GUIDANCE_]__

EXPECTED STUDENT RESPONSE I IRF RWS022 (10 430) 100 0 IRF RWS020 (10 490) 0 0 IRF RWS014 (10 520) 0 0 IRF RWS017 (10 560) 0 0 TRGSET 11 'X060033R' IMF RCS03B (11120) 0.14 BVPS -1L14 NRC 2, Rev 2 Open 1RW-174, 1CH-P-1C RW return isolation Close 1RW-172, 1CH-P-1A RW return isolation Close 1RW-160, RW Header A supply to 1CH-P-1A Close 1RW-163, RW Header B supply to 1CH-P-1A Set Trigger 11 on 1CH-P-1B start (red light lit) 200 gpd SG 'B' Tube leak 5 of27 BEAVER VALLE) JWER STATION I INSTRUCTIONAL GUIDELINES

1 PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Assign shift positions SRO: ________ _ ATC: ________ _ BOP: ------------

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators.

When the shift turnover is completed, place the simulator to RUN and commence the scenario.

BVPS -1L14 NRC 2, Rev 2 it needs to be run momentarily for an alignment change. Simulator running. 6 of27 Crew assumes control of the Unit.

BEAVER VALLE\ )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE --I EVENT 1: 1A Charging Pump trip. IMF SISOSA (0 0) ROLE PLAYS: 1CH-P-1A trips. Charging flow decreases to zero. A3-49; Charging Pump Auto Start-Stop A3-50; Charging Pump Disch Press Low A3-78; React Cool PP Seal Inj Flow Low A3-58; Charging Pump Disch Flow High-Low SRO enters AOP 1.7.1, Loss of Charging or Letdown. Ifcrewisinvestigatingiftripisdueto AOP 1.7.1 lOA's. cavitation, report in as System Engineer that the VOID MONITORING BVT has just been completed with NO Voids Letdown isolated.

detected at B V -1. If crew dispatches operators to locally investigate, wait 5 minutes then report back as appropriate; SWITCHGEAR-Overcurrent relay is flagged on brk 1E11 for 1CH-P-1A.

PAB -1CH-P-1A-pump is shutdown, nothing obvious wrong with it. 1CH-P-1B-if previously started report running SAT, otherwise report looks ok 1CH-P-1B running. -ready to start. NOTE: Next event is at LE discretion following letdown restoration.

BVPS -1L14 NRC 2, Rev 2 7 of27 ATC announces multiple unexpected charging related alarms. A TC determines running charging pump tripped and informs SRO. BOP reviews ARPs. A TC performs Immediate Operator Actions of AOP 1.7.1;

isolates letdown by closing TV-1CH-200A, B

closing FCV-1CH-122

adjusting HCV-1CH-186 closed ATC verifies RCP thermal barrier flow OR seal injection flow to all RCP's. A TC verifies no charging pumps are running. ATC verifies VCT level is > 5%. ATC verifies VCT outlet to charging pumps valves are open (MOV-1CH-115C, E). Crew verifies pump did not trip due to cavitation.

ATC places control switch for 1CH-P-1A in PTL. ATC closes HCV-1CH-186.

ATC manually starts 1CH-P-1B.

ATC restores charging and seal injection flows. SRO directs the crew to restore letdown IA W 1OM-7.4.AF.

BEAVER VALLE'! JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCE-DURAL GUIDANCE I EXPECTED STUDENT RESPONSE I BVPS -1L14 NRC 2, Rev 2 8 of27 BOP restores letdown IA W 1 OM-7 .4.AF as follows: If directed; raises VCT level to 43% and manually cycles PCV-1CH-145.

Places charging flow to regen hx inlet control valve, FCV-1CH-122 in MANUAL and CLOSED. Verifies charging cnmt isolation valves open; MOV-1CH-310

& MOV-1CH-289 Verifies allltdn orifice isolation valves CLOSED TV-1CH-200A, 200B, & 200C Verifies TV-1 CH-204, regen hx/ltdn outlet cnmt isol valve is OPEN. Places ltdn back press reg valve, PCV-1CH-145, in MANUAL with controller set at 25% (75% open) Opens letdown to regen hx inlet isolation valves; LCV-1CH-460A

& LCV-1CH-460B MANUALLY adjusts FCV-1CH-122 to establish 30-50 gpm flow on FI-1CH-122A.

Monitors Letdown Pressure (PI-1CH-145) and Flow (FI-1CH-150) while placing letdown orifices in service. Opens TV-1CH-200A and adjusts FCV-1CH-122 as necessary to prevent flashing.

BEAVER VALLE'\ JWER STATION r INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Proceed with next event at LE discretion ROLEPLAY:

When dispatched to place ICH-P-IC on the AE bus, actuate TRG! 10, wait 10 minutes then contact control room and report ICH-P-IC is racked onto the 1 AE bus with cooling water aligned. BVPS -1L14 NRC 2, Rev 2 9 of27 If directed to place a second orifice in service; BOP lowers letdown pressure by adjusting PCV -1 CH-145 as necessary to maintain 120-140 psig on PI-I CH-145 and continues to monitor letdown pressure.

Throttles FCV-ICH-122 to establish a flowrate of > 60 gpm. Opens TV-1CH-200B or C and adjusts FCV-ICH-122 as necessary to prevent flashing.

Adjusts PCV-ICH-145 to obtain 300 psig on PI-ICH-145 and places controller in AUTO. Verifies all RCP seal injection flows between 6-9 gpm and adjusts HCV-ICH-186 as necessary.

Adjusts FCV-ICH-122 as necessary to restore Pzr level to program level then places FCV-ICH-122 controller in AUTO. Crew dispatches an operator to place ICH-P-IC on the AE bus. ATC places AE control switch for ICH-P-IC in auto.

BEAVER VALLE'. JWER STATION I INSTRUCTIONAL GUIDELINES

-]-PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I NOTE: If SRO did not identify applicable TS prior to next event being entered, ask as a follow up question.

EVENT2: 200 gpd "B" SG Tube Leak. (malfunction is preloaded, occurs 2 minutes after 1CH-P-1B is started).

IMF RCS03B (11120) 0.14 ROLEPLAY:

2 minutes after being dispatched to the N-16 monitor: report "B" SG tube leakage of 200 gpd and stable. BVPS -1L14 NRC 2, Rev 2 SRO references Tech Specs. SG "B" 200 gpd Tube Leak A4-88, Stm Gen N-16 Monitor Alert/High Trouble A4-71; Radiation Monitoring High A4-72; Radiation Monitoring High-High RIS-SV-100 is HI-HI@ 3X10 3 BD-101 Alert & Hi alarms on SPING SRO enters AOP 1.6.4, Steam Generator Tube Leakage. 10 of27 T.S. 3.5.2 Condition A, Restore train to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . LR 3 .1.4 Condition A, Restore charging pump to functional status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . ATC notes Radiation Monitor Alarms. BOP reviews ARPS, N-16 ARP directs entry into AOP 1.6.4. Crew dispatches an operator to the N-16 monitor to determine leakrate and affected SG. SRO estimates initial primary-to-secondary leakrate using radiation monitor alarm setpoints lAW AOP 1.6.4. Estimates at least 150 gpd based on existing alarms. ATC controls charging flow as necessary to maintain programmed PRZR level using FCV -1 CH -122 and HCV-1CH-186.

Crew determines PRZR level can be maintained with normal charging flow. Crew will attempt to identify the affected SG. ATC verifies VCT level can be maintained by normal makeup.

BEAVER VALLE', JWER STATION CINSTR0CfiONAL GUIDELINES j PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT RESPONSE -] EVENT 2: (continued)

Proceed to next event after SRO determines TS Action or at LE discretion.

BVPS -1L14 NRC 2, Rev 2 SRO references Tech Specs. 11 of27 SRO refers to Attachment 1, "SG Tube Leak Monitoring." SRO determines conditions support Action Level 3 entry. IA W with AOP 1.6.4, SRO determines plant shutdown is required; Be <= 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and MODE 3 entry within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . TS 3.4.13 Condition B with Primary to secondary leakage not within limit, be in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

BEAVER VALLE'. JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT3: Trip of"B" Main Feed Pump Rapid Power reduction IMF FWMOlB (0 0) NOTE: Crew may enter AOP 1.51.1, Unplanned Power Reduction.

BVPS -1L14 NRC 2, Rev 2 1FW-P-1B trips. A7-37, SG Feed Pump Auto Stop A7-39, SG Feed Pump Disch Flow Hi Start 2nd Pump A7-40, Steam Generator Feed Pump Disch Equalize Press Low SRO enters AOP 1.24.1, Loss ofMain Feed water. 12 of27 BOP recognizes feed pump trip and informs SRO. BOP performs Immediate Operator Action of AOP 1.24.1 and verifies 1FW-P-1A remains running. ATC refers to ARPs as time permits. IA W AOP 1.24.1, SRO directs load decrease to < 52% at 5%/minute.

BOP initiates turbine load reduction;

Depress 1st STG IN pushbutton

Set EHC SETTER to < 50% power equivalent

Set LOAD RATE thumbwheel to 5%/minute

Depresses GO ATC reduces Rx power by manually inserting control rods or initiating either a normal or emergency boration.

BOP;

Verifies both condensate pumps and one heater drain pump are running

Verifies A7-6, "Steam Generator Feed Pump Suet Press Low" -NOT IN ALARM

Verifies proper operation of FCV 1 FW-150A,B SG Main FW Pump Recirc Vlvs BEAVER VALLE'. JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT 3: (continued)

ROLEPLAY:

5 minutes after being dispatched to investigate 1FW-P-1B trip, report P-1B has a severe oil leak, oil reservoir is extremely low. When plant is stable, continue with next event at LE discretion.

BVPS -1L14 NRC 2, Rev 2 13 of27 BOP stabilizes SG levels by verifying steam flow is< available feed flow. BOP verifies SG levels are at or trending to program. BOP;

Verifies MFP < 450 amps on each motor

Verifies A7-40, "Steam Generator Feed Pump Disch Equalize Press Low" -NOT IN ALARM Crew dispatches an operator to investigate 1 FW-P-1 B trip.

BEAVER VALLE'. JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 4, 5, & 6 Feedwater Regulating Valve Failure (will require a reactor trip) IMF FWM07B (0 0) 0 Loss ofOffsite Power and 500 gpm SGTR in the "B" SG occurs when the Rx is tripped. (all commands preloaded)

BVPS-1L14 NRC 2, Rev 2 "B" Feed Reg valve fails closed Manual control unsuccessful.

Reactor trip required SRO directs the crew to trip the reactor, perform E-0 lOA's and report when ready to read. SRO enters E-0 AE and DF busses energized from EDG's. Loss of Off-Site Power SGTR 14 of27 lAW AOP 1.4.1, Loss of Process Control, BOP unsuccessfully attempts to take manual control of the "B" Feed Reg valve. BOP reports to crew that FCV-1FW-488 has failed closed and will not open under manual control. ATC manually trips reactor. ATC verifies Rx trip;

Rx trip and bypass breakers OPEN

Power range indication

-< 5%

Neutron flux -DROPPING BOP verifies Turbine trip;

Throttle OR Governor valves ALL closed

Main Generator output brks -open * . Exciter Circuit breaker -open BOP verifies Power to AC Emergency Busses;

Using VB-C voltmeters, verifies either AE or DF has voltage indicated BOP identifies that both emergency busses are energized from EDG's.

BEAVER VALLE'. JWER STATION [ .. INSTRUCTIONAL GUIDELINES

[ PLANT STATUS I PROCEDURAL G-UIDANCE

[ EXPECTED STUDENT RESPONSE .. [ EVENTS 4, 5, & 6 (continued)

NOTE: Based on scenario timing, Crew may elect to manually actuate SI. Crew may initially transition to ES-0.1 until

conditions degrade to require a SI. ES-0.1 actions not scripted.

BVPS-1L14 NRC 2, Rev 2 15 of27 Check SI Status;

ATC checks if SI is actuated

ATC verifies Cnmt press < 5psig

A TC verfies PRZR press > 1850 psig

ATC or BOP verifies Steamline pressure > 500 pstg A TC manually actuates SI by depressing both Train "A" and Train "B" pushbuttons.

ATCIBOP alerts plant personnel.

Check if SI flow should be reduced;

Verifies CNMT & Secondary radiation is consistent with pre-event

Verifies RCS subcooling

> 46°F

Verifies Secondary Heat sink exists

Verifies RCS pressure is stable or rising

Verifies PZR level is < 17% Determines SI is required and continues with step 7. BOP verifies 1 VS-F-4A running.

BEAVER VALLE'. JWER STATION [--iNSTRUCTIONAL GUIDELINES I PLANT STATOSTPROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 4, 5, & 6 (continued)

ROLEPLAY:

After the crew has opened the control room operated valves and dispatched a field operator; INSERT BAT 10M464G.BAT Command will start the "A" Hydrogen analyzer in 9 minutes and the "B" in 15 minutes. After "B" is started report back to the CR that the WR Hydrogen analyzers have been placed in service. Critical Task CT -4 (E-O.F): Crew establishes the minimum required AFW flow rate to the SGs before transition out of E-0, unless the transition is to FR-H.l, in which case the task must be initiated before RCPs are manually tripped in accordance with FR-H.l. . SAFETY SIGNIFICANCE

-Failure to establish the minimum required AFW flow rate results in "adverse consequence or a significant degradation in the mitigative capability of the plant." BVPS-1L14 NRC 2, Rev 2 1FW-P-3A has not auto started. 1FW-P-2 tripped on overspeed.

16 of27 Crew dispatches an operator to perform 10M-46.4.G to place hydrogen analyzers in service. ATC verifies SI system status;

Two charging pumps running (If crew had previously dispatched an operator to place 1CH-P-1C in service

Both LHSI pumps running

BIT flow indicated BOP verifies AFW System status;

Motor-driven AFW Pumps-NONE RUNNING

MANUALLY STARTS 1FW-P-3A

TV-1MS-105A, B-OPEN

A7-7 is LIT

AFW Throttle Vlvs all FULL OPEN

Total AFW Flow-> 3 70 GPM Crew determines 1FW-P-2 is tripped and dispatches an operator to investigate 1FW-P-2 status.

BEAVER VALLE. JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURALGUIDANCE I EXPECTED STUDENT RESPONS-E . I EVENTS 4, 5, & 6 (continued)

ROLEPLAY:

When dispatched to investigate 1FW-P-2, report back in 4 minutes that the throttle valve is tripped, there is no apparent damage, ask if reset should be attempted.

If requested to reset trip-throttle valve, wait 6 more minutes then insert commands to reset trip valve and report back to the control room. NOTE: Evaluation of BOP performing Attachment 1-K begins on page 26. BVPS -1L14 NRC 2, Rev 2 List of Attachment 1-K Discrepancies:

1FW-P-3A manual start required.

1FW-P-2 tripped on overspeed.

1FW-P-3B is OOS. RCS temperature<

547°F and dropping due to Safety Injection flow. 17 of27 SRO directs BOP to perform of Attachment 1-K. ATC checks RCS Tavg stable at or trending to 547°F;

A TC verifies no steam release is occurring

A TC verifies reheat steam is isolated

A TC reduces total feedflow to minimize C/D ATC checks Recirc Spray Pumps-NONE RUNNING BEAVER VALLE'. JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ] EVENTS 5, 6, & 7 (continued)

BVPS -1L14 NRC 2, Rev 2 A TC verifies PRZR isolated;

PORVs-CLOSED

Spray Valves -CLOSED

Safety relief valves -CLOSED

PRT conditions-CONSISTENT WITH EXPECTED VALUES

Power to at least one block valve -AVAILABLE (all available)

Block valves-AT LEAST ONE OPEN (all) RCP' s not running due to loss of offsite power. A TC checks if RCPs should be stopped; SRO transitions to E-3. 18 of27

DIP between RCS pressure and highest SG pressure -< 200 PSID ATCIBOP checks if any SGs are faulted;

Pressures in all SGs-ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY SG COMPLETELY DEPRESSURIZED Crew determines NO SG's are faulted. Crew checks if SG tubes are intact;

Check all SG levels-NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation-CONSISTENT WITH PRE-EVENT VALUES Crew determines "B" SG level rising in an uncontrolled manner and Secondary Radiation is NOT CONSISTENT WITH PRE-EVENT VALUES.

BEAVER VALLF. JWER STATION I INSTRUCTIONAL GUIDELINES I -PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 5, 6, & 7 (continued)

ROLEPLAY:

If requested as RP to perform a survey of the Main steam lines, wait 5 minutes then report that "B" Main steam line is showing elevated radiation levels. BVPS -1L14 NRC 2, Rev 2 All RCPs are off due to loss of power. 19 of27 ATC checks if CREVS should be actuated:

Check EITHER of the following;

Control Room Radiation Monitor RM-1RM-218A,B-NOT IN HIGH ALARM

CIB -HAS NOT OCCURRED Crew determines CREVS actuation NOT required.

SRO directs STA to Commence Control Room ventilation actions. Refer to Attachment 4-F. ATC checks if RCPs should be stopped;

DIP between RCS pressure and highest SG pressure<

200 PSID Crew identifies ruptured SGs;

Unexpected rise in any SG narrow range level -OR-* High radiation from any SG sample -OR-* High radiation from any SG steamline N16 monitor Radiation Protection survey -OR-* High radiation from any SG blowdown line RIS-1 SS-1 00, SG BD Sample Radiation Protection survey Crew determines "B" SG is ruptured.

BEAVER VALLE'. JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ] EVENT 6: (continued)

Critical Task: CT -18 E-3.A): Crew isolates feed flow into and steam flow from the ruptured SG and directs operator to close isolation valve(s) operated from outside of the control room before a transition to ECA-3.1 occurs. SAFETY SIGNIFICANCE

--Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SGs. Upon a loss .of differential pressure, the crew must transition to a contingency procedure that constitutes an incorrect performance that " ... necessitates the crew taking compensating action which complicates the event mitigation strategy .... " NOTE: In addition to these actions, the next 2 pages contain actions required to meet this Critical Task, these steps are BOLDED and designated as "CT-18" CT-18 BVPS -1L14 NRC 2, Rev 2 20 of27 ATCIBOP isolates flow from the ruptured SG. BOP places ruptured SG atm stm dump valve, PCV-lMS-lOlB, in MAN and verifies valve is CLOSED. BOP verifies residual heat release valve-CLOSED.

BEAVER VALLE'. JWER STATION [-. INSTRUCTIONAL GUIDELINES j -PLANT STATUS I PROCEDURAL GUIDANCE I

EXPECTED STUDENT RESPONSE I EVENT 6: (continued)

CT-18 ROLEPLAY:

5 minutes after being dispatched to locally isolate 1MS-16 and open 1MS-17, insert IRF FWM35 (0 0) 0 IRF FWM36 (0 0) 100 then report 1 MS-16 is CLOSED 1MS-15 is OPEN & 1MS-17 was OPENED. CT-18 EVENT7 CT-18 BVPS -1L14 NRC 2, Rev 2 21 of27 Steam supply valve from ruptured SG -OPEN

BOP verifies 1MS-16 open (unless previously closed IA W AOP 1.6.4 actions) BOP verifies 1FW-P-3A, Motor-driven AFW pump is runmng. BOP closes MOV-1MS-105, AFW Turbine Steam Isol Vlv. Crew dispatches an operator to locally isolate steam supply valve from "B" SG, 1MS-16 and to;

Verify open steam supply valve from "A" SG, 1MS-15

Unlock and open steam supply valve from "C" SG, 1MS-17 If necessary, crew restarts 1FW-P-2 by opening lMS-105, and resetting the trip throttle valve. BOP closes ruptured SG Pre nrtrn Drain Isol Vlv;

TV-1MS-111B BOP closes ruptured SG main steam trip, bypass, and non-return valves;

TV-1MS-101B trip

MOV-1MS-101B bypass

NRV-1MS-101B non return BOP recognizes TV-1MS-101B will not close. SRO directs BOP to close TV-1MS-101A and C.

BEAVER VALLE*. JWER STATION [-INSTRUCTIONAL GUIDELINES -T PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 5, 6, & 7 (continued)

CT-18 NOTE: AFW flow may have pre-emptively isolated to the "B" SG. BVPS -1L14 NRC 2, Rev 2 Condenser is not available due to loss of offsite power. (circulating water pumps not running) 22 of27 BOP checks ruptured SG level;

Narrow range level -> 31% BOP closes AFW throttle valves on ruptured SG;

MOV-1FW-151C, D BOP checks ruptured SG(s) pressure->

380 PSIG. BOP initiates RCS cooldown;

Determine required core exit temperature as a function of ruptured SG pressure

WHEN PRZR pressure < 1950 PSIG, THEN blocks low steamline pressure SI

Verifies station instru air press > 100 PSIG

Checks MSIVs-AT LEAST ONE OPEN (only ruptured SG MSIV is open)

Fully opens PCV-1MS-101A and PCV-1MS-101C to initiate a maximum rate cooldown When Core exit TCs (average of five hottest), <REQUIRED TEMPERATURE, BOP stops RCS cooldown and maintains core exit TCs <REQUIRED TEMPERATURE.

BOP Checks Intact SG Levels;

Narrow range level > 31% Controls feed flow to maintain narrow range level between 25% and 65%. Checks station instrument air header press> 100 PSIG BEAVER VALLE .)WER STATION [ --INSTRUCTIONALGUIDEI.JNES

[ PLANT STATUS I PROCEDURAL GUIDANCE [ EXPECTED STUDENT RESPONSE [ EVENTS 5, 6, & 7 (continued)

BVPS -1L14 NRC 2, Rev 2 23 of27 ATC checks PRZR PORV s and block valves;

Power to block valves -AVAILABLE

PORVs-CLOSED

Block valves-AT LEAST ONE OPEN A TC resets SI, CIA and CIB. BOP verifies Containment Instrument AVAILABLE by;

Checking Station Instrument Air Header Pressure > 100 PSIG

Verifying TV -liA-400 -OPEN

Checking CNMT instrument air header pressure -> 85 PSIG A TC checks if LHSI pumps should be stopped;

ATC checks LHSI pumps -ANY RUNNING WITH SUCTION ALIGNED TO RWST

ATC checks RCS pressure>

275 PSIG (400 PSIG ADVERSE CNMT)

ATC stops LHSI pumps AND places in AUTO BOP checks if RCS cool down should be stopped;

When Core exit TCs (average of five <REQUIRED TEMPERATURE BOP stops RCS cooldown and maintains core exit TCs <REQUIRED TEMPERATURE.

BOP checks ruptured "B" SG pressure-STABLE OR RISING.

BEAVER VALLE' JWER STATION CINSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 5, 6, & 7 (continued)

EVENTS: Selected PORV will not close and the associated block valve MUST be closed. BVPS -1L14 NRC 2, Rev 2 24 of27 ATC checks RCS subcooling based on core exit TCs -> 66°F A TC depressurizes RCS to minimize break flow and refill PRZR. Checks RCPs 1A and 1C-BOTH RUNNING;

NO RCPs running Opens one PRZR PORV. Checks depressurization method -EFFECTIVELY REDUCING RCS PRESSURE.

A TC continues depressurization until ANY of the following conditions satisfied;

PRZR level >76% (61% ADVERSE CNMT) -OR-* RCS subcooling based on core exit TCs < SUBCOOLING ON ATTACHMENT 6-A -OR-* BOTH of the following;

RCS pressure < RUPTURED SG press

PRZR level > 17% (38% ADVERSE CNMT) -OR-* BOTH of the following;

RCS pressure within 300 PSI of RUPTURED SG pressure

PRZR level> 47% (50% ADVERSE CNMT) ATC unsuccessfully ATTEMPTS to close PORV. A TC closes associated motor operated block valve.

BEAVER VALLE JWER STATION [-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT 8: (continued)

Terminate scenario when the crew has isolated HHSI flow and established a normal charging flowpath.

Classify Event: ALERT per FAl, due to a LOSS of RCS Barrier because of a RUPTURED SG resulting in an SI Actuation.

BVPS -1L14 NRC 2, Rev 2 RCS pressure is rising EVALUATOR NOTE: Use Administrative JPM, SRO A.4 to document SRO's declaration.

25 of27 ATC checks ifRCS pressure-RISING. Crew checks if SI flow should be terminated.

ATC verifies RCS subcooling is> 46°F (54°F ADVERSE CNMT) based on CETC's. BOP confirms secondary heat sink available by >370 gpm of feed flow available OR NR level in at least 1 SG > 31% (50% ADVERSE CNMT). A TC confirms RCS pressure is stable or rising. ATC reports PRZR level is > 17%. Crew determines that current plant conditions support SI termination.

ATC stops all but 1 charging pump. Isolate the BIT;

ATC closes MOV-1SI-867A, B, C, & D

ATC verifies HHSI flow indicates zero gpm A TC establishes charging flow by;

Closing FCV-1CH-122

Opening MOV-lCH-310 and MOV-1CH-289

Adjusting FCV-1CH-122 as necessary to maintain PRZR level between 31% and 50% SRO performs follow-up classification of theE-Plan event, completes an Initial Notification form and declares an ALERT.

BEAVER VALLE JWER STATION [ -INSTRUCTIONALGUIDEI.JNES-

-r PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of Automatic Actions' BVPS-1L14 NRC 2, Rev 2 Both EDG's are running. Ensure Reheat Steam Isolation 26 of27 BOP performs the verifications/actions of Attachment 1-K 'Verification of Automatic Actions' as follows: Diesel generators-BOTH RUNNING with no Trouble Alarms, RW pumps running supplying cooling water flow. Verifies power to both Emergency 4KV AC busses. Station Instrument Air Header Pressure >100 PSIG. Ensure Reheat Steam Isolation;

Verify MOV-1MS-100A,B-CLOSED

Reset reheater controller

Close MOV-1MS-204, gland stm spillover vlv Verify CCR Pumps -ONE RUNNING with recirc pressure > 1 00 psig. Align Neutron Flux Monitoring for Shutdown

When operable IR channels <1E-10 amp, check SR channels energized

Transfer NR-1NI-45 recorder to operable source and intermediate range displays Verify River Water System In Service

RPRW Pumps-TWO RUNNING

Check CCR Heat EX R W pressure -> 20 psi g. OR (IF CIB has occurred)

Verify RPR W flow to recirc spray hxs BEAVER VALLE JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ] Attachment 1-K 'Verification of Automatic Actions' (continued)

BVPS-1L14 NRC 2, Rev 2 1FW-P-3A had to be manually started. lFW-P-2 tripped on overspeed.

1FW-P-3B is OOS. Discrepancies:

1FW-P-3A had to be manually started

lFW-P-2 tripped on overspeed 27 of27 Check If Main Steamline isolation required;

CNMT pressure > 7 PSIG -OR-* Steamline pressure < 500 PSIG -OR-* Steamline pressure high rate of change -ANY ANNUNCIATOR LIT (A7-41, A7-49, A7-57) Determines steamline isolation is NOT required.

Check CIB And CNMT Spray Status;

Containment press -REMAINED < 11 PSIG Verify ESF Equipment Status;

Verify SI status by checking all RED SIS marks-LIT

Verify CIA by checking all ORANGE CIA marks-LIT

Verify FWI by checking all GREEN FWI marks-LIT When SR's are energized, verify Audible indication;

Verify operating SR Ch selected on Audio Count Rate Channel Selector Switch.

Audible indication functioning properly

Adjust Multiplier Sw & Volume as necessary Upon completion, reports any discrepancies to SRO.

/ A d" D lppen 1x s

o tr cenano u me 1L14N3 Facility:

FENOC BVPS Unit 1 Scenario No.: 3 Op Test No.: 1LOT14 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 211: 4.9% power, BOL, Equ. XE Conditions, CB "D"@ 114 steps, RCS boron-1851 Conditions:

ppm. Turnover:

Raise Power to 10-14% to place turbine online. Critical Tasks: 1. CT -12 (E-O.P), Manually actuate SLI 2. CT -17 (E-2.A), Isolate faulted SG 3. CT-48 (FR-P.l.A), Terminate ECCS flow I challenge to the integrity CSF Event Malf. No. Event Type Event Description No. 1 (R) ATC Raise Power to 10-14% (N) SRO 2 (C) BOP, SRO Leak collection exhaust fan, 1 VS-F-4A trips, requiring manual (TS) SRO start of 1 VS-F-4B 3 (C) ATC, SRO Charging flow control valve, FCV-1CH-122 fails shut in AUTO, requires manual control ofPRZR level. 4 (I) BOP, SRO Main steam header pressure transmitter, PT-1MS-464 fails low, requiring manual control of condenser steam dumps. (C) BOP, SRO SG atmospheric reliefvalve, PCV-1MS-101B fails open, 5 requires manual control of condenser steam dumps during (TS) SRO failure and local operator isolation.

6 (M) ALL Steam Break inside cnmt on "B" SG 7 (I) BOP, SRO SLI auto actuation failure, requires manual MSLI. 8 (C) BOP, SRO Aux feedwater control valve failed open, requires alternate isolation method. 9 (I) BOP, SRO Control room emergency ventilation system fails to actuate on CIB signal, requiring manual initiation. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev 2 Appendix D Scenario Outline 1L14N3 The crew will assume the shift at approximately 5% (4.9%) power with instructions to raise power to 10-14% to .ace the turbine online lAW the reactivity plan and 1 OM-52.4.A.

The ATC will initiate a dilution and withdraw control rods. After the power has raised to 6.4%, 1 VS-F-4A will trip, the crew will respond using the ARP which will direct the BOP to manually start 1 VS-F-4B. The SRO will address applicable TS .. After the power has raised to 8.0%, FCV-1CH-122 will fail closed in Auto, the ATC will be required to identify the failure and manually control FCV-1CH-122 to maintain Pzr level. 2 minutes after the crew blocks the Power Range Low Overpower Reactor trip, the main steam header pressure transmitter, MS-1PT-464 will fail low causing the condenser steam dumps to close in response.

The ensuing RCS heatup will cause SG atmospheric steam relief valve, PCV-1MS-101B to fail open, causing Rx power to rise and Tavg to drop due to the increased steam flow. The BOP will restore Rx power and Tavg by manually controlling the condenser steam dumps. The crew will unsuccessfully attempt to close the valve from the control room and then dispatch an operator to locally isolate. The BOP will control the condenser steam dumps while a local operator isolates the failed open SG atmospheric valve. A large steam break will then occur on the "B" SG inside of CNMT. The crew will enter E-0 and transition to E-2 after diagnosing a faulted SG. The steam break is of a magnitude that will cause conditions for an Integrity Red Path and require the crew to transition to FR-P.l. :dditional malfunctions occur during the event; 1. Automatic SLI fails to automatically actuate 2. "A" header AFW control valve will fail to close from the control room. 3. The control room emergency ventilation system, CREV's, fails to automatically actuate. The scenario will be terminated when the crew has established normal charging flow in FR-P.l. Expected procedure flow path is E-0 E-2 FR-P.1. NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev 2 BEAVER VALLE' JWER STATION INITIAL CONDITIONS:

4.9% Power, CBD = 114, BOL, 1851 PPM Boron, IC-211 ADDITIONAL LINEUP CHANGES STICKERS Place Aux steam to U2 placard on VB EQUIPMENT STATUS DATEffiME OOS Steam dump pot @J 6.95 (X10A039P) -SHIFT TURNOVER INFORMATION

1. Continue plant startup to place turbine on line lAW 10M-52.4A.

2. Aux steam is aligned to U-2. SCENARIO SUPPORT MATERIAL REQUIRED 1. Protected Train "A" Placard 2. 10M-52.4A, place kept up to step 6.a.l. 3. Reactivity Plan 4. Aux steam from Unit 2 placard posted 5. SETUP MONITOR SETUP VB-B1, display Low Power, page 1, Tavg VB-B2, SR & IR NI trend WR levels on trend, 1 OM-52.4.A, page 5, step 3 TECHNICAL SPECIFICATION(S)

PROCEDURES NEEDED 10M-52.4.A AOP 1.4.1 E-0 E-2 FR-P.1 Attachment 1-K, Verification of Automatic Actions Attachment 2-Y, AFW Throttle Valve Failure Prior to going to "RUN", ensure steam dump pot is set at 6.95 using variable XIOA039P to confirm. BVPS -1L14 NRC 3, Rev 2 3 of24 BEAVER VALLE .JWER STATION I INSTRUCTIONAL GUIDELINES--]

PLANT STATUS I PROCEDURALGUIDANCE I EXPECTED STUDENT RESPONSE -] Initialize IC 211 (5), and establish initial plant conditions.

Insert the following per the Simulator Setup section of the HTML File for this scenano: TRGSET 3 'FNISPR(2).GE.8.0' IMF CHS22 (3 0) 0 180 TRGSET 4 'FNISPR(2).GE.6.4' IMF AUX13G (4 0) IMF VLV-AFW04 (0 0) 100 TRGSET 6 'X060088D' TRG 6 'DMF CHS22' lOR X190005S (0 0) OFF TRGSET 13 'X191006S' TRG 13 'DOR X190005S' lOR X190020S (0 0) OFF TRGSET 14 'X191021C' TRG 14 'DORX190020S' IMFVLV-HVA01 (00) 100 TRGSET 7 'X191006S' TRG7 'DMFVLV-HVA01' IMF VLV-HVA02 (0 0) 100 TRGSET 8 'X191021C' TRG 8 'DMFVLV-HVA02' IMF VL V -HV A03 (0 0) 100 TRGSET 9 'X191006S' TRG9 'DMFVLV-HVA03' IMF VLV-HV A04 (0 0) 100 TRGSET 10 'X191021C' TRG 10 'DMF VLV-HV A04' IMF INH51 (0 0) TRUE BVPS -1L14 NRC 3, Rev 2 4.9% power, BOL, CB "D"@ 114 steps, RCS boron -1851 ppm. Inserts all pre-loads required to support the scenario.

Set trigger 3 on N42 at 8% power FCV-1CH-122 fails closed in AUTO (controller goes to 0% demand-OPEN position)

Set trigger 4 on N42 at 6.4% power VS-F-4A spurious trip (TS implications)

MOV-1FW-151D failed open Set trigger 6 on FCV-1CH-122 Manual PB depressed Delete malfunction, allows manual control ofFCV-1CH-122 Inhibit CREV's timer Train A Set trigger 13 on Train A Control Room Emerg Air Supply Actuation PB depressed Delete override, allows CREV' s timer Train A to operate Inhibit CREV' s timer Train B Set trigger 14 on Train B Control Room Emerg Air Supply Actuation PB depressed Delete override, allows CREV' s timer Train B to operate Fail 1 VS-D-40-1A open Set trigger 7 on Train A Control Room Emerg Air Supply Actuation PB depressed Delete malfunction, allows 1 VS-D-40-1A to CLOSE Fail1VS-D-40-1B open Set trigger 8 on Train B Control Room Emerg Air Supply Actuation PB depressed Delete malfunction, allows 1VS-D-40-1B to CLOSE Fail 1 VS-D-40-1 C open Set trigger 9 on Train A Control Room Emerg Air Supply Actuation PB depressed Delete malfunction, allows 1 VS-D-40-1 C to CLOSE Fail1VS-D-40-1D open Set trigger 10 on Train B Control Room Em erg Air Supply Actuation PB depressed Delete malfunction, allows 1VS-D-40-1D to CLOSE Auto MSLI inhibited 4of24 BEAVER VALLE' JWER STATION [-INSTRUCTIONAL GUIDELINES

-J PLANT STATUS I PROCEDURAL GUIDANCE J -. EXPECTED STUDENT RESPONSE TRGSET 11 'X07I057C' IMF XMT-MSS023A (11 120) 0 15 TRGSET 12 'X040010A' IMF MSS12B (12 0) 100 30 BVPS-1L14 NRC 3, Rev 2 Set trigger 11 on Train B Power Range Low Trip Block MS-1 PT -464 fails to zero Set trigger 12 on PCV -1 MS-1 01 B opening PCV -1 MS-1 01 B fails open 5 of24 BEAVER VALLE' JWER STATION L-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Assign shift positions SRO: ________ _ ATC: ________ _ BOP: ________ _ Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators.

When the shift turnover is completed, place the simulator to RUN and commence the scenario.

BVPS -1L14 NRC 3, Rev 2 it needs to be run momentarily for an alignment change. Simulator running. 6 of24 Crew assumes control of the Unit.

BEAVER VALLE' JWER STATION I INSTRUCTIONAL GUIDELINES-I PLANT STATUS I PROCEDURAL GUIDANCE f EXPECTED STUDENT RESPONSE I EVENTS l, 2 & 3: Normal Plant Startup, Rx Power increase to 10-14% to support Turbine Startup. NOTE: Reactivity plan requires 400 gallons dilution and 7 rod steps to raise power to 1 0%. Crew may elect to add total dilution volume in multiple steps. NOTE: Events 2 & 3 are triggered to actuate on rising power at 6.4% and 8% on N42, however each event may be inserted at LE discretion.

BVPS -1L14 NRC 3, Rev 2 7 of24 A TC commences raising reactor power to between 1 0 and 14%. A TC initiates control rod withdrawal and dilution lAW 10M-7.4.BB and the reactivity plan.

Places 1MU control switch to STOP for greater than 1 second

Place 43/MU Control switch in DIL orAL T DIL.

Set AM-1CH-114, Blender Total Flow Set Point to desired flow rate

Set YIC-1CH-168A, Blender Output Integrator, to desired dilution quanity

Reset YIC-1CH-168A

Place 1MU Control Switch to START

Verify FCV-1CH-114B opens, if ALT DIL selected, verify FCV-1CH-113B opens

Verify PG water to Blender flow rate indicated on FR-1CH-113.

When YIC-1CH-168A reaches setpoint, verify dilution automatically stops.

BEAVER VALLE' JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT 2: 1VS-F-4A trips (Automatically occurs 6.4% pwr or A11-33; Leak Collection Exhaust Fan Auto Stop BOP notes alarm, informs SRO. at LE discretion) 1VS-F-4A trips BOP refers to ARP. IMF AUX13G (4 0) ROLEPLAY:

Wait 5 minutes then report back as applicable.

SWITCHGEAR-If dispatched to breaker, report breaker 8N5 is tripped. If asked to attempt to reset, report that it will not reset. SRO references Tech Specs. FAN -If dispatched to fan, report that the fan housing is damaged, appears that the fan blades have failed. If started, 1VS-F-4B is running SAT. EVENT3: (Automatically occurs 8.0% pwr or at LE discretion)

FCV-1CH-122 fails closed in Auto IMF CHS22 (3 0) 0 180 BVPS -1L14 NRC 3, Rev 2 FCV-1CH-122 closes, Valve demand decreases A3-58, Charging Pump Discharge Flow Low PRZR level decreases.

8 of24 BOP manually starts 1VS-F-4B.

Crew dispatches operators to investigate cause of fan trip. TS 3.7.12 and LR 3.7.7. Condition A, restore in 7 days. A TC notes alarm and notifies crew. ATC notes problem with PRZR level control, IA W AOP 1.4.1, Process Control Failure, takes manual control ofFCV-1CH-122 and informs SRO. BOP reviews ARP.

BEAVER VALLE' JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I NOTE: ATC is required to manually control PRZR level for remainder of scenario.

Power increases continues NOTE: Events 4 and 5 will automatically actuate 2 minutes after the PR BLOCK TRAIN B control switch is placed in the BLOCK position but can be inserted at LE discretion.

EVENT4: PT -1 MS-464 fails low BVPS -1L14 NRC 3, Rev 2 SRO enters 10M-6.4.IF, attachment

2. Status lights on Panel 176 actuate at 10%. Status Light PNL 176, DlO,-'INT RNG RX TRIP BLOCKED' -LIT. Status Light PNL 176, B12,-'PW RA LO SET R TRIP BLKD' -LIT. All condenser steam dump valves close. RCS temperature rises. SG steam pressures rise. SG atmospheric steam dump valves open. 9 of24 SRO directs ATC to restore PRZR level to program value using FCV-1CH-122 in manual. Due to manual control of PRZR level, SRO establishes a level control band and Rx trip criteria of 5% low and 90% high. SRO notifies I&C to investigate.

ATC verifies P-10 bistables lit on Panel176.

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 status pnl 17 6, D 1 0 is LIT. ATC blocks the Power Range Low Overpower Trip by placing the PR BLOCK TRAIN A and TRAIN B control switches to the BLOCK position and verifies status pnl176, B12 is LIT. ATC selects highest power ranges on NR-45. BOP identifies condenser steam dump valves closing while in auto. lAW AOP 1.4.1, takes manual control of the condenser steam dumps and restores SG pressures.

BEAVER VALLE' )WER STATION I INSTRUCTIONAL GUIDEUNES--

I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENT 5: PCV -1 MS-1 01 B fails open after it opens in response to PT -1 MS-464 failure. NOTE: If operator response to PT-1 MS-464 failure is quick enough to not open SG atmospheric then insert following command at the LE discretion.

IMF MSS12B (0 0) 100 30 Valve requires manual isolation.

ROLE PLAYS (as appropriate):

When requested to isolate 1MS-24, wait 8 minutes then insert: IRF-MSS08 (0 0) 0 120 then report to the Control Room that 1MS-24 is isolated.

EVENT 5: (continued) "B" Atmospheric Steam Dump valve fails open. Steam Flow increases.

Reactor power increases.

RCS temperature and pressure decreases.

Bypass Feed regulating valve opens in response.

ADV will NOT close from BB control. NOTE: SRO references Tech Specs. Due to scenario progression, it may be necessary to ask SRO follow up questions regarding TS applicability for PCV-1MS-101B failure and DNB. Proceed with next event at LE discretion BVPS -1L14 NRC 3, Rev 2 10 of24 SRO directs ATC to manually close the open ADV. (PCV-1MS-101B).

ATC unsuccessfully attempts to manually close the 1 B SGADV. SRO requests I&C assistance.

Crew dispatches operator to isolate PCV-1MS-101B by closing 1MS-24. TS 3.7.4, Condition A-inoperable atmospheric dump valve. Requires restoring within 7 days. DNB TS, TS 3.4.1, restore RCS DNB parameters to within limits in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

BEAVER VALLE' .)WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I. EXPECTE-D STUDENT RESPONSE I EVENTS 6, 7, 8 & 9: (7-9 pre-loaded) "B" SG Steam Break inside CNMT with failure "B" SG steam break IMF MSSOlB (0 0) 2E6 120 SES BVPS -1L14 NRC 3, Rev 2 of automatic steamline isolation, AFW valve failed open along with CREV' s auto actuation failure. Al-35, 36, 43, 44, Multiple CNMT alarms. Steam flow rises. RCS temperature and pressure drop. SRO enters E-0. 11 of24 Crew determines that a manual reactor trip and SI is warranted.

A TC manually trips the reactor and depresses SI actuation pushbuttons.

ATC and BOP commence lOA's ofE-0. ATC verifies Rx trip;

Rx trip and bypass breakers open

Power range indication is < 5%

Neutron flux is dropping BOP verifies Turbine trip;

Throttle OR Governor valves ALL closed

Main Generator output brks -open

Exciter Circuit breaker-open BOP verifies Power to AC Emergency Busses;

Using VB-C voltmeters, verifies AE and DF busses both have voltage indicated BOP identifies that both emergency busses are energized from off-site power.

BEAVER VALLE' JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT RESPONSE l EVENTS 6, 7, 8 & 9: (continued)

ROLEPLAY:

After the crew has opened the control room operated valves and dispatched a field operator; INSERT BAT 10M464G.BAT Command will start the "A" Hydrogen analyzer in 9 minutes and the "B" in 15 minutes. After "B" is started report back to the CR that the WR Hydrogen analyzers have been placed in service. BVPS -1L14 NRC 3, Rev 2 12 of24 Check SI Status;

ATC checks that SI has previously actuated

A TC manually actuates SI by depressing both Train "A" and Train "B" pushbuttons A TC/BOP alerts plant personnel.

Check if SI flow should be reduced;

Verifies CNMT & Secondary radiation is consistent with pre-event

Verifies RCS subcooling

> 46°F

Verifies Secondary Heat sink exists

Verifies RCS pressure is stable or rising

Verifies PRZR level < 1 7% Determines SI is required and continues with step 7. BOP verifies 1VS-F-4B running. Crew dispatches an operator to perform 1 OM-46.4.G to place hydrogen analyzers in service.

BEAVER VALLE\ JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8 & 9: (continued)

NOTE: Evaluation of BOP performing Attachment 1-K begins on page 22. BVPS -1L14 NRC 3, Rev 2 List of Attachment 1-K Discrepancies:

Automatic Steam Line actuation failed and required all YELLOW identified components to be manually aligned. CREV' s failed to actuate, manual actuation SAT. RCS temperature

< 54 7°F and dropping due to Safety Injection flow. 13 of24 A TC verifies SI system status;

Two charging pumps running

Both LHSI pumps running

BIT Flow indicated BOP verifies AFW status;

Both motor-driven pumps running

Turbine-driven pump running

AFW throttle valves all FULL OPEN

Total AFW flow is> 370 gpm SRO directs BOP to perform Attachment 1-K. ATC checks RCS Tavg stable at or trending to 547°F;

A TC verifies no steam release is occurring

ATC verifies reheat steam is isolated

A TC reduces total feedflow to minimize C/D ATC checks Recirc Spray Pumps-NONE RUNNING BEAVER VALLE\ )WER STATION L -INSTRUCTIONAL GUfDELINES

-I PLANT STATUSTPROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9: (continued)

NOTE: By now, CIB will have actuated, A TC will most likely have already tripped RCPs due to loss of CCR cooling. BVPS-1L14 NRC 3, Rev 2 14 of24 ATC verifies PRZR isolated;

PORVs-CLOSED

Spray Valves -CLOSED

Safety relief valves -CLOSED

PRT conditions-CONSISTENT WITH EXPECTED VALUES

Power to at least one block valve -AVAILABLE (all available)

Block valves-AT LEAST ONE OPEN, (all) ATC checks if RCPs should be stopped;

DIP between RCS pressure and highest SG pressure-<

200 PSID (350 PSID ADVERSE CNMT)

Criteria for stopping is met-trips all RCPs if not previously tripped ATCIBOP checks if any SGs are faulted;

Pressures in all SGs-ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY SG COMPLETELY DEPRESSURIZED Crew determines "B" SG is faulted.

BEAVER VALLE\ >WER STATION I INSTRUCTIONAL GUIDELINES I PLANT-STATUS I PROCEDURAL GUIDANCE I ----EXPECTED STUDENT RESPONSE -] EVENTS 6, 7, 8 & 9: (continued)

NOTE: By now, CIB will have actuated, and therefore CREV' s should have automatically actuated.

NOTE: Dependent upon crew actions, at some point, plant conditions will degrade to first ORANGE path and then to RED path requiring the crew to enter FR-P.l. All of the actions ofE-2 have been scripted.

NOTE: Automatic main steamline isolation was inhibited.

Critical Task: CT-12 (E-O.P) Crew manually actuates main steam line isolation before a Severe (orange path) challenge develops to either the Sub-criticality or Integrity CSF or before transition to ECA-2.1, whichever occurs first. SAFETY SIGNIFICANCE

--Failure to close the MSIV s under these plant conditions causes challenges to CSFs beyond those irreparably introduced.

BVPS-1L14 NRC 3, Rev 2 SRO transitions to E-2, Faulted Steam Generator ATC/BOP recognizes that the control room air intake Isolation.

and exhaust Dampers are NOT closed and the timers have not started. 15 of24 ATCIBOP actuates CREVS by;

Manually actuates CREV's by depressing both trains PB's

Verifying the control room air intake and exhaust dampers are CLOSED SRO requests a BV -2 operator to verify Unit 2 CREVS actuation.

SRO directs STA to commence Control Room ventilation actions. Refer to Attachment 4-F. BOP verifies steamline isolation did NOT occur. BOP places all YELLOW SLI identified components into the designated position.

BEAVER VALLE'. )WER STATION [ INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUTI5.AJ.fCE I EXPECTED STUDENT RESPONSE . EVENTS 6, 7, 8 & 9: (continued)

Critical Task: CT -17 {E-2.A) Crew isolates the faulted SG and directs operator to close isolation valves operated from outside of the control "B" SG pressure is lower than "A" & "C. "A" & "C" may be slowly lowering as expected due to the cooldown.

Crew should respond with "stable" for "A" & "C" SG's. "B" SG pressure & level lowering.

room before transition out ofE-2. MOV-1FW-151D is failed open, crew may have previously responded while in E-0 using EOP SAFETY SIGNIFICANCE--

Failure to attachment 2-Y. isolate a faulted SG that can be isolated causes challenges to CSFs beyond those irreparably introduced by the postulated conditions.

BVPS -1L14 NRC 3, Rev 2 16 of24 BOP identifies "A" & "C" steam generator pressures are "stable or rising". Crew identifies "B" SG as faulted. BOP isolates the faulted, "B" SG as follows;

Verifies FWI (previously verified via Attachment 1-K)

Closes AFW throttle valves on "B" SG MOV-1FW-151C, D (If not previously identified, Crew isolates AFW thru MOV-1 FW -151 D using Attachment 2-Y and secures 1FW-P-3B.)

Directs field operator to verify closed 1 MS-16 and verify open 1 MS-15 and 1 MS-1 7.

Verifies closed, "B" SG Atmospheric steam dump valve. (ADV is failed-previously isolated)

Verifies Residual Heat Release valve is closed. BOP verifies PPDWST level is> 27.5 feet.

BEAVER VALLE'! )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9: (continued)

ROLEPLAY:

If the crew has not identified that entry into FR-P.1 is required by this time, after the crew makes a determination to transition to either E-1 or ES-1.1, as STA report to the SRO that a RED path exists on the Vessel Integrity status tree. BVPS-1L14 NRC 3, Rev 2 SRO determines transition to FR-P.1, "Response to Imminent Pressurized Thermal Shock Condition" is appropriate.

17 of24 Crew checks if SG tubes are intact;

Check all SG levels-NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation-CONSISTENT WITH PRE-EVENT VALUES Determines no SG levels are rising in an uncontrolled manner and Secondary Radiation-is CONSISTENT WITH PRE-EVENT VALUES. Crew determines SG Tubes ARE INTACT. Crew checks if SI flow should be reduced. ATC verifies RCS Subcooling is greater than 54°F, ADVERSE CNMT, based on CETC's. BOP confirms secondary heat sink available by >370 gpm of feed flow available OR NR level in at least 1 SG>50%. ATC confirms RCS pressure is stable or rising. ATC checks ifPRZR level is> 38%. BOP verifies PPDWST level is> 27.5 feet.

BEAVER VALLE'. )WER STATION j INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAl...

GUIDANCE_!_

EXPECTED STUDENT RESPONSE ---, EVENTS 6, 7, 8 & 9: (continued)

NOTE: Dependant upon crew actions and timing to this point, the faulted SG may have already blown down and a RCS heatup may be occurring, if not, the RNO actions should already have been completed in E-2. BVPS -1L14 NRC 3, Rev 2 18 of24 Check RCS pressure to determine ifFR-P.l procedure actions are necessary.

ATC verifies RCS pressure is > 225 psig ( 400 psig ADVERSE CNMT). SRO continues in procedure.

A TC checks RCS cold leg temperatures

-stable or rising. BOP checks station instrument air header pressure on PI-IIA-106 is> 100 PSIG. ATC checks PRZR PORV Block valves;

Power to block valves -AVAILABLE

Block valves-AT LEAST ONE OPEN ATC checks ifPORV's should be closed;

Verifies OPPS is NOT in service

Verifies RCS pressure is < 2325 psig

Verifies all PORV's are closed ATC verifies HHSI flow is indicated.

BEAVER VALLE\ )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I -EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8 & 9: (continued)

ROLE PLAY: \\'hen requested to energize 480v stub busses, insert IRF EPS138 (0 0) CLOSED IRF EPS140 (0 0) CLOSED IRF EPS176 (0 0) CLOSED IRF EPS183 (0 0) CLOSED then report all breakers closed. BVPS-1L14 NRC 3, Rev 2 19 of24 Crew checks if SI flow can be terminated.

ATC verifies RCS subcooling based on CETC's is greater than subcooling listed on Attachment 6-E. ATC verifies RVLIS Full Range level is> 64%. ATC resets SI, CIA and CIB. ATCIBOP resets SIS auto recirc changeover.

BOP energizes Stub Busses by;

Checking both 4kv stub bus bkrs not closed.

Places all CCR and Aux RW CS' s in PTL.

Energizes lAE stub bus by dosing ACB-1E5.

Energizes lDF stub bus by closing ACB-1F5. ATC verifies 480v stub busses are not energized by no indicating lights on either Boric Acid transfer pump or CNMT vacuum pumps. BOP places CS's for CNMT Air Recirc fans and CRDM Shroud fans in PTL. ATC places CS's for the 2A & 2B PRZR htrs in PTL. Crew dispatches operator to close local 480v breakers to energize stub busses and feeder bkrs to MCCl-Ell and MCC1-El2.

BEAVER VALLE'. JWER STATION I INSTRUCTIONALGOIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9: (continued)

Critical Task: CT-48 (FR-P.l.A)

Terminate ECCS flow so that ifthe challenge to the integrity CSF is;

Severe, an extreme challenge is prevented

Extreme, RCS pressure and temperature are controlled before the end of the scenario SAFETY SIGNIFICANCE

--Failure to terminate ECCS flow when SI termination criteria are met causes the PRZR to fill and RCS pressure to increase.

Additionally, the unnecessary continuation of ECCS flow needlessly aggravates the thermal stress on the reactor vessel. BVPS-1L14 NRC 3, Rev 2 Indicated SIIBIT flow decreases to zero. 20 of24 BOP establishes Instrument Air to CNMT by;

Checking Station Instrument Air Header Pressure > 100 PSIG

OPENS TV-liA-400

Checking CNMT instrument air header pressure -> 85 PSIG SRO directs ATC to stop 1 charging pump. ATC stops all but 1 charging pump. ATC stops both LHSI pumps AND places in AUTO. SRO directs A TC to isolate the BIT;

ATC closes MOV-1SI-867A, B

ATC closes MOV-1SI-867C, D BEAVER VALLE\ )WER STATION [niNSTRUCTIONALGUIDELTNES I PLANT STAfOSTPROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9: (continued)

Terminate scenario when the crew establishes normal charging flowpath in FR-P.l. Classify Event: ALERT per HA4, due to a Stearn Line Break inside CNMT. BVPS-1L14 NRC 3, Rev 2 EVALUATOR NOTE: Use Administrative JPM, SRO A.4 to document SRO's declaration.

21 of24 SRO directs ATC to establish normal charging flowpath;

ATC closes FCV-1CH-122

ATC opens MOV-1CH-310

ATC opens MOV-1CH-289

ATC adjusts FCV-1CH-122 to maintain PRZR level SRO performs follow-up classification of theE-Plan event, completes an Initial Notification form and declares an ALERT.

BEAVER VALLE\ )WER STATION [ INSTRUCTIONAL GUIDELINES I PLANT STATUSTPROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of Automatic Actions' BVPS-1L14 NRC 3, Rev 2 Both EDG's are running. Ensure Reheat Steam Isolation.

CCR pumps not running due to CIB. 22 of24 BOP performs the verifications/actions of Attachment 1-K 'Verification of Automatic Actions' as follows: Diesel generators-BOTH RUNNING with no Trouble Alarms, R W pumps running supplying cooling water flow. Verifies power to both Emergency 4KV AC busses. Station Instrument Air Header Pressure > 1 00 psig. Ensure Reheat Steam Isolation;

Verify MOV-1MS-100A,B-CLOSED

Reset reheater controller

Close MOV-1MS-204, gland stm spillover vlv Verify CCR Pumps-ONE RUNNING with recirc pressure > 100 psi g. Align Neutron Flux Monitoring for Shutdown;

When operable IR channels <1E-10 amp, check SR channels energized

Transfer NR-1NI-45 recorder to operable source and intermediate range displays Verify River Water System In Service;

RPRW Pumps-TWO RUNNING

Check CCR Heat EX RW pressure -> 20 psig. OR (IF CIB has occurred)

Verify RPR W flow to recirc spray hxs BEAVER VALLE\ )WER STATION I INSTRUCTIONAL GUIDELINES -r PLAf.*fTSTATUS I PROCEDURAL GUIDANC(]

EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of Automatic Actions' (continued)

Critical Task: CT -12 (E-O.P) Crew manually actuates main steam line isolation before a Severe (orange path) challenge develops to either the Sub-criticality or Integrity CSF or before transition to ECA-2.1, whichever occurs first. SAFETY SIGNIFICANCE--

Failure to close the MSIV s under these plant conditions causes challenges to CSFs beyond those irreparably introduced.

BVPS-1L14 NRC 3, Rev 2 Automatic Steam Line isolation actuation failed, requires components to be manually aligned. CREV' s failed to automatically actuate, manual actuation successful.

23 of24 Check If Main Steamline isolation required;

CNMT pressure > 7 PSIG -OR-* Steamline pressure < 500 PSIG -OR-* Steamline pressure high rate of change -ANY ANNUNCIATOR LIT (A7-41, A7-49, A7-57) Determines steamline isolation is required and YELLOW SLI marks are lit or manually aligns if necessary.

Check CIB And CNMT Spray Status;

Containment pressure-HAS NOT REMAINED < 11 PSIG and CIB is required

Verifies BLUE CIB marks lit

Verifies RCPs are all stopped

Requests BV -2 to verify CREVS equipment has actuated

Places CR ventilation intake and exhaust damper CS's in CLOSE BEAVER VALLE'\ )WER STATION I INSTRUCTIONALGTITiSELlNES

] PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE *1 Attachment 1-K 'Verification of Automatic Actions' (continued)

BVPS-1L14 NRC 3, Rev 2 Discrepancies:

CREV's failed to automatically actuate

Automatic Steam Line actuation failed 24 of24 Verify ESF Equipment Status;

Verify SI status by checking all RED SIS marks-LIT

Verify CIA by checking all ORANGE CIA marks-LIT

Verify FWI by checking all GREEN FWI marks-LIT When SR's are energized, verify Audible indication;

Verify operating SR Ch selected on Audio Count Rate Channel Selector Switch

Audible indication functioning properly

Adjust Multiplier Sw & Volume as necessary Upon completion, reports any discrepancies to SRO.

/ Appendix D s cenano utme

o r 1L14N4 Facility:

BVPS Unit 1 Scenario No.: 4 Op Test No.: 1LOT14 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 62(18): 81% power, MOL, Equilibrium Xe, CB "D"@ 206 steps, RCS boron-1012 Conditions:

ppm. Turnover:

Rx is at 81% power due to isolating the condenser "D" Waterbox for cleaning. "A" Train Priority, 1FW-P-3B is OOS with 1FW-P-2 aligned to the "B" header lAW TS 3.7.5, Condition B. Critical Tasks: 1. CT -1 (E-O.A) -Manually Trip Reactor 2. CT -6 (E-0.1) -Establish 1 train of HHSI Event Malf. No. Event Type Event Description No. 1 (C)ATC, SRO The 1A boric acid transfer pump trips requiring aligning the (TS) SRO standby train for service. 2 (TS) SRO Ch 2, cnmt pressure transmitter, PT-1LM-100B, fails high. 3 (R) ATC Cooling tower pump, CT-P-1C trips, causing degraded (N) BOP, SRO condenser

vacuum, power reduction.

4 (I) ATC, SRO Auto rod insertion fails on load reduction, ATC manually controls Tavg. 5 (M)ALL Condenser Low-Low vacuum causes turbine trip. 6 (I) ATC, SRO Auto Rx trip fails to occur, requires ATC to manually trip the reactor from BB-A. 7 Exciter circuit breaker fails to auto open on Rx trip, requires (C) BOP, SRO BOP to manually trip the exciter circuit breaker. 8 (M) ALL 1500 GPM LOCA one minute after Rx trip. 9 "A" charging pump, 1CH-P-1A trips, and "B" charging pump, (C) ATC, SRO 1CH-P-1B fails to auto start on Safety Injection, requiring manual start. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 2

. Appendix D Scenario Outline 1L14N4 * +ter taking the shift, boric acid transfer pump, 1CH-P-2A will trip. SRO "'rill direct placing the 2B boric acid . ..a1sfer pump in service lAW 10M-7.4.R, "Transfer oflnservice Boric Acid Tank". SRO will also address Technical Specifications.

After the crew has reestablished a boric acid flowpath, containment pressure ch 2 transmitter, PT-1LM-100B fails high. The SRO will enter 1 OM-1.4.IF and review the Technical Specifications.

The SRO will then contact I&C to trip the applicable bistables.

The "C" cooling tower pump will trip causing condenser vacuum to degrade. The crew will enter AOP 1.26.2, "Loss of Condenser Vacuum". While working through the Loss of Condenser Vacuum AOP, they will recognize the need to reduce turbine load to prevent exceeding hotwell temperature of 130 °F. At this point the SRO will enter AOP -1.51.1, "Unplanned Power Reduction" and reduce turbine load. The control rods will fail to auto insert during the turbine load reduction.

The ATC will have to insert control rods in manual to maintain Tavg to Tref. During the load reduction the turbine will trip due to low condenser vacuum, the plant will be greater than 49% power (P-9), but the Rx will fail to auto trip. The ATC will successfully trip the reactor from Bench board "A". During the immediate operator actions ofE-0, the BOP will be required to manually open the exciter circuit breaker due to an auto open failure. nqe minute after the Rx is manually tripped a 1500 GPM LOCA will occur on the "B" RCS loop. The LOCA 1l cause a Safety Injection actuation due to low RCS pressure.

Upon the SI actuation the "A" charging pump will trip, and the "B" charging pump will fail to auto start, requiring the ATC to manually start the "B" charging pump to restore high head safety injection flow. The crew will enter E-0, transition to E-1 due to containment parameters, and then to ES-1.2 to cooldown the RCS. The scenario will be terminated when RCS cooldown is commenced in ES-1.2. Expected procedure flow path is E-0 E-1 ES-1.2. NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 2 BEAVER VALLE :>WER STATION INITIAL CONDITIONS:

81% Power, CBD = 206, Equilibrium XE, MOL, 1012 PPM Boron, IC-62 (18) ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUPS 1FW-P-3B PTL YCTonCS VB-B 1, Hi Power screen 1CT-P-1D PTL YCTonCS EQUIPMENT STATUS DATEffiME OOS TECHNICAL SPECIFICATION(S) 1FW-P-3B OOS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago 3.7.5, Condition B, restore in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1FW-P-2 to "B" header ------SHIFT TURNOVER INFORMATION

1. 81% power, MOL, Equilibrium Xe, Boron 1012 ppm, CBD at 206 steps. Shift goal is to maintain 81% power. 2. "D" Condenser Waterbox is isolated for cleaning.

SCENARIO SUPPORT MATERIAL REQUIRED 1. MOL Reactivity Placard. 2. Protected Train "A" Placard. 3. 4. 5. BVPS -1L14 NRC 4, Rev 2 3 of24 PROCEDURES NEEDED 10M-1.4.1F, Att. 1 10M-7.4.R 10M-7.4.W AOP-1.26.2 AOP-1.51.1 E-0 E-1 ES-1.2 Attachment 1-F Attachment 1-K 10M-46.4.G I I I I I

BEAVER VALLE' )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE --] Initialize IC-62, and establish initial 81% power, MOL, Equilibrium Xe, Boron 1012 ppm, plant conditions.

Use IC-18 as base IC. CBD at 206 steps. Insert the following per the Simulator Inserts all pre-loads required to support the scenario.

Setup section of the HTML File for this scenano: trgset 1 jpplp4(1 )' trgset 2 jpplsi(1)'

trgset 3 jpplaso(l

)' IMF CRF12A (0 0) TRUE lOR X071038L 0 IMF CRF02A (0 0) TRUE IMF INH40 (0 0) TRUE IMF RCS02B (1 60) 1500 0 0 IMF SIS05A (2 0) TRUE IMF CHS19A (4 0) TRUE IMF XN03022 ( 4 0) 1 IMF EPS19 (0 0) 1 IMF CND12C (50) IMF CND09 (5 120) 4 600 trgset 6 'FNISPR(1)

<= 76' IMF BST-CFW008 (6 0) 0 BVPS -1L14 NRC 4, Rev 2 Set trigger 1 = reactor trip Set trigger 2 = safety injection actuation Set trigger 3 = turbine trip Automatic reactor trip failure Inhibit BB-B Rx trip switch Auto Rod insertion failure 1CH-P-1B auto start inhibit Loop 1B cold leg LOCA 1 min. after reactor trip 1CH-P-1A trips upon SI 1CH-P-2A trips Annunciator A3-22 (pump thermal overload)

Exciter Circuit Breaker auto open inhibit 1CT-P-1C trip Vacuum break leak Set trigger 6 =Reactor power <76% Spurious Turbine trip on Low Vacuum 4 of24 BEAVER VALLE'. )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Assign shift positions SRO: ________ _ ATC: ________ _ BOP: ________ _ Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless it needs operators.

to be run momentarily for an alignment change. When the shift turnover is completed, place the simulator to RUN and commence the scenario.

BVPS-1L14 NRC 4, Rev 2 Simulator running. 5 of24 Crew assumes control of the Unit.

BEAVER VALLE :)WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENT 1: 2A Boric Acid Transfer Pump Trip. trg! 4 (commands preloaded)

ROLE PLAYS: If crew dispatches operators to locally investigate, wait 5 minutes then report back as appropriate; MCC-E11 -Thermal overload is tripped, if asked to attempt reset, report that reset is unsuccessful.

P AB-1 CH-P-2A-pump is shutdown, nothing obvious wrong with it. NOTE: 1CH-P-2A trips A3-22, Boric Acid Transfer Pump Thermal OVLD If SRO did not identify applicable TS SRO references Tech Specs. prior to next event being entered, ask as a follow up question.

Proceed to next event after crew dispatches a field operator to place 1CH-P-2B in service or at LE discretion.

BVPS -1L14 NRC 4, Rev 2 6 of24 ATC announces unexpected BA transfer pump thermal overload alarm. BOP reviews ARP for A3-22 (10M-7.4.AAA).

BOP verifies Boric Acid Transfer pump, 1CH-P-2A is tripped via Red light not being lit. SRO directs BOP to place the "B" Boric Acid Transfer pump in service lAW 10M-7.4.R.

LR 3 .1.2, Boration Flow Paths-Operating, Cond. A. LR 3.1.6, Boric Acid Transfer Pumps-Operating, Cond. A. Both require restoration within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

BEAVER VALLE' JWER STATION Clt-.JSTRUCTIONAL GUIDELINES I PLANTSTATUS I PROCEDURAL GUIDANCE f-----EXPECTED STUDENT-RESPONSE I EVENT 1: (continued) 6 minutes after Field Operator requested to perform valve line-up. Insert commands:

IRF CHS064 (0 0) 0 IRF CHS068 (0 0) 100 IRF CHS070 (0 0) 100 IRF CHS067 (0 0) 0 IRF CHS069 (0 0) 0 ROLEPLAY:

Then report back that all actions for lining up 2B BA Transfer pump have been completed.

1CH-78, 79, 104 are CLOSED, and 1CH-77, 80, 106 are OPEN. BVPS -1L14 NRC 4, Rev 2 7 of24 BOP refers to 10M-7.4.R, 'Transfer Oflnservice Boric Acid Tank', Part A. BOP places both BA Transfer pump CS's to stop. BOPdirectsfieldoperatortoclose 1CH-78, 79,104, and open 1CH-77, 80, 106. BOP places BA Transfer pump to SLOW. Iftime permits BOP may verify BA flow lAW 10M-7.4.P.

BEAVER VALLE' )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUfiSANCE I EXPECTED STUDENT RESPONSE I EVENT2: Containment Pressure Ch 2 transmitter (PT-1LM-100B) fails high IMF XMT -CNM004A (0 0) 55 60 NOTE: If SRO did not identify applicable TS prior to next event being entered, ask as a follow up question.

Proceed to next event at LE discretion.

EVENT 3: Cooling Tower Pump, 1CT-P-1C trips trg! 5 (commands pre loaded) BVPS-1L14 NRC 4, Rev 2 Containment Pressure Ch 2 transmitter PT-1LM-100B fails high. A1-58, Containment Press High (1/3) A1-60, Containment Press Intermediate High (1/3) A1-66, Containment Press High-High (1/4) SRO enters 10M-1.4.IF, Att. 1, Instrument Failure procedure for failed Ch 2 Cnmt Pressure.

SRO references Tech Specs. 1CT-P-1C trips. A6-83, Cooling Tower Pump Auto Stop A7-3, Condenser Vacuum Low-Low A7-4, Condenser Vacuum Low SRO enters AOP 1.26.2 for Loss Of Condenser Vacuum. 8 of24 A TC announces multiple unexpected containment pressure related alarms. ATC reports PT-1LM-100B failed high. BOP reviews ARPs and reports entry into IF procedure is required.

Tech Specs 3.3.2, Condition A requires actions from Table 3.3.2-1, Functions 1.c, & 4.c, Condition D -Place channel in TRIP within 72 hrs or Shutdown.

Functions 2.a.3, 2.b.2, & 3.b.3, ConditionE-Place channel in BYPASS within 72 hrs or Shutdown.

SRO notifies I&C to investigate and trip/bypass bistables within 72 hrs. BOP announces multiple unexpected condenser vacuum related alarms. BOP reports 1CT-P-1C indicates tripped. BOP reports degrading condenser vacuum.

BEAVER VALLE DWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE _u ___ ] EVENT 3: (continued)

NOTE: SRO may initially direct a 2%/min power reduction and then raise it to 5%/min after observing the plant response.

BVPS -1L14 NRC 4, Rev 2 Insufficient cooling tower pumps are operating with condenser hotwell temperature rising. SRO enters AOP 1.51.1, Unplanned Power Reduction.

9 of24 ATC sounds standby alarm. ATC verifies Rx power > P9. BOP verifies condenser backpressure

<8 IN HG-ABS. BOP checks aux steam pressure -normal. BOP checks for adequate # of cooling tower pumps. BOP reports hotwell temperature is rising. SRO directs ATC and BOP to reduce power with boration and turbine load reduction lAW AOP 1.51.1. ATC places all PRZR heaters to ON. ATC initiates boration lAW Attachment 2; (5% per minute power reduction).

Opens MOV -1 CH-350

Places BA Transfer Pump 2B in FAST

Checks Boration flow is > 30 gpm

Continues to emergency borate per reactivity plan BOP initiates turbine load reduction;

Depress 1st STG IN pushbutton

Set EHC SETTER to desired load

Set LOAD RATE thumbwheel to 2% or 5%

Depress GO

Maintain power factor within limits ATC verifies rod control in AUTO.

BEAVER VALLE'. )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT4: Auto Rod Insertion failure IMF CRF02A (0 0) TRUE (command preloaded)

Event 5 will automatically initiate when the Rx power is <76% (approx. 5% power reduction).

EVENTS: Turbine trip due to Low-Low Condenser Vacuum. IMF BST -CFW008 (6 0) *0 (command pre loaded) BVPS -1L14 NRC 4, Rev 2 Rods will fail to automatically insert during turbine load reduction.

A5-39, Reactor Trip due to Turbine Trip & P9. Turbine trip >P9. Rx fails to auto trip. ATC notes that Tavg is not being maintained within +/-5°F ofTrefwith control rods in AUTO. ATC reports auto rod insertion failure. SRO directs ATC to take manual rod control. ATC places rod control in MANUAL to maintain Tavg within+/-5°F ofTref. Crew recognizes Turbine trip> P9, and the Reactor failed to auto trip. SRO directs the crew to trip the reactor, perform ATC attempts to trip the Rx from BB-B. E-0 lOA's and report when ready to read. 10 of24 BEAVER VALLE JWER STATION [--INSTRUCTiONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9 (all commands preloaded)

Auto Rx Trip failure. Exciter Circuit brk fails to auto open. 1500 gpm SBLOCA. "A" Charging pump ICH-P-IA trips. "B" Charging pump ICH-P-IB fails to auto start on Safety Injection.

Critical Task CT -1 <E-O.A): Crew manually trips the reactor from the Control Room before performing the mitigation strategy of FR-S.l. SAFETY SIGNIFICANCE

--Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions.

EVENT7 Exciter circuit breaker fails to auto open on Rx trip. IMF EPS19 (0 0) 1 (command pre loaded) BVPS -1L14 NRC 4, Rev 2 SRO enters E-0. 11 of24 ATC manually trips the reactor from BB-A. A TC verifies Rx trip;

Rx trip and bypass breakers OPEN

Power range indication

-< 5%

Neutron flux -DROPPING BOP verifies Turbine trip;

Throttle OR Governor valves ALL closed

Main Generator output brks -open

Exciter Circuit breaker -open BOP reports that the exciter circuit breaker failed to open, manual opening was successful.

BEAVER VALLE'. )WER STATION [-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9 (continued)

EVENTS 1500 gpm LOCA 1 min. after Rx trip. IMF RCS02B (1 60) 1500 0 0 (command preloaded)

NOTE: Based on scenario timing, Crew may elect to manually actuate Sl. Crew may initially transition to ES-0.1 until conditions degrade to require a Sl. ES-0.1 actions not scripted.

BVPS -1L14 NRC 4, Rev 2 AE and DF Busses are energized from offsite. 12 of24 BOP verifies Power to AC Emergency Busses

Using VB-C voltmeters, verifies AE and DF busses have voltage indicated.

BOP identifies that both emergency busses are energized from offsite power. Check SI Status;

A TC checks if SI is actuated

A TC verifies Cnmt press < 5psig

ATC verfies PRZR press is> 1850 psig.

ATC or BOP verifies Steamline pressure>

500 ps1g ATC manually actuates SI by depressing both Train "A" and Train "B" pushbuttons.

ATC/BOP alerts plant personnel.

Check if SI flow should be reduced;

Verifies CNMT is NOT consistent with pre-event

Verifies RCS subcooling

> 46°F

Verifies Secondary Heat sink exists

Verifies RCS pressure is NOT stable or rising

Verifies PRZR level is < 1 7% Determines SI is required and continues with step 7. BOP verifies 1VS-F-4A running.

BEAVER VALLE 8WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE -] EVENTS 6, 7, 8 & 9 (continued)

ROLE PLAY: After the crew has opened the control room operated valves and dispatched a field operator; INSERT BAT 10M464G.BAT Command will start the "A" Hydrogen analyzer in 9 minutes and the "B" in 15 minutes. After "B" is started report back to the CR that the WR Hydrogen analyzers have been placed in service. BVPS -1L14 NRC 4, Rev 2 13 of24 Crew dispatches an operator to perform 1 OM-46.4.G to place hydrogen analyzers in service.

BEAVER VALLE\ )WER STATION I INSTRUCTIONAL -GUIDELINES

=r-PLANTSTATUS

/PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT9 "A" Charging pump trip with "B" auto start failure. IMF SISOSA (2 0) TRUE IMF INH40 (0 0) TRUE (commands pre loaded) Critical Task: CT -6 (E-0.1) Crew establishes flow from at least one high head ECCS pump before transition out ofE-0. SAFETY SIGNIFICANCE

--Failure to manually start at least one high-head ECCS pump under the postulated conditions constitutes "misoperation or incorrect crew performance which leads to degraded ECCS capacity." NOTE: A TC may have previously started the "B" charging pump during the IOAs. ROLEPLAY:

If requested to place the "C" charging pump in service lAW 10M-7.4.W, wait until the crew progresses past the ES-1.1 transition point, enter commands per HTML and report that the "C" charging pump is ready for service on the 1AE bus. BVPS-1L14 NRC 4, Rev 2 14 of24 ATC verifies SI system status;

Charging pumps running

LHSI pumps running

BIT Flow indicated A TC identifies and reports that there is no charging pumps running and starts the "B" charging pump.

BEAVER VALLE) )WER STATION I INSTRUCTIONAL GUIDELINES

-, PLANT STATUS I PROCE-DURAL-GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9 (continued)

NOTE: Evaluation of BOP performing Attachment 1-K begins on page 23. NOTE: RCPs may have been previously tripped per LHP requirements.

BVPS-1L14 NRC 4, Rev 2 List of Attachment 1-K Discrepancies:

1CH-P-1A Charging pump tripped. 1CH-P-1B Charging pump failed to Auto start. 1FW-P-3B is OOS. RCS temperature<

547°F and dropping due to Safety Injection flow. 15 of24 BOP verifies AFW status;

Motor-driven AFW Pumps-ONE RUNNING

Turbine-driven pump TV-1MS-105A, B open A 7-7 is NOT LIT, turbine driven pump running

AFW Throttle Vlvs all FULL OPEN

Total AFW Flow-> 370 GPM SRO directs BOP to perform Attachment 1-K. ATC checks RCS temp. stable at or trending to 54 7°F;

A TC verifies no steam release is occurring

A TC verifies Reheat steam is isolated

A TC reduces total feedflow to minimize C/D ATC checks Recirc Spray Pumps-NONE RUNNING ATC verifies PRZR isolated;

PORVs-CLOSED

Spray Valves -CLOSED

Safety relief valves -CLOSED

PRT conditions-CONSISTENT WITH EXPECTED VALUES

Power to at least one block valve -AVAILABLE (all available)

Block valves-AT LEAST ONE OPEN (all)

BEAVER VALLE'. JWER STATION [-INSTRUCTIONALGUIDELINES I-PLANT STATUS I PROCEDURALGUIDANCE I EXPECTED STUDENT-RESPONSE I EVENTS 6, 7, 8 & 9 (continued)

BVPS -1Ll4 NRC 4, Rev 2 16 of24 ATC checks if RCPs should be stopped;

DIP between RCS pressure and highest SG pressure-<

200 PSID (350 PSID ADVERSE CNMT)

Criteria for stopping is met-trips all RCPs if not previously tripped ATCIBOP checks if any SGs are faulted;

Pressures in all SGs-ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY SG COMPLETELY DEPRESSURIZED Crew determines NO SG's are faulted. Crew checks if SG tubes are intact;

Check all SG levels-NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation-CONSISTENT WITH PRE-EVENT VALUES Crew determines no SG levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all SG tubes are intact.

BEAVER VALLE :)WER STATION I INSTRUCTIONAL GUIDELINES PLANT STATOS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9 (continued)

BVPS-1L14 NRC 4, Rev 2 Hi-Hi Radiation alarm is in due to containment Crew checks ifRCS is intact by checking cnmt radiation levels. conditions consistent with pre-event values; Incore room, RM-204 and containment, RM-215A and 215B in Hi-Hi alarm. Containment Pressure is rising. Containment Sump level is rising. SRO transitions to E-1. RCPs previously shutdown.

17 of24

Cnmt radiation

Cnmt pressure

Cnmt sump level Crew determines the RCS is not intact based on cnmt conditions.

ATC checks if CREVS should be actuated.

Checks EITHER of the following;

Control Room Radiation Monitor RM-1RM-218A,B-NOT IN HIGH ALARM

CIB -HAS NOT OCCURRED Crew determines CREVS actuation NOT required.

A TC checks if RCPs should be stopped ATC reports RCPs previously shutdown.

ATC checks Recirc Spray Pumps-NONE RUNNING ATCIBOP checks if any SGs are faulted;

Pressures in all SGs-ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY SG COMPLETELY DEPRESSURIZED Crew determines NO SG's are faulted.

BEAVER VALLE', )WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE --] EVENTS 6, 7, 8 & 9 (continued)

NOTE: The spare charging pump can now be SI reduction criteria are not met. placed in service at this point, if the crew previously dispatched an operator.

Insert commands per HTML and report that the "C" charging pump is now available.

BVPS -1L14 NRC 4, Rev 2 18 of24 BOP checks intact SG levels;

Narrow range levels > 31% (50% Adverse) BOP controls feed flow to maintain narrow range level between 31% (50% adverse) and 65%. BOP checks station instr air hdr press > 100 PSIG. Crew checks if SG tubes are intact;

Check all SG levels-NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation-CONSISTENT WITH PRE-EVENT VALUES Crew determines no SG levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all SG tubes are intact. ATC checks PORV's and block valves;

Power to block valves -AVAILABLE

PORVs-CLOSED

Block valves-AT LEAST ONE OPEN Crew checks if SI flow should be reduced. ATC verifies RCS subcooling is NOT> 46°F (54°F Adverse) based on CETC's. Crew determines that current plant conditions for subcooling, does NOT support SI reduction.

BEAVER VALLE OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE -] EVENTS 6, 7, 8 & 9 (continued)

NOTE: Dependant on procedure progression and timing, RCS pressure may still be dropping at this point, if so, the crew would leave the LHSI pumps in service. This is a continuous action step -therefore the crew will return to this step and secure the LHSI pumps when RCS pressure stabilizes.

BVPS-1L14 NRC 4, Rev 2 19 of24 Check if CNMT spray should be stopped. ATC verifies no Quench or Recirc Spray pumps are running. ATC resets SI, CIA and CIB. ATC checks if LHSI pumps should be stopped;

LHSI pumps are running with RWST suction

RCS pressure is > 275 PSIG ( 400 PSIG ADVERSE CNMT)

Check RCS pressure-STABLE ATC stops LHSI pumps AND places CS's in AUTO. Check RCS and SG pressures.

BOP checks pressure in all SG's NOT stable or rising. A TC checks RCS pressure is dropping.

SRO determines SG pressure dropping is NOT due to a faulted SG and continues with procedure based upon preceding note. BOP verifies AC Emergency busses are energized by offsite power. SRO directs BOP to stop unloaded EDG's lAW Attachment 2-AD as time permits.

BEAVER VALLE\ )WER STATION INSTRUCTIONAL GUIDELINES--]

PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9 (continued)

TSC is not staffed at this point. BVPS-1L14 NRC 4, Rev 2 20 of24 BOP performs Attachment 1-F to verify power available to at least 1 train of Cold Leg Recirculation equipment.

BOP reports Attachment 1-F completed SAT with no discrepancies.

Crew evaluates radiation monitors, determines Auxiliary building and Safeguards radiation is consistent with pre-event values. SRO determines TSC is not activated.

SRO directs ATC to monitor nuclear instrumentation to ensure adequate shutdown margin. SRO directs Chemistry and RP to obtain samples. Start additional plant equipment to assist in recovery.

SRO directs a field operator to perform Attachment 2-A for securing the turbine plant. Check if RCS cool down and depressurization is required.

ATC checks RCS pressure>

275 psig (400 PSIG ADVERSE CNMT). SRO determines plant conditions support transition to ES-1.2.

BEAVER VALLE' JWER STATION ,-. INSTRUCTIONAl STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9 (continued)

NOTE: LHSI pumps may have previously been secured due to continuous action step in E-1. NOTE: LHSI pumps may have previously secured due to continuous action step in E-1. BVPS-1L14 NRC 4, Rev 2 SRO transitions to ES-1.2 21 of24 ATC resets SI, CIA and CIB. (all signals were previously reset in E-1 ). ATC checks LHSI pumps -no signs of cavitation.

ATC reports LHSI pumps previously stopped. ATC checks CNMT pressure < 8 psig. SRO directs makeup to the RWST IA W 1 OM-7 .4.Q BOP verifies 4160V and 480V stub busses energized;

ACB-1E5 and ACB-1F5 closed

BA transfer pumps or CNMT vacuum pump indicating lights BOP verifies CNMT Instrument air is available;

Station Instrument Air > 1 00 psig

TV -1 IA-400 open

Cnmt Instrument Air header> 85 psig BOP verifies all AC busses energized by offsite pwr. ATC places all PRZR heaters in PTL. ATC checks if LHSI pumps should be stopped;

LHSI pumps are running with RWST suction

RCS pressure is> 275 PSIG ( 400 PSIG ADVERSE CNMT)

Check RCS pressure -STABLE ATC stops LHSI pumps AND places CS's in AUTO.

BEAVER VALLE' JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, 8 & 9 (continued)

Terminate scenario when the crew establishes RCS cooldown in ES-1.2 and demonstrates the intent to limit C/D rate to< 100 °F/Hr. Classify Event: ALERT per F Al-Potential Loss of the RCS due to RCS leak rate exceeding the capacity of 1 charging pump. OR ALERT per SA3 due to Automatic Reactor trip failure. BVPS-1L14 NRC 4, Rev 2 TSC is not staffed at this point. BOP checks intact SG levels;

NR level > 31% (50% adverse)

Control SG NR levels between 31% (50% ADVERSE) and 65% BOP checks station instrument air header> 100 psig. SRO determines TSC is not activated.

SRO directs A TC to monitor nuclear instrumentation to ensure adequate Shutdown Margin. Initiate RCS cooldown to cold shutdown:

Maintain C/D rate < 100 op /Hr

Block low press SI when RCS is < 1950 psig

Check NO MSIV s are open

Dump steam to the atmosphere using the SG Atm dump valves OR residual heat release valve. EVALUATOR NOTE: SRO performs follow-up classification ofthe E-Plan Use Administrative JPM, SRO A.4 to document event, completes an Initial Notification form and SRO's declaration.

declares an ALERT. 22 of24 BEAVER VALLE' .)WER STATION L -fNSTR0Cfi6NA[

GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of Automatic Actions' BVPS-1L14 NRC 4, Rev 2 Both EDG's are running. Ensure Reheat Steam Isolation.

23 of24 BOP performs the verifications/actions of Attachment 1-K 'Verification of Automatic Actions' as follows: Diesel generators-BOTH RUNNING with no Trouble Alarms, R W pumps running supplying cooling water flow .. Verifies power to both Emergency 4KV AC busses. Station instrument air header pressure>

100 PSIG. Ensure Reheat Steam Isolation;

Verify MOV-1MS-100A,B-CLOSED

Reset reheater controller

Close MOV-1MS-204, gland stm spillover vlv Verify CCR Pumps-ONE RUNNING with recirc pressure > 1 00 psig. Align Neutron Flux Monitoring For Shutdown;

When operable IR channels <1E-10 amp, check SR channels energized

Transfer NR-1NI-45 recorder to operable source and intermediate range displays Verify River Water System In Service;

RPRW Pumps-TWO RUNNING

Check CCR Heat EX RW pressure -> 20 psig. OR (IF CIB has occurred)

Verify RPR W flow to recirc spray hxs BEAVER VALLE' JWER STATION I INSTRUCTIONAL GUIDELINES I PlANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE --] Attachment 1-K 'Verification of Automatic Actions' (continued)

BVPS-1L14 NRC 4, Rev 2 "A" charging/HHSI pump tripped "B" charging/HHSI pump failed to Auto start Check If Main Steamline isolation required;

CNMT pressure -> 7 PSIG -OR-* Steamline pressure -< 500 PSIG -OR-* Steamline pressure high rate of change -ANY ANNUNCIATOR LIT (A7-41, A7-49, A7-57) Determines steamline isolation is NOT required.

Check CIB And CNMT Spray Status;

Containment press-REMAINED<

11 PSIG Verify ESF Equipment Status;

Verify SI status by checking all RED SIS marks-LIT

Verify CIA by checking all ORANGE CIA marks-LIT

Verify FWI by checking all GREEN FWI marks-LIT When SR's are energized, verify Audible indication

Verify operating SR Ch selected on Audio Count Rate Channel Selector Switch.

Audible indication functioning properly

Adjust Multiplier Sw & Volume as necessary Discrepancies:

Upon completion, reports any discrepancies to SRO. * "A" Charging pump tripped * "B" Charging pump failed to Auto start * "B" MDAFW pump is OOS 24 of24

ML14246A240: Difference between revisions

Revision as of 12:13, 9 July 2018

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