Text

Draft Operating Test (Section a, Section B, Section C) (Folder 2)
	ML18102A982
Person / Time
Site:	Beaver Valley
Issue date:	08/28/2017
From:	; FirstEnergy Nuclear Operating Co
To:	D'Antonio J; Operations Branch I
Shared Package
ML17068A096	List: IR 05000412/2017301; ML17072A012; ML17305A086; ML17305A153; ML18019B173; ML18101B304; ML18102A106; ML18102A158; ML18102A224; ML18102A269; ML18102A573; ML18102A982;
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BVPS-TR-0026 Page 1 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-Oxx JPM TITLE: Review a Clearance Tagout for 2FWE-P23A, 'A' Motor JPM REVISION: 0 Driven Aux Feedwater Pump KIA

REFERENCE:

2.2.13 4.1 / 4.3 TASK ID: 0481-007-03-043 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING

~ SRO ONLY 0 ALTERNATE PATH JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[8J Perform D Plant Site D Annual Requa! Exam D BVT D Simulate D Simulator D Initial Exam D NRC

~ Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP#:

Time 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:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Correctly identify the incorrect tagged components, required positions, and clearance sequence for 2FWE-P23A Auxiliary Feedwater Pump.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS:

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

2FWE-P23A Auxiliary Feedwater Pump is to be placed on clearance for pump repacking.

INITIATING CUE: You are to verify/review the required clearance points (equipment),

position (placement configuration), and sequence for clearing 2FWE-P23A, Auxiliary Feedwater Pump for work specified as shown on the clearance coversheet using the references provided.

ESOMS is out of service.

Document your results on the table provided.

REFERENCES:

NOBP-OP-1001, "Manual Clearance Generation", Rev. 4 NOP-OP-1001, "Clearance/Tagging Program", Rev. 24 OP Manual Fig. No. 24-3, 8700-RM-424-003, Rev. 19 20M-24, Steam Generator Feedwater System Operating Manual TOOLS: None HANDOUT: NOBP-OP-1001, "Manual Clearance Generation", Rev. 4 NOP-OP-1001, "Clearance/Tagging Program", Rev. 24 OP Manual Fig. No. 24-3, 8700-RM-424-003, Rev. 19 20M-24, Steam Generator Feedwater System Operating Manual Clearance coversheet 2R00-24-FW-001

BVPS-TR-0026 Page 4 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-Oxx JPM TITLE: Review a Clearance Tagout for 2FWE-P23A, 'A' Motor JPM REVISION: 0 Driven Aux Feedwater Pump STEP STANDARD

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

START TIME: _ _ _ _ _ __

l.C Candidate notices that the 1.1 Recognizes that the turning off the power supplies, steps were not performed in placing the pump switch in PTL, and racking out the the correct order. breaker should be performed first.

COMMENTS:

2.C Candidate notices that the 2.1 C Candidate adds 2FWE-1169 in the required position casing vent valve (2FWE- as OPEN on the tagout sheet.

1169) was not identified in the tagout. COMMENTS:

3.C Candidate notices that the 3.1 C Candidate adds 2FWE-1171 in the required position casing vent valve (2FWE- as OPEN on the tagout sheet.

11 71) was marked in the incorrect position. Correct COMMENTS:

position should be SHUT.

BVPS-TR-002 6 Page 4 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-Oxx JPM TITLE: Review a Clearance Tagout for 2FWE-P23A, 'A' Motor JPM REVISION: 0 Driven Aux Feedwater Pump STEP STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U 4.C Recognizes that there was a 4.1 C Candidate changes the power supplies to transcription error for 4KVS- 4KVS-2AE-2E 18, 4160 Volt Breaker for 2AE-4/2E l 8 and 4KVS- 2FWE-P23A.

2AE-2El 8 were written as 4KVS-2AE-4/2E16 and 4.2C Candidate changes the power supply to 4KVS-2AE-2E16, 4KVS- 2E-4/2El 8, 125 VDC Breaker Control for respectively, but were 4KVS-2AE-2El8.

written in the correct position. COMMENTS:

5. C Recognizes that these 5 .1 C components are in the correct

2FWE-P23A-CS PTL position.

2FWE-3 7 SHUT

2FWE-52 SHUT

2FWE-91 SHUT

2FWE-94 SHUT COMMENTS:

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

Grader discretion will be required.

STOP TIME: - - - - - - -

ANSWER KEY ---DO NOT GIVE TO STUDENT---

Component ID Component Description Position Sequence 2FWE-P23A-CS BB C/S Steam Generator Aux FW Pump Pull-To-Lock 1 (PTL)

C*l) 4KVS-2AE- 125 voe Breaker Control for 4KVS-2AE- OFF 2 4/2E18 2E18 4KVS-2AE-2E18 4160 Volt Breaker for 2FWE-P23A Racked Out 3 2FWE-37 (2FWE*P23A) 'A' Header Disch Isolation Shut 4 2FWE-52 (2FWE*P23A) Recirc Isolation Shut 4 2FWE-91 (2FWE*P23A) Supply from Service Shut 5 (**2)

Water 2FWE-94 (2FWE*P23A) Supply from Primary Shut 5 (**2)

DWST 2FWE-1171 (2FWE*P23A) Casing Drain Open 6 (**2) 2FWE-1169 (2FWE*P23A) Casing Vent Open 6 (**2)

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. The student will correct it and it will look similar to this.

C* 1). DC Control PWR is optional and not required.

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

BVPS-TR-0026 Page 1 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 3AD-024 JPM TITLE: Evaluate Operators Work History to Determine if License Status JPM REVISION: 1 is Active (SRO)

KIA

REFERENCE:

2.1.4 3.8 TASK ID: 0481-024-03-013 JPM APPLICATION: !ZI REQUALIFICATION IZI INITIAL EXAM D TRAINING IZI SRO ONLY 0 ALTERNATE PATH JPM !ZI ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[3J Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC

[3J Classroom D Training D Other:

' D Other:

EVALUATION RES UL TS Performer Name: Performer SAP:

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 Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determines SRO I and SRO 3 are Inactive. Determines SRO 2 and SRO 4 are Active.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS: Today is 11/7/17. Four Senior Reactor Operators have the following work history for the third quarter of 2017 (Plant was in Mode I the entire quarter):

SRO 1 Entered third quarter with active 1icense 7/01/17 Worked 0700-1500 as Command SRO 7/02/17 Worked 0700-1500 as Command SRO 7/03/17 Worked 0700-1500 as Command SRO 7/07/17 Worked 0700-1500 as Command SRO. Was relieved for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to obtain required biennial License Physical at the Health Center 7/08/17 Worked 0700-1500 as Command SRO 7/17/17 Worked 0700-1500 as Command SRO 7/16/17 Worked 0700-1500 as Command SRO SR02 Entered third quarter with inactive license Completed all requirements for license reactivation 9/15/17 through 9/20/17 9/23/17 Worked 0700-1500 as Command SRO 9/24/17 Worked 0700-1500 as Comrnand SRO 9/28/17 Worked 0700-1500 as Shift Technical Advisor SR03 Entered third quarter with active license 7/10/17 Worked 0700-1500 as Shift Manager 7/11/17 Worked 0700-1500 as Shift Manager 7/18/17 Worked 0700-1500 as Shift Manager 7/19/17 Worked 0700-1500 as Shift Technical Advisor 7/20/17 Worked 0700-1500 as Shift Manager 8/01/17 Worked 0700-1500 as Shift Manager 8/02/17 Worked 0700-1500 as Shift Manager SR04 Entered third quarter with active license 8/01/17 Worked 0700-1900 as Command SRO 8/02/17 Worked 0700-1900 as Command SRO 8/03/17 Worked 0700-1500 as Command SRO 8/09/17 Worked 0700-1900 as Command SRO 8/10/17 Worked 0700-1500 as Command SRO 8/25/17 Worked 0700-1900 as Command SRO 8/26/17 Worked 0700-1500 as Command SRO INITIATING CUE: Based on the previous quarters work history determine the license status as of today, 11/7/17, for each Senior Reactor Operator and document as ACTIVE or INACTIVE on this form, include the basis for your determination.

BVPS-TR-0026 Page 3 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE

REFERENCES:

NOBP-TR-1271, Operator License Administration, Rev 3 TOOLS: Calculator HANDOUT: NOBP-TR-1271, Operator License Administration, Rev 3

BVPS-TR-0026 Page 4 of 5 Revision 0 OPERATIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 3AD-024 JPM TITLE: Evaluate Operators Work History to Determine if License Status JPM REVISION: 1 is Active (SRO)

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT):::::. S/U EVALUATOR NOTE: Provide a copy ofNOBP-TR-1271.

START TIME: - - - - - - - -

1. Reviews NOBP-TR-1271 for 1.1 Reviews NOBP-TR-1271 Section 4.5, Shift Maintaining an Active License. requirements for Active license maintenance.

COMMENTS:

2.C Evaluates SRO I work history. 2.1.C Determines requirement for working seven 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shifts is NOT credited towards active license. The time for the License Physical is not credited toward the watch.

COMMENTS:

3.C Evaluates SRO 2 work history. 3.1.C Determines requirement for maintaining an active license is met by reactivating the license in the quarter.

COMMENTS:

BVPS-TR-0026 Page 5 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 3AD-024 JPM TITLE: Evaluate Operators Work History to Determine if License Status JPM REVISION: 1 is Active (SRO)

STEP STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT :=> SIU 4.C Evaluates SRO 3 work history. 4.1.C Determines requirement for working seven 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shifts is NOT credited towards active license. The STA position is not credited for maintaining an active license, even though STAs may hold a license.

COMMENTS:

5.C Evaluates SRO 4 work history. 5.1.C Determines requirement for maintaining an active license is met by working the required seven shifts in a licensed position, Shift Manager or Command SRO.

COMMENTS:

6. Reports SROs I and 3 are NOT 6.1 Determines that the SRO 1 and 3 Licenses are NOT active SROs 2 and 4 ARE active. active due to not working seven 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shifts or five 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts in the previous quarter, SRO 2 and 4 are active.

EVALUATOR CUE: When the applicant makes a decision regarding Active or Inactive License, the evaluation for this JPM is complete.

COMMENTS:

STOP TIME:

BVPS-TR-0026 Page 1 of 8 Revision O OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Reviewing a Shutdown Margin Calculation Following a 001 MS Dropped Rod then Stuck Rod JPM REVISION: 0 KIA

REFERENCE:

2.1.25 3.9/4.2 TASK ID: 0011-006-06-013 JPM APPLICATION: rg] REQUALIFICATION rg] INITIAL EXAM D TRAINING D SROONLY 0 ALTERNATE PATH JPM rg] ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

!Zl Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC

!Zl Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

Time D Yes Allotted 20 Minutes Actual minutes Critical: [2J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SAP: Name/SAP:

Name/SAP: Name/SAP:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Identifies and corrects errors in SOM calculation and boration requirements for one dropped rod, then two other rods stuck full out.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS:

All rods are at 228 steps on group demand counters.

A single Bank "D" Control Rod has dropped and indicates O steps.

The plant is at 100% power.

Tavg is within 1 F of Tref.

Current RCS boron concentration is 600 PPM from a sample at 1115.

Core Burn-up is 16500 MWD/MTU.

The date is [today] at 1300 INITIATING CUE: Part 1:

Your supervisor has directed you to review a Shutdown Margin calculation that was calculated for the present plant conditions using 20ST-49.1, "Shutdown Margin Calculation (Plant Critical)", and recorded in the COMMENT section of the OST cover sheet.

Part 2:

After reviewing the Shutdown Margin calculation using 20ST-49. l, the unit reduced power to 90% and two stuck rods was discovered by the ATC. Review the new shutdown margin calculation that was performed in accordance with 20ST-49 .1, "Shutdown Margin Calculation (Plant Critical)"

REFERENCES:

20ST-49 .1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 20), Rev. 22 Unit 2 Plant Curve Book (Updated for Cycle 20)

Unit2 LRM TOOLS: Calculator Ruler/straight edge HANDOUT: 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 20), Rev. 22 place kept up to step VII.A.

Unit 2 Plant Curve Book (Updated for Cycle 20)

Unit2 LRM Completed SDM calculations IAW 20ST-49.l and 20ST-49.2 Provide Data Sheet 1 for20ST-49.l for both parts.

BVPS-TR-0026 Page 3 of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Reviewing a Shutdown Margin Calculation Following a 001MS Dropped Rod then Stuck Rod and Reactor Trip JPM REVISION: 0 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=>

EVALUATOR NOTE: Provide the Candidate with a copy of the completed 20ST-49.l, Cycle 20 Curve Book, Unit 2 LRM, calculator, and a ruler/straight edge.

START TIME: - - - - - - - -

1. C (Step VII.A. l through Step l .C Determines these steps were performed correctly.

VII.B. l.d)

Step 1 initialed

Power is recorded at 100%

Program Tavg is initialed as within 3F of Tref.

NI A Step VII.A.2

Boron Concentration is 600 ppm

Control Bank D is 228 steps withdrawn

Data Sheet 1 is filled out correctly until B.2

Number of Inoperable Rods is 1

NIA Step VII.A.7

B.l.a ARO Total Bank Worth is 7.813% ~k/k

B.l.b IRW is ZERO (0)

B.l.c TBW-IRW = 7.813% ~k/k

B. l.d = 7.0317% ~k/k

B.4.a = 600 ppm boron

B.4.b = 0.837

B.4.c = 502.2 ppm

B.4.d = 2580 pcm

B.4.e = 2.580% ~k/k

B.4.f = 2.730% ~k/k COMMENTS:

BVPS-TR-0026 Page 4 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Reviewing a Shutdown Margin Calculation Following a 001MS Dropped Rod then Stuck Rod and Reactor Trip JPM REVISION: 0 STEP STANDARD 1

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=:> SIU I 2.C Inoperable (Untrippable) OR 2.lC Determines that the operator interpolated stuck rod Dropped Rods: worth to be 2.742% b.k/k and determines that it If ONE rod is inoperable should be the higher bumup value and puts in 2.774%

(untrippable) OR dropped, b.k/k.

Record "Worst Case Rod with Inoperable Rod" worth EXAMINER NOTE: this is the only error, however on Data Sheet 1. Value is the applicant must use 2.774% b.k/k in his or her determined from Column calculations.

"B" on Attachment 2 for the appropriate Cycle Bumup.

COMMENTS:

(Step VII.B.2.b)

3. Subtract Stuck Rod Worth 3.1 Determines 90% Total Bank Worth minus Stuck from the 90% Total Bank Rod(s) Worth to be 4.2577 %.6.k/k and records on Worth value AND Enter the Data Sheet 1 (Block B.3).

result on Data Sheet 1.

COMMENTS:

(Step VII.B.3) 4.C Determine SHUTDOWN 4.lC Determines SDM to be 1.5277% (+/- 0.100%) b.k/k, MARGIN by subtracting and records on Data Sheet 1 (Block B.4.f) AND Power Defect (Step records on the OST cover sheet.

VII.B.4.f) from the value determined in Step VII.B.3 4.2C Compares calculated SDM to the limits specified in AND Record on Data Sheet the COLR, and determines that it does NOT meet

1. acceptance criteria AND records on the OST cover sheet.

(Step VII.B.5) COMMENTS:

BVPS-TR-0026 Page 5 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Reviewing a Shutdown Margin Calculation Following a 001MS Dropped Rod then Stuck Rod and Reactor Trip JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU PART 2: Two Stuck Rods 5.C Steps VII.A.1 through 5.lC Candidate determines that these steps were performed VII.A.6 were performed correctly.

correctly.

COMMENTS:

6.C If the number of inoperable 6.lC Candidate uses Attachment 1, "Required Boron (untrippable) OR dropped Concentration With Greater Than One Inoperable control Rods is greater than Rod" and determines that the operator used the 1, Use Attachment 1 to required boron concentration associated with 14000 determine the required boron MWD/MTU (1508 ppm boron). The candidate concentration with greater determines the CORRECT required boron than one inoperable rod and concentration to be 1314 ppm.

Record below. (Otherwise EXAMINER NOTE: The procedure is not clear on what do to when NIA) in between burnup values for this table. Need to clarify, applicant may interpolate or pick higher burnup value instead of higher boron (Step VII.A. 7) requirement. Interpolation value: 1266 ppm. Higher Burnup = 1121 ppm is NOT conservative and therefore, not correct. Examiner discretion is required.

COMMENTS:

7.C With the number of inoperable 7.lC Determines that this step is applicable and goes to Step (untrippable) OR dropped VII.C.2.

rods greater than one, the shutdown margin is < 1. 77% COMMENTS:

~k/k. Perform Step VII.C.2 UNTIL the required boron concentration of Attachment 1 is reached.

(Step VII.A.7.a)

BVPS-TR-0026 Page 6 of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Reviewing a Shutdown Margin Calculation Following a 001MS Dropped Rod then Stuck Rod and Reactor Trip JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 8.C If SDM is not within limits 8.1 C Determines that the SDM is NOT within limits specified in the COLR, intiate specified in the COLR and reports that boration is boration and continue UNTIL the required. Boration value= Step VII.A.7 - Step required SDM is restored. VII.A. 3= 1314 ppm - 502 ppm = 812 ppm boron.

(Step VII.C.2) COMMENTS:

EVALUATOR CUE: When the candidate hands in the OST cover sheet, the evaluation for this JPM is complete.

EVALUATOR CUE: Grader discretion may be required.

STOP TIME: - - - - - - - -

BVPS-TR-0026 Page 1 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-015 JPM TITLE: Classify an Event and Determine Protective Action JPM REVISION: 1 Recommendations (SRO Only)

KIA

REFERENCE:

2.4.44 4.4 TASK ID: 1350-011-03-023 2.4.41 4.6 1350-004-03-023 JPM APPLICATION: t8J REQUALIFICATION t8J INITIAL EXAM D TRAINING t8J SRO ONLY 0 ALTERNATE PATH JPM t8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[81 Perform D Plant Site D AnnualRequalExam D BVT D Simulate D Simulator D Initial Exam D NRC

~ Classroom D Training D Other:

D Other:

EVALUATION RES UL TS Performer Name: Performer SAP#:

Time ~ Yes Allotted 15 Minutes Actual minutes Critical: D No Time: Time:

JPM RE SULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK ST AND ARD: Determines the Emergency Classification is a General Emergency and Protective Action Recommendations in accordance with 1/2-EPP-IP-

4. l.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS: The Unit was operating at 100% power for 160 days on-line when the following occurred:

The reactor failed to trip on low Steam Generator water level, attempts to manually trip the reactor have been unsuccessful.

The reactor is currently at 8% power and stable.

Steam Generator narrow range levels are 2% on all SGs.

Total Aux Feedwater flow is 290 gpm.

The following plant conditions exist:

35' wind direction is from 195° at 4 MPH.

150' wind direction is from 52° at 11 MPH.

500' wind direction is from 230° at 15 MPH.

NO radioactive release has occurred or is imminent (within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ).

The Containment Fission Product Barrier EAL is NOT challenged (no Loss or Potential Loss)

There is NO Hostile Action event in progress.

Offsite agencies have NOT identified any impediments to evacuation.

Health Physics has provided the following dose projections:

At the EAB: .025 REM TEDE; .008 REM CDE At 2 miles: .0015 REM TEDE; .004 REM CDE At 5 miles: .009 REM TEDE; .025 REM CDE Unit 1 remains operating at 100% power.

INITIATING CUE: You are the Emergency Director and the TSC/EOF has NOT yet been activated. You are to evaluate the above conditions and determine which, if any, Emergency Classification and offsite Protective Action Recommendations (PAR) are necessary. Complete 1/2-EPP-IP-l .l.FOl Nuclear Power Plant Initial Notification Form. The evaluator will peer check the form.

This JPM is TIME CRITICAL.

REFERENCES:

EPP/I-1 b, Recognition And Classification of Emergency Conditions, Rev. 17 1/2-EPP-IP-4. l, "Offsite Protective Actions", Rev. 31 1/2-EPP-IP-l. l.FOl FENOC INF Rev. 9 1/2-EPP-I-5 General Emergency Rev 44 EPP Flow Chart

BVPS-TR-0026 Page 3 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TOOLS: None HANDOUT: EPP /1-1 b, Recognition And Classification of Emergency Conditions, Rev. 17 1/2-EPP-IP-4.1, "Offsite Protective Actions", Rev. 31 1/2-EPP-IP-1.l.FOl FENOC INF Rev. 9 l/2-EPP-1-2 Unusual Event Rev 46 1/2-EPP-I-3 Alert Rev 43 1/2-EPP- 1-4 Site Area Emergency Rev 43 1/2-EPP-I-5 General Emergency Rev 44 EPP Flow Chart EOP Status Trees

BVPS-TR-0026 Page 4 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-015 JPM TITLE: Classify an Event and Determine Protective Action JPM REVISION: 1 Recommendations (SRO Only)

STEP STANDARD

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

' 'i ,_v *. *.;:'

START TIME:

EV ALU ATOR NOTE: Record the start and stop times for classification and PAR determination once the candidate begins his assessment of the event. The candidate may fill out information on the INF AFTER completing the classification and PAR.

TIME CRITICAL START TIME:

I I l.C Correctly classify the l.lC Candidate classifies the event as a GENERAL emergency event from the EP EMERGENCY based on SG3 as indicated by the Wallboard/ procedure. following conditions:

An Automatic Reactor Trip failed to shutdown the reactor as indicated by reactor power >5%,

AND

all manual trip actions failed to shutdown the reactor as indicated by reactor power >5%

AND

Heat Sink RED entry conditions met.

COMMENTS:

BVPS-TR-0026 Page 5 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-O 15 JPM TITLE: Classify an Event and Determine Protective Action JPM REVISION: 1 Recommendations (SRO Only)

STEP STANDARD

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

classification.

Box 1 Call Status: Places a checkmark in the "A Drill" box.

Box 1 Call Status: Places N erifies the word "Simulator" in the code word space.

C Box 2 Affected Station: Places a checkmark in BV 2 block.

C Box 3 Classification: Places a checkmark in the appropriate classification box (GENERAL EMERGENCY as identified in step 1 of the JPM above).

C Box 4 Declared At: Places current time in the declaration time space, places the date in the date space.

C Box 5 Emergency Action Level: Places the appropriate EAL number in the EAL number space (SG3 as identified in step 1 of the JPM above).

Box 6 Radiological Release Status: Places a checkmark in the box for NO radiological release in progress due to this event box.

Box 7 Places 52° in the 150' Wind Direction and 4 mph in the Wind Speed at 35' spaces.

Box 8 Protective Action Recommendation:

Routes to procedure Vi-EPP-IP-4.1, Offsite Protective Actions.

COMMENTS:

BVPS-TR-0026 Page 6 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-O 15 JPM TITLE: Classify an Event and Determine Protective Action JPM REVISION: 1 Recommendations (SRO Only)

STEP STANDARD

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

3. Locates Offsite Protective 3.1 Refers to 1/2-EPP-IP-4. l, Attachment A, Part 1 Action Recommendation Offsite Protective Action Recommendation Flowchart. Flowchart.

COMMENTS:

4. Determines offsite protective 4.1 Navigates PAR flowchart as follows:

action.

General Emergency declared ( t)

Records Met data that was provided in Initial Conditions (t)

ONE of the following is TRUE (t):

,. 35' wind speed LESS than 2 MPH (or unavailable)?

,. Is either 150' or 500' wind directions unavailable?

,. The difference between the 150' & 500' wind directions is~ 165 and :S 195 degrees?

(opposite wind directions) or unavailable?

(-+) May Route to page 2 at this step.

,. Release transport will span sunrise or sunset hours. No Release is in progress.

,. The TSC I EOP is NOT activated.

Routes to page 2 based upon opposite wind directions.

Containment FPB is NOT a Loss. (-+)

No Hostile Action or No impediment to evacuation. (-+)

Projected Dose at 5 Miles is less than limits. (-+)

COMMENTS:

BVPS-TR-0026 Page 7 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-015 JPM TITLE: Classify an Event and Determine Protective Action JPM REVISION: 1 Recommendations (SRO Only)

STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 5.C Determine Offsite Protective 5.1. Determines and documents on 1/2-EPP-IP-1. 1. FO 1, Action Recommendations. the following PARs:

C Evacuate 0-5 Miles 360 Degrees

All others monitor and prepare

Advise the general public to administer KI per state plan TIME CRITICAL STOP TIME:

I I COMMENTS:

6. Continues assessment. 6.1 Indicates that they would continue monitoring for changes in the meteorological and radiological conditions.

COMMENTS:

BVPS-TR-0026 Page 8 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-015 JPM TITLE: Classify an Event and Determine Protective Action JPM REVISION: 1 Recommendations (SRO Only)

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT ~ S/U 7.C Completes section 8 and 9 of 7.lC Box 8 PAR: Completes recording the PAR on the the Initial Notification Form INF.

for the PAR.

Places a checkmark on the recommended PAR box.

C Places a check.mark in the EVACUATE box.

C Places a check.mark in the 5 Miles - 360° box.

7.2 Box 9 Call Back Number: Places a check.mark in the Control Room number box.

7.3 Print/ Signs the form and requests a Peer Check.

COMMENTS:

8.C Completes the Initial 8.1. Determine that declaration is completed within 15 Declaration and PAR within minutes of the start time.

15 minutes.

8.2 C Confirm the Time Critical start and stop times are within 15 minutes.

COMMENTS:

EVALU ATOR NOTE: Refer to Answer Key for initial notification form critical steps.

EVALUATOR CUE: When the candidate completes the Declaration and Protective Action Recommendation, the evaluation for this JPM is complete.

STOP TIME: - - - - - - - -

FENOC NUCLEAR POWER PLANT BV1LOT17 NRC SRO AD 4 STATE / COUNTY USE ONLY INITIAL NOT/FICA TION FORM DATE: TIME:

Beaver Valley Power Station (BVPS) 1/2-EPP-IP-1.1.F01 Rev. 9 MESSAGE NO:

1. Call Status: [8J This is a DRILL 0 This is an ACTUAL EMERGENCY I CODE WORD: SIMULATOR

2. Affected Station: Beaver Valley Power Station 0 UNIT 1 [gl UNIT 2 0 BOTH Units 1 & 2

3. Classification: 0 UNUSUAL EVENT 0 PAR MODIFIED (Check only 1 box)

D ALERT 0 EVENT TERMINATION 0 SITE AREA EMERGENCY

[8JGENERALEMERGENCY

4. Declared At: Current Time Current Date I TIME: hrs DATE:

-- I

5. EMERGENCY ACTION LEVEL: SG3 (See BVPS EAL Reference for more information)

6. Radiological Release Status:

[8J a. NO radiological release in progress due to the event D b. AIRBORNE radiological release in progress due to the event D c. LIQUID radiological release in progress due to the event

7. Wind DIRECTION at 150' is FROM: 52 degrees Wind SPEED at 35' is: 4 mph

8. Protective Action Recommendation (PAR):

D NO Protective Action Recommendation

[8J The PROTECTIVE ACTION RECOMENDATION from the Utility is:

a. [8J EVACUATE D SHELTER

b. D 2 Miles - 360° AND the following sectors out to D 5 miles D 10 Miles DA DB DC DD DE OF DG DH DJ DK DL OM ON DP Do DR C. [8J 5 Miles - 360° D 10 Miles - 360°

d. D Other:

(PAR beyond 10-miles following discussion with State Agencies, per IP-4.1 section 8.4)

e. AND that potassium iodide (Kl) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to monitor EAS and prepare for further protective actions.

9. Call Back Number: [8J Control Room: 724-643-8000 0 TSC: 724-682-5427 0 Alt TSC: 724-891-1946 For Utility Use Only Approved: Candidates N a m e / ~ '7!4- Peer Check: Requests Peer Check / :£valuator PrinUSign (Emergency Director) PrinUSion

BVPS-TR-0026 Page 1 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-023 JPM REVISION: 3 JPM TITLE: Review/ Approve LW Discharge (SRO ONLY)

KIA

REFERENCE:

2.3.11 4.3 TASK ID: l 300-009-03-023 JPM APPLICATION: IS) REQUALIFICATION IS) INITIAL EXAM O TRAINING 0 SRO ONLY O ALTERNATE PATH JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D AnnualRequalExam D BVT D Simulate D Simulator D Initial Exam D NRC

[gl Classroom D Training D Other:

D Other:

EV ALU ATI ON RESULTS Performer Name: Performer SAP#:

Time D Yes Allotted 20 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RES ULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: RWDA-L-99999T is NOT approved for the following reasons:

Wrong tank volume and Wrong alternate radiation monitor alarm setpoint calculation.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS:

Unit 2 is at 100% power.

RWDA-L-99999T has been prepared for discharging Steam Generator Blowdown Evaporator Test Tank 2SGC-TK23B.

Steam Generator Blowdown Evaporator Test Tank 2SGC-TK23B level is 130 inches.

Procedure 20M-25.4.L, "Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Contents To Cooling Tower Blowdown" has been completed through step IV.A.12.a.

INITIATING CUE: Approve RWDA-L-99999T IAW procedure 20M-25.4.L, "Discharging Steam Generator Blowdown Evaporator Test Tank

[2SGC-TK23A(B)] Contents To Cooling Tower Blowdown", step IV.A.12.b-f.

Document the results of your approval in appropriate steps of 20M-25.4.L AND in the block below. (Located on candidate direction sheet)

REFERENCES:

20M-25.4.L, "Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Contents To Cooling Tower Blowdown", Rev. 34 TOOLS: Calculator.

HANDOUT: RWDA-L-99999T filled out with the following errors:

17,394 gal volume for the tank instead of 17,705 gals.

Wrong alternate radiation monitor alarm setpoint calculation. ( l .88E- 3 instead of l .88E-4) 20M-25.4.L, "Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Contents To Cooling Tower Blowdown", Rev. 34, filled out up to step IV.A.12.b

BVPS-TR-0026 Page 3 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-023 JPM TITLE: Review/ Approve L W Discharge (SRO ONLY)

JPM REVISION: 3 STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U EV ALU ATOR CUE:

Provide marked up copy of 20M-25.4.L and completed Discharge Permit.

START TIME: - - - - - - -

l.C After the RWDA-L is 1.1 C Refers to Tank Curve Book or Table 1 in 20M-approved by Radiation 25.4.L and determines that the tank data is Protection AND Chemistry, INCORRECT. The correct volume for 130 inches have the SM or US review the should be 17,705 gals. NOT 17,394 gals.

R WDA-L to confirm the following: EV ALUTOR NOTE: Candidate may also refer to recirculation time of the tank. The recirculation time is The tank data is correct. more than the minimum required.

COMMENTS:

2. Verify Radiation Protection 2.1 Verifies Rad Pro has signed the appropriate block on has authorized the RWDA-L. the RWDA-L.

COMMENTS:

BVPS-TR-0026 Page 4 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-023 JPM TITLE: Review/ Approve L W Discharge (SRO ONLY)

JPM REVISION: 3 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 3.C All hand calculations are 3.lC Determines that the alternate radiation Alarm setpoint correct. calculation is INCORRECT.

EV ALUTOR NOTE: 4000/85 X 4.0E*6 should equal l .88E*4 NOT l .88E*3 AND this also makes l .88E*4 X 0.70 INCORRECT.

COMMENTS:

4. Verify the effective period for 4.1 Determines RWDA-L is still effective.

the RWDA-L has NOT expired. EV ALUTOR NOTE: IA W P&L I on page 3 the RWDA-L is effective for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time the sample was drawn.

COMMENTS:

BVPS-TR-0026 Page 5 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-023 JPM TITLE: Review/ Approve LW Discharge (SRO ONLY)

JPM REVISION: 3 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT :=) SIU 5.C If the tank is NOT acceptable 5.1 C In the remarks section places the following for discharge, an approval information:

signature is NOT required.

Mark the RWDA-L VOID

Tank volume is incorrect.

Mark the RWDA-L VOID,

Radiation monitor alarm setpoint calculations are state reason, initial, AND incorrect Return the RWDA-L to

Candidate initials Radiation Protection.

(Otherwise NIA this step). EVALUTOR NOTE: Some discretion is required when grading this step of the JPM. It is NOT required to place the exact words listed here for the tank volume and radiation monitor alarm setpoint.

However, it is critical the candidate documents all the errors on the form.

COMMENTS:

TERMINATING CUE: That completes this JPM.

STOP TIME: - - - - - - - -

BVPS-TR-0026 Page 1 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 3AD-023 JPM TITLE: Determine if License Status is Maintained Active (RO)

JPM REVISION: 1 KIA

REFERENCE:

2.1.4 3.3 TASK ID: 0481-024-03-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM O TRAINING D SROONLY 0 ALTERNATE PATH JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[8J Perform D Plant Site D AnnualRequalExam D BVT D Simulate D Simulator D Initial Exam D NRC

[8J Classroom D Training D Other:

D Other:

EVALUATION RES UL TS Performer Name: Performer SAP:

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:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determines active license status is not maintained, and evaluates whether each shift meets the requirements.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS: Today is 11/6/17. You are a Reactor Operator. You are scheduled to stand a Reactor Operator ATC watch tomorrow and need to determine whether or not your license is Active or Inactive based upon the previous quarter work history. The plant has been at power the entire quarter. Your work history is as follows:

7/12/17 Worked 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months as BOP (day shift).

7/13/17 Worked 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months as BOP ( day shift).

7/14/17 Worked 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months as ATC and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ATC doing Crew JIT training on Simulator (day shift).

8/19/17 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as BOP (night shift).

8/25/17 Worked 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months as ATC (night shift).

9/21/17 Worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as BOP (night shift).

9/22/17 Worked 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months as BOP (night shift).

9/23/17 Worked 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months as WEC Clearance RO (night shift).

9/27/17 Worked 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months as the 3rd RO in the Control Room (day shift).

INITIATING CUE: Determine if your license status is active or inactive based on the previous quarters work history and document as ACTIVE or INACTIVE on this form.

Document the basis for your determination for each work history item.

(Provide copies of the references)

REFERENCES:

NOBP-TR-1271, Operator License Administration, Rev 3 I OCFR-55 53 Conditions of Licenses TOOLS: Calculator HANDOUT: NOBP-TR-1271, Operator License Administration, Rev 3

BVPS-TR-0026 Page 3 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 3AD-023 JPM TITLE: Determine if License Status is Maintained Active (RO)

JPM REVISION: 1 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU EVALU ATOR NOTE: Provide the candidate a copy ofNOBP-TR-1271.

START TIME: - - - - - - - -

1. Reviews NOBP-TR-1271 for 1.1 Reviews NOBP-TR-1271 Section 4.5 and reviews the Maintaining an Active License. Shift requirements for Active license maintenance.

COMMENTS:

2. Evaluates 7/12/17 work period 2.1. Determines requirement for working the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . is credited towards active license. This counts as one shift.

COMMENTS:

3.C Evaluates 7/13/17 work period 3. 1. C Determines requirement for working the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . is NOT credited towards active license, since it was not a complete shift turnover to turnover.

COMMENTS:

4.C Evaluates 7/14/17 work period 4.1.C Determines requirement for working the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . is NOT credited towards active license, since the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of JIT Training is not a licensed position function.

COMMENTS:

BVPS-TR-0026 Page 4 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 3AD-023 JPM TITLE: Determine if License Status is Maintained Active (RO)

JPM REVISION: 1 STEP ST AND ARD

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

5. Evaluates 8/19/17 work period 5.1 Determines requirement for working the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . is credited towards active license. This counts as one shift.

COMMENTS:

6. Evaluates 8/25/17 work period 6.1 Determines requirement for working the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . is credited towards active license. This counts as one shift.

COMMENTS:

7. Evaluates 9/21 /17 work period 7.1 Determines requirement for working the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . is credited towards active license. This counts as one shift.

COMMENTS:

8. Evaluates 9/22/17 work period 8.1 Determines requirement for working the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . is credited towards active license. This counts as one shift.

COMMENTS:

BVPS-TR-0026 Page 5 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 3AD-023 JPM TITLE: Determine if License Status is Maintained Active (RO)

JPM REVISION: 1 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 9.C Evaluates 9/23/17 work period 9 .1 C Determines requirement for working the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift is of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . NOT credited towards active license, since this was performed in the Work Execution Center (WEC).

COMMENTS:

10.C Evaluates 9/27/17 work period 10.1 C Determines requirement for working the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shift of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . is NOT credited towards active license since it was not for the ATC or BOP position.

COMMENTS:

11.C Evaluates work history and 11.1 C Determines that the License is INACTIVE due the determines if the license is NOT requirements to work five 12-hour shifts, seven 8-hour Active. shifts, or a combination of 8 & 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts totaling >56 hours in the quarter not being met.

COMMENTS:

EV ALU ATOR CUE: When the applicant makes a recommendation regarding Active or Inactive License, state that "The evaluation for this JPM is complete".

STOP TIME:

BVPS-TR-0026 Page I of 3 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-Oxx JPM TITLE: Prepare a Clearance Tagout for 2FWE-P23A, 'A' Motor JPM REVISION: 0 Driven Aux Feedwater Pump KIA

REFERENCE:

2.2.13 4.1 / 4.3 TASK ID: 0481-007-03-043 JPM APPLICATION: [:8J REQUALIFICATION [:8J INITIAL EXAM O TRAINING D SRO ONLY 0 ALTERNATEPATHJPM [:8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D Annual Requa! Exam D BVT D Simulate D Simulator D Initial Exam D NRC

~ Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP#:

Time D Yes Allotted 25 Minutes Actual minutes Critical: [:8J No Time: Time:

JPM RES ULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 3 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EV ALU ATOR DIRECTION SHEET TASK STAND ARD: Identify the tagged components, required positions, and clearance sequence for 2FWE-P23A Auxiliary Feedwater Pump.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS:

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

2FWE-P23A Auxiliary Feedwater Pump is to be placed on clearance for pump repacking.

INITIATING CUE: You are to identify the required clearance points (equipment), position (placement configuration), and sequence for clearing 2FWE-P23A, 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.

REFERENCES:

NOBP-OP-1001, "Manual Clearance Generation", Rev. 4 NOP-OP-1001, "Clearance/Tagging Program", Rev. 24 OP Manual Fig. No. 24-3, 8700-RM-424-003, Rev. 19 20M-24, Steam Generator Feedwater System Operating Manual TOOLS: None HANDOUT: NOBP-OP-1001, "Manual Clearance Generation", Rev. 4 NOP-OP-1001, "Clearance/Tagging Program", Rev. 24 OP Manual Fig. No. 24-3, 8700-RM-424-003, Rev. 19 20M-24, Steam Generator Feedwater System Operating Manual Clearance coversheet 2R00-24-FW-OO l

BVPS-TR-0026 Page 3 of 3 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-Oxx JPM TITLE: Prepare a Clearance Tagout for 2FWE-P23A, 'A' Motor JPM REVISION: 0 Driven Aux Feedwater Pump STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU EVALU ATOR 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.

START TIME:

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

2FWE-P23A-CS PTL

4KVS-2AE-4/2EI8 OFF

C 4KVS-2AE-2EI8 RACKED OUT

C 2FWE-37 SHUT

C 2FWE-52 SHUT

C 2FWE-9I SHUT

C 2FWE-94 SHUT

C 2FWE- l l 7 l OPEN

C 2FWE-l 169 OPEN COMMENTS:

TERMINATING 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 Component Description Position Sequence 2FWE-P23A-CS BB C/S Steam Generator Aux FW Pump Pull-To-Lock 1 (PTL)

C*l) 4KVS-2AE- 125 VDC Breaker Control for 4KVS-2AE- OFF 2 4/2E18 2E18 4KVS-2AE-2E18 4160 Volt Breaker for 2FWE-P23A Racked Out 3 2FWE-37 (2FWE*P23A) 'A' Header Disch Isolation Shut 4 2FWE-52 (2FWE*P23A) Recirc Isolation Shut 4 2FWE-91 (2FWE*P23A) Supply from Service Shut 5 (**2)

Water 2FWE-94 (2FWE*P23A) Supply from Primary Shut 5 (**2)

DWST 2FWE-1171 (2FWE*P23A) Casing Drain Open 6 (**2) 2FWE-1169 (2FWE*P23A) Casing Vent Open 6 (**2)

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.

<* 1). DC Control PWR is optional and not required.

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

BVPS-TR-0026 Page I of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-A4 RO JPM TITLE: Complete Emergency Plan Initial Notifications (RO Only)

JPM REVISION: 0 Kl A

REFERENCE:

2.4.43 3.2 TASK ID: 0481-024-03-013 JPM APPLICATION: IX] REQUALIFICATION C8;J INITIAL EXAM O TRAINING D SROONLY 0 ALTERNATE PATH JPM C8;J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[SJ Perform D Plant Site D AnnualRequalExam D BVT D Simulate D Simulator D Initial Exam D NRC

[SJ Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP#:

Time C8J 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:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALU ATOR DIRECTION SHEET TASK ST AND ARD: Completes the 15 minute initial notifications to the organizations listed in Section lof the Emergency Notification Call-List. (6 agencies)

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS: The Emergency Director has declared an Alert at Beaver Valley Unit 2.

He has provided you the Initial Notification Form for the event, procedure Yz-EPP-IP-1.1 Notifications, and the Emergency Notification Call-List. The Network copier/ scanner is not available, the FAX machine will be used.

You are to make the notifications per Attachment A, Initial Notifications.

INITIATING CUE: You are to notify the offsite agencies listed in section 1 of the Emergency Notification Call-List. You are only required to contact the agencies that are to be notified within 15 minutes of the event.

Use Passcode 9999 when activating the Initial Notification Bridge Line.

THIS IS A TIME CRITICAL JPM

REFERENCES:

Yi-EPP-IP-1.1, Notifications, Rev 54 Yz-EPP-IP-1. l .F02, Emergency Notifications Call-List Rev 24

'/2-EPP-IP-l. l.FOl, FENOC Nuclear Power Plant Initial Notification Form, Rev 9 TOOLS: EPP Fax Machine (not connected) or simulated machine Telephone (not connected) or simulated HANDOUT: 1/2-EPP-IP-l. l, Notifications

'l2-EPP-IP-l. l .F02, Emergency Notifications Call-List Yz-EPP-IP-1.1.FO 1, FENOC Nuclear Power Plant Initial Notification Form, completed for an ALERT (SAl) Classification. No PAR with a Code Word of SIMULATOR.

BVPS-TR-0026 Page 3 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-A4 RO JPM TITLE: Complete Emergency Plan Initial Notifications (RO Only)

JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U START TIME:

EVALUATOR NOTE: The use of the FAX Machine and Telephone will be simulated. The equipment is not to be connected for communications. Record the time critical start when candidate reviews the handouts.

I TIME CRITICAL START TIME: I

1. Reviews Attachment A of Y:z- 1.1 Reviews the Attachment and Call List materials.

EPP-IP-1.1 for Initial Notifications, the Initial 1.2 Reviews the Initial Notification form for the ALERT Notification form and the Call classification.

List.

COMMENTS:

EV ALU ATOR NOTE: The copier/scanner is not available per the initial conditions, if needed cue the candidate to use the FAX machine.

2.lC Places the completed Initial Notification form on the 2.C Transmit the Initial FAX machine face down.

Notification Form to the Offsite Agencies: 2.2C Depresses the Speed Dial number "01" labeled INF/

FUN, or dials the listed phone number.

Place completed Notification Form on the fax machine (face 2.3C Pushes the START button.

down).

EVALUATOR CUE: The FAX machine starts and Press Speed Dial number "O l" the Initial Notification Form is transmitted.

labeled "INF/FUN" (or dial 9-1-330-436-8514) on the fax COMMENTS:

machine.

Push the START button.

BVPS-TR-0026 Page 4 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-A4 RO JPM TITLE: Complete Emergency Plan Initial Notifications (RO Only)

JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=:> SIU 3.C Initiate the Primary Initial 3.lC Dials 1-724-682-1900 or 1900.

Notification Conference (INC)

Bridge Line EVALUATOR CUE: After dialing state, "Welcome to the Beaver Valley Power Station Conferencing Dial 1-724-682-1900 (or from a System please enter your passcode followed by a PAX phone, "1900"). pound sign."

When prompted, enter Passcode If needed, cue that the passcode is 9999, as was given XXXX and then the # key in the initiating cue.

(NOTE the following steps are NIA) 3.2C Enters Passcode "9999" the "#".

IF unable to activate the Primary INC Bridge Line, EVALUATOR CUE: After dialing state, "Your THEN dial the Backup INC passcode has been confirmed, please wait while you Bridge Line. are joined to your conference."

Dial 1-800-882-3610.

When prompted, enter Backup You are now connected to the conference line.

Bridge Line Passcode xxxxxx.

IF unable to activate either INC 3.3 Does not access the backup INC bridge or each Bridge line, THEN individually Agency individually.

contact each required Offsite Agency using the contact COMMENTS:

information listed on Form 1/2-EPP-IP-l. l.F02, EMERGENCY NOTIFICATION CALL-LIST, SECTION 1.

BVPS-TR-0026 Page 5 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-A4 RO JPM TITLE: Complete Emergency Plan Initial Notifications (RO Only)

JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU 4.C Provide Initial Notification to EV ALU ATOR CUE: The following are on the Offsite Agencies. conference line:

As each Agency enters the

Beaver County Emergency Management INC call, state the following: Agency "This is Beaver Valley Power

PA Emergency Management Agency Duty Station, please stand-by for an Officer emergency notification."

Columbiana County Emergency Management Agency After all Agencies* appear to

Ohio Emergency Management Agency Duty be on the call, state the Officer following: "This is (Your

West Virginia Division of Homeland Security/

Name) at Beaver Valley Emergency Management Power Station, and the Code

Hancock County Office of Emergency Word is " (get Code Word Management from the Initial Notification Form). 4.1 States, "This is the Beaver Valley Power Station, please standby for an emergency notification."

Perform a roll-call and record the contact time of each 4.2 After all Agencies appear to be on the call, state the agency representative on Form following, "This is (their Name) at Beaver Valley 1/2-EPP-IP-l. l .F02, Power Station, and the Code Word is EMERGENCY SIMULATOR.".

NOTIFICATION CALL-LIST, SECTION 1. 4.3C Performs a roll call and records the contact time of each agency representative on Form 1/2EPP-IP-(NOTE: The following are l .1.F02 Emergency Notification Call-List.

N/A)

If a party does not answer to EVALUATOR CUE: Report that all agencies listed the roll call in a reasonable on section 1 of the form respond to the Roll Call.

period of time, bypass that party and proceed down the 4.4C States the Emergency Classification is an ALERT list. After other required (SAI) and that there is NO Protective Action State/County contact times are Recommendation.

logged, re-attempt to contact any bypassed parties. TIME CRITICAL STOP TIME:

State the Emergency NOTE: Must be within 15 minutes of the start time.

Classification and Protective Action Recommendation( s) COMMENTS:

from the Initial Notification Form.

BVPS-TR-0026 Page 6 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-A4 RO JPM TITLE: Complete Emergency Plan Initial Notifications (RO Only)

JPM REVISION: 0 STEP STANDARD

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

5. Ask each agency if they 5.1. Asks if all agencies have received the Initial received the Initial Notification Form FAX and if it was legible.

Notification Form FAX or EMAIL, and if it is legible. EVALUATOR CUE: Report that all agencies have received the legible FAX.

If the FAX or EMAIL is not legible, or was not received, 5.2 Asks if there are any questions.

read the information from the entire Initial Notification EVALUATOR CUE: Report that all agencies have Form verbally. The Initial no questions.

Notification Form may be re-sent after the call, if requested.

5.3 State "A Follow-Up Notification will be provided as Ask if there are any questions. additional information becomes available. Beaver Answer the questions if the Valley Power Station is now exiting the Initial answer is known. Do not give Notification Conference Call. This will terminate the an answer unless you have conference bridge."

firm information that the answer is valid. Do not COMMENTS:

speculate on any future events or actions.

If any questions cannot be immediately answered, get a telephone number where someone can return the call with the answer when the answer is found.

State "A Follow-Up Notification will be provided as additional information becomes available. Beaver Valley Power Station is now exiting the Initial Notification Conference Call. This will terminate the conference bridge."

BVPS-TR-0026 Page 7 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-A4 RO JPM TITLE: Complete Emergency Plan Initial Notifications (RO Only)

JPM REVISION: 0 STEP STANDARD

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

6. For any State/County 6.1. Recognizes that all agencies have been notified, steps Agency(ies) not on the are N/A.

conference call, perform the following: 6.2 Signs and Dates page 1 of Form 1/2-EPP-IP-l. l.F02.

Contact each remaining 6.3 Notifies the SM/ED that the six (6) required Offsite Agency individually State/County Agency Notifications are completed.

using the contact information on Form 1/2-EPP-IP-l. l.F02, EVALUATOR CUE: Acknowledge report as the EMERGENCY Shift Manager.

NOTIFICATION CALL-LIST, SECTION 1. COMMENTS:

Repeat steps 4.2 through 4.7.

Every effort MUST be made to contact all six (6) required State/County organizations and all attempts MUST be documented.

Sign and Date page 1 of Form 1/2-EPP-IP-l .1.F02.

Notify the SM/ED that the six (6) required State/County Agency Notifications are completed.

EVALU ATOR CUE: Once the report is made to the Supervisor, state "This JPM is complete".

STOP TIME: - - - - - - -

BVPS-TR-0026 Page I of 8 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-001 M JPM TITLE: Calculating a Shutdown Margin Following a Stuck Rod JPM REVISION: 0 KIA

REFERENCE:

2.1.25 3.9/4.2 TASK ID: 0011-006-06-013 JPM APPLICATION: [8J REQUALIFICATION IZI INITIAL EXAM D TRAINING D SROONLY 0 ALTERNATE PATH JPM [8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D Annual Requa( Exam D BVT D Simulate D Simulator D Initial Exam D NRC

~ Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

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 Name/SAP: Name/SAP:

Name/SAP: Name/SAP:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 13 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determines correct SOM and boration requirements for one dropped rod, then two other rods stuck full out.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS:

All rods are at 228 steps on group demand counters.

A single Bank "D" Control Rod has dropped and indicates O steps.

The plant is at 100% power.

Tavg is within 1F of Tavg.

Current RCS boron concentration is 600 PPM from a sample at 1115.

Core Burn-up is 16500 MWD/MTU.

The date is [today] at 13 00 INITIATING CUE: Part 1:

Your supervisor has directed you to perform a Shutdown Margin calculation for the present plant conditions using 20ST-49. I, "Shutdown Margin Calculation" (Plant Critical), beginning at step VII.A, and other provided references. Report your results in the COMMENT section of the OST cover sheet.

Part 2:

At 1304, after calculating the shutdown margin using 20ST-49. l, power was reduced to 90% and two rods were reported by the ATC as stuck full out. Evaluate any effects on shutdown margin.

REFERENCES:

20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 20), Rev. 22 Unit 2 Plant Curve Book (Updated for Cycle 20)

Unit2 LRM TOOLS: Calculator Ruler/straight edge HANDOUT: 20ST-49 .1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 20), Rev. 22 place kept up to step VII.A.

Unit 2 Plant Curve Book (Updated for Cycle 20)

Unit 2 LRM

BVPS-TR-0026 Page 3 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod 001 M then Stuck Rod JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)::::, SIU EVALUATOR NOTE: Provide the Candidate with a copy of20ST-49.1, Cycle 20 Curve Book, Unit 2 LRM, calculator, and a ruler/straight edge.

START TIME: _ _ _ _ _ __

1. If the plant is in Mode 1 with 1.1 Initials Step VII.A 1, (From initial conditions Tavg is the Main Generator online, within IF of Tref.

Verify that Tavg is less than 3°F above Tref. (Otherwise COMMENTS:

NIA).

(Ste VII.Al)

2. If the plant is in Mode 2 OR 2.1 Places N/A in Step VII.A2, (Plant not in Mode 2).

Mode 1 with Main Generator offline, Verify that Tavg is COMMENTS:

less than SF above Program Tavg as follows: (Otherwise NIA).

(Ste VII.A.2)

3. Request Chemistry to 3.1 Determines current boron concentration is 600 ppm determine current RCS from initial conditions.

Boron concentration in ppm.

COMMENTS:

(Step VII.A.3)

4. Record the number of steps 4.1 Records Control Bank Das 228 steps withdrawn on withdrawn for Control Bank Data Sheet 1 from initial conditions.

D from the group demand counters, (BB-B) on Data COMMENTS:

Sheet 1.

(Step VII.A.4)

BVPS-TR-0026 Page 4 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod 001 M then Stuck Rod JPM REVISION: 0 STEP STANDARD

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

5. Record the current reactor 5.1 Records reactor power as 100% on Data Sheet 1.

power level in percent of full power from [2NME-NR45], COMMENTS:

Reactor Excore Recorder, (VB-B) OR PCS computer point Ul 150, PWR RNG NUCLEAR FLUX IM AVG, on Data Sheet 1.

(Step VII.A.5) 6.C Record the number of 6.lC Determines one rod is dropped and records as immovable or untrippable immovable or untrippable on Data Sheet 1.

control rods on Data Sheet 1.

COMMENTS:

(Step VII.A.6)

7. If the number of inoperable 7.1 Places NIA in Step VII.A.7.

(untrippable) OR dropped control Rods is greater than COMMENTS:

1, Use Attachment 1 to determine the required boron concentration with greater than one inoperable rod and Record below. (Otherwise NIA)

(Step VII.A. 7)

BVPS-TR-0026 Page 5 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod OO l M then Stuck Rod JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT ~ S/U 8.C Determine control bank 8.1 Recognizes initial plant core burnup is 16500 reactivity worth per the MWD/MTU, based on initial plant conditions.

following:

8.2 Refers to ARO Total Bank Worth table on Data Sheet Using the ARO Total Bank 1 AND determines ARO Total Bank Worth to be Worth table on Data Sheet 1, 7.813.

Enter the total bank worth for the current core burnup 8.3C Records 7.813 on Data Sheet 1 (Block B. l.a).

range, in the space provided on Data Sheet 1. COMMENTS:

(Step Vll.B.1.a) 9.C Using Curve Book Figures 9.lC Using Curve Book Figure CB-24C, determines CB24A, 248 OR 24C, integral rod worth to be ZERO and records on Data Determine integral rod worth Sheet 1 (Blocks B.1. b. l) and (B. l. b ).

for the current bank position AND Enter this value on COMMENTS:

Data Sheet 1.

Divide value from curve (in pcm) by 1000 to convert to o/o~k/k AND Record on Data Sheet 1.

(Step VII.B. l.b) 10.c Subtract the integral rod 10.1 Determines TBW-IRW is 7.813% ~k/k and records worth from the Total Bank on Data Sheet 1 (Block B.1.c).

Worth AND Enter the result on Data Sheet 1. COMMENTS:

(Step VII.B. l .c)

BVPS-TR-0026 Page 6 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod OO l M then Stuck Rod JPM REVISION: 0 STEP STANDARD

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

11. (. Multiply this result by 0. 9 to 11.1 Determines 90% ofTBW to be 7.0317% ~k/k and apply a 10% uncertainty records on Data Sheet 1 (Block B. l .d).

AND Enter the result on Data Sheet 1. COMMENTS:

(Step VII.B. l .d) 12.C Inoperable (Untrippable) OR 12. 1C Determines stuck rod worth to be 2. 77 4% ~k/k and Dropped Rods: records on Data Sheet 1 (Block B.2).

If ONE rod is inoperable (untrippable) OR dropped, Record "Worst Case Rod COMMENTS:

with Inoperable Rod" worth on Data Sheet 1. Value is determined from Column "B" on Attachment 2 for the appropriate Cycle Bumup.

(Step VII.B.2.b)

13. Subtract Stuck Rod Worth 13 .1 Determines 90% Total Bank Worth minus Stuck from the 90% Total Bank Rod(s) Worth to be 4.2577 %~k/k and records on Worth value AND Enter the Data Sheet 1 (Block B.3).

result on Data Sheet 1.

COMMENTS:

(Step VII.B.3)

14. Determine Power Defect as 14.1 Record RCS Boron Concentration of 600 ppm on follows: Data Sheet 1 (Block B.4.a).

Record RCS Boron COMMENTS:

Concentration results from Chemistry on Data Sheet 1.

(Step VII.B.4.a)

BVPS-TR-0026 Page 7 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod 001 M then Stuck Rod JPM REVISION: 0 STEP STANDARD

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

15. Using Curve Book Figure 29, 15.1 Determines B-10 Correction Factor to be 0.837 and Determine the B-10 records on Data Sheet 1 (Block B.4.b).

Correction Factor for the present Bumup (If between COMMENTS:

two Bumup values, Use the B-10 Correction Factor for the greater MWD/MTU Bumup entry) AND Record on Data Sheet 1.

(Step VII.B.4.b)

16. Determine Corrected Boron 16.1 Determines Corrected Boron Concentration to be Concentration by multiplying 502.2 ppm and records on Data Sheet 1 (Block B.4.c).

the RCS Boron Concentration and the B-10 COMMENTS:

Correction Factor AND Record on Data Sheet 1.

(Step VII.B.4.c)

17. Using Curve Book Figure 21, 17.1 Determines ABSOLUTE VALUE of the Power Determine the ABSOLUTE Defect to be 2580 pcm and records on Data Sheet 1 VALUE of the Power Defect (Block B.4.d).

for the current power level and the Corrected Boron COMMENTS:

Concentration AND Enter this value on Data Sheet 1.

(Step VII.B.4.d)

BVPS-TR-0026 Page 8 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod 001 M then Stuck Rod JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU 18.C Divide value from curve (in 18. 1C Converts ABSOLUTE VALUE of the Power Defect pcm) by 1000 to convert to of 2580 pcm to 2.580 %1'.\k/k and records on Data

%1'.\k/k AND Record on Data Sheet 1 (Block B.4.e).

Sheet 1.

COMMENTS:

(Step VII.B.4.e)

19. Add 0. 150% L\k/k for 19. 1 Determines Power Defect plus operating temperature operating temperature band band margin to be 2.730 % L\k/k and records on Data margin to the Power Defect Sheet 1 (Block B.4.f).

recorded in Step VII.B.4.e AND Record on Data Sheet COMMENTS:

1.

(Step VII.B.4.f) 20.C Determine SHUTDOWN 20.lC Determines SOM to be 1.5277% (+/- 0.100%) L\k/k, MARGIN by subtracting and records on Data Sheet 1 (Block B.4.f) AND Power Defect (Step records on the OST cover sheet.

VII.B.4.f) from the value determined in Step VII.B.3 20.2C Compares calculated SDM to the limits specified in AND Record on Data Sheet the COLR, and determines that it does NOT meet

1. acceptance criteria AND records on the OST cover sheet.

(Step VII.B.5)

COMMENTS:

BVPS-TR-0026 Page 9 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod 001 M then Stuck Rod JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU PART2:

21. Step VII.A I through VII.A.4 COMMENTS:

were previously completed.

(Step VII.A I)

22. Record the current reactor 22.1 Records 90% from the cue in part 2.

power level in percent of full power from [2NME-NR45], COMMENTS:

Reactor Excore Recorder, (VB-B) OR PCS computer point Ul 150, PWR RNG NUCLEAR FLUX IM AVG, on Data Sheet 1.

(Step VII.AS) 23.C Record the number of 23.lC Determines one rod is dropped, two rods are stuck immovable or untrippable and records three (3) rods as immovable or control rods on Data Sheet 1. untrippable on Data Sheet 1.

(Step VII.A6) COMMENTS:

BVPS-TR-0026 Page 10 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod OO l M then Stuck Rod JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)::::, SIU 24.C If the number of inoperable 24.lC Candidate uses Attachment I, "Required Boron (untrippable) OR dropped Concentration With Greater Than One Inoperable control Rods is greater than Rod" and determines required boron concentration to 1, Use Attachment 1 to be 1314 ppm.

determine the required boron concentration with greater than one inoperable rod and EXAMINER NOTE: The procedure is not clear on what do to when Record below. (Otherwise in between bumup values for this table. Need to clarify, applicant may interpolate or pick higher bumup value instead of higher boron NIA) requirement. Interpolation value: 1266 ppm. Higher Burunup = 1121 ppm. Examiner discretion is required.

(Step VII.A. 7)

COMMENTS:

25.C With the number of inoperable 25. IC Determines that this step is applicable and goes to (untrippable) OR dropped Step VII.C.2.

rods greater than one, the shutdown margin is < 1. 77% COMMENTS:

Lik/k. Perform Step VII.C.2 UNTIL the required boron concentration of Attachment 1 is reached.

(Step VII.A.7.a) 26.C If SDM is not within limits 26.lC Determines that the SDM is NOT within limits specified in the COLR, intiate specified in the COLR and reports that boration is boration and continue UNTIL required. Boration value = Step VII.A. 7 - Step the required SDM is restored. VII.A.3= 1314 ppm- 502 ppm= 812 ppm boron.

(Step VII.C.2) COMMENTS:

BVPS-TR-0026 Page 11 of 11 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-JPM TITLE: Calculating a Shutdown Margin Following a Dropped Rod OO l M then Stuck Rod JPM REVISION: 0 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U EVALUATOR CUE: When the candidate hands in the OST cover sheet and reports how much additional boration is required, the JPM is complete.

EVALUATOR CUE: Grader discretion may be required.

STOP TIME: -------

BVPS-TR-0026 Page 1 of 7 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-023 JPM TITLE: Perform a Hot Bus Transfer JPM REVISION: 11 Kl A

REFERENCE:

062 Kl.04 3.7/4.2 TASK ID: 0361-013-01-013 062 A4.01 3.3/3.1 JPM APPLICATION: (2J REQUALIFICATION (2J INITIAL EXAM D TRAINING D SROONLY 0 ALTERNATE PATH JPM O ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D AnnualRequalExam D BVT D Simulate ~ Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RES UL TS Performer Name: Performer SAP#:

Time D Yes Allotted 15 Minutes Actual minutes Critical: [2J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

. Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The 4KV Bus 2B is being supplied by the System Station Service Transformer.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS: The plant is at 100% power with all systems in NSA. It is desired to place the 2B 4KV bus on offsite power to allow for a relay check on ACB-142C.

INITIATING CUE: Your supervisor directs you to transfer the 2B 4KV bus to the 2A SSST in accordance with 20M-36.4.C, "Transferring 4KV System from US Serv Tfmr To SS Serv Tfmr". Do NOT set up for auto transfer back to USST 2C.

REFERENCES:

20M-36.4.C, "Transferring 4KV System From US Serv Tfmr To SS Serv Tfmr", Rev 15 TOOLS: None HANDOUT: 20M-36.4.C, "Transferring 4KV System From US Serv Tfrnr To SS Serv Tfmr", Rev 15

BVPS-TR-0026 Page 3 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-023 JPM TITLE: Perform a Hot Bus Transfer JPM REVISION: 11 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U SIMULATOR SETUP:

Initialize to a 100% power IC Set with all systems in NSA.

EVALUATOR NOTE: Provide the candidate a copy of 20M-36.4.C. When candidate is ready to begin, ENSURE the simulator in RUN.

START TIME:

1. Reviews the copy of 20M- 1.1 Reviews 20M-36.4.C.

36.4.C, "Transferring 4KV System From US Serv Tfmr To COMMENTS:

SS Serv Tfmr", provided.

BVPS-TR-0026 Page 4 of 7 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-023 JPM TITLE: Perform a Hot Bus Transfer JPM REVISION: 11 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT :::> S/U EVALUATOR NOTE: Candidate needs to check only Bus 2B since the other Busses will NOT be transferred for this JPM.

EVALUATOR NOTE: The values specified in step 2.2 are identified in P&L K of the procedure.

2. Verify voltages on the 4KV 2.1 Locates the 4KV Common Voltmeter, KV Bus 2B Busses and SSSTs are Voltmeter, and 2A SS Serv Tfmr Voltmeter Phase approximately the same on all Selector Switch.

phases as follows:

2.2 Checks all phases on the 2A SS Serv Tfmr Voltmeter

a. Places the 2A SS Serv Phase Selector Switch, "X" position. Verifies SSST Tfmr Voltmeter Phase 2A voltage is Oto 2.0 volts higher than Bus 2B selector switch to each of voltage, and the unloaded transformer secondary is the phases of Bus 2A & between 122 volts and 126.5 volts.

2B and compares the values on the 4KV COMMENTS:

Common Volt meter to the same phase values on the 4KV Bus 2A & 2B Volt meters when 4KV Bus 2A

& 2B Voltmeter Phase Selector switches are selected to each phase.

EVALUATOR CUE:

Another operator has completed Data Sheet 1, all readings are within the required ranges.

3. Perform Data Sheet 1 to check 3.1 Step is N/A.

for an open primary circuit on SSST-2A. COMMENTS:

BVPS-TR-0026 Page 5 of 7 Revision 0 OPERATIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-023 JPM TITLE: Perform a Hot Bus Transfer JPM REVISION: 11 STEP STANDARD

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

4. Adjust SSST secondary voltage 4.1 Determines it is necessary to adjust tap changer and to Oto 2 volts higher than lower SSST secondary voltage.

respective 4KV bus volts for each bus being transferred. 4.2 Locates the Load Tap Changer X Windings - Bus 28 SS Serv TFMR 2A swith and pushes inward to take out of AUTO.

4.3 Places the Load Tap Changer switch to LOWER until the SSST secondary voltage is Oto 2 volts higher than Bus 28.

COMMENTS:

5.C Place the Live Bus Transfer 5.lC Places the Live Bus Transfer Switch to the ON Switch to ON. position.

COMMENTS:

6.C Close [ACB-142A], 2A SS Serv 6.lC Places control switch for ACB-142A to the CLOSE Tfmr to 4KV Bus 28. position.

6.2 Verifies BOTH RED lights - LIT and WHITE light -

NOT LIT 6.3 Acknowledges A8-1H, "4160V NORM BUS SUPPLY ACBs PARALLELED", if received.

COMMENTS:

BVPS-TR-0026 Page 6 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-023 JPM TITLE: Perform a Hot Bus Transfer JPM REVISION: 11 STEP STANDARD

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

7. Check that amps increase on 7.1 Checks 4KV Bus 2B Tfmr 2A ammeter indicates 4KV Bus 2B Tfmr 2A Amps. greater than ZERO amps.

COMMENTS:

8. IF SSST 2A voltage less than 8.1 This step is N/ A. SSST 2A voltage is> 122 volts.

122 volts prior to transfer, Adjust Load Tap Changer, X- COMMENTS:

Winding - Bus 2B, by 4 steps to raise bus voltage. (Otherwise NIA) 9.C Open [ACB-142C], 2C US 9.lC Places control switch for ACB-142C to the Serv Tfmr to 4KV Bus 2B. OPEN/TRIP position.

9.2 Verifies WHITE light - LIT and BOTH RED lights -

NOT LIT 9.3 Silences and resets Annunciator A8-1 H, if cleared.

COMMENTS:

10. Place the Bus 2B load tap 10.1 Places the Load Tap Changer switch to AUTO by changer in AUTO (pulled out pulling outward on the switch.

slightly from vertical board).

COMMENTS:

BVPS-TR-0026 Page 7 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-023 JPM TITLE: Perform a Hot Bus Transfer JPM REVISION: 11 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT):::;, S/U

11. Check load was picked up by 11.1 Checks load was picked up by observing 4KV Bus 2B observing 4KV Bus 2B Tfmr Tfmr 2A amps increasing to a higher value.

2A Amps.

COMMENTS:

12. Place the Live Bus Transfer 12.1 Places the Live bus Transfer Switch to the OFF Switch to OFF. position.

COMMENTS:

EVALUATOR CUE: State "This JPM is complete" STOP TIME:

BVPS-TR-0026 Page 1 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx . .

JPM REVISION: O . JPM TITLE: Respond to VCT Level Transmitter Failure KIA

REFERENCE:

004 A2.18 3.1 I 3.1 TASK ID: 0071-025-01-013 004 A4.12 3.8 / 3.3 0071-115-04-012 JPM APPLICATION: ~ REQUALIFICA TION ~ INITIAL EXAM D TRAINING D SRO ONLY ~ ALTERNATEPATHJPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[8J Perform D Plant Site D Annual Requa! Exam D BVT D Simulate [8J Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SAP: Name/SAP:

Name/SAP: Name/SAP:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Perform calculations and manipulations required to perform a manual blender makeup to the VCT in accordance with 20M-7.4.N, "Blender Manual Makeup Operations", and stop the VCT from diverting prior to emptying the VCT during the 2CHS-LT115 level transmitter failure.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS:

The plant is in Mode 1.

The in service 'A' Boric Acid Tank concentration is 7487 ppm.

Current Corrected RCS boron concentration is 14 71 ppm.

VCT level is currently 28%.

INITIATING CUE: Your supervisor directs you to perform a 200 gallon makeup to the VCT at 75 gpm to raise VCT level to 42%, in accordance with 20M-7.4.N, "Blender Manual Makeup Operations", beginning at step IV.A.6.

REFERENCES:

20M-7.4.N, Blender Manual Makeup Operations, Rev. 16 20M-7.4.AAC, Volume Control Tank Trouble, Rev. 6 20M-7.4.IF, Instrument Failure Procedure, Rev. 3 TOOLS: Calculator HANDOUT: 20M-7.4.N, Blender Manual Makeup Operations, Rev. 16, place kept up to Step IV.A.6.

Have copies of the following available to replace Simulator copy.

20M-7.4.AAC, Volume Control Tank Trouble, Rev. 6 20M-7.4.IF, Instrument Failure Procedure, Rev. 3

BVPS-TR-0026 Page 3 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx JPM TITLE: Respond to VCT Level Transmitter Failure JPM REVISION: 0 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU EVALU ATOR NOTE: Simulator setup:

- Any Mode 1 IC.

- Expert command to set VCT level to 28%: Set AVCTLIQ=6720 (Preloaded to IC snap)

- Fail 2CHS-MOV350 Closed - VLV-BAT014 2

- Mark in service BAST 7487 PPM; (RCS Cb=1471).

Set 2CHS*FCV114A Potentiometer for 100 gpm flow rate. (625 dial units)

Fail 2CHS*LT115 high when VCT level reaches 38%.

EV ALU ATOR NOTE:

The blender makeup calculations may be completed during the JPM brief for time efficiency.

BOOTH OPERATOR NOTE:

Set BA & Total flow totalizers to ZERO after each performance of the JPM.

START TIME: - - - - - - -

1. Reviews 20M-7.4.N, 1.1 Reviews 20M-7.4.N, "Blender Manual Makeup "Blender Manual Makeup Operation.

Operation.

COMMENTS:

BVPS-TR-0026 Page 4 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx JPM TITLE: Respond to VCT Level Transmitter Failure JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EV ALU ATOR NOTE: Candidate may perform flow setpoint calculations prior to making any control manipulations.

2. Place Boric Acid Makeup 2.1 Places Boric Acid Makeup Blender Control switch in Blender Control switch in STOP position.

Stop.

2.2 Verifies Green Light- LIT, Red Light- NOT LIT.

COMMENTS:

EVALU ATOR CUE: If asked, role-play the US and report independent verifications of calculations SAT.

EVALUATOR CUE: If asked, provide BAST boron of 7487 ppm and Corrected RCS boron is 1471 ppm.

3.C Determine desired boric acid 3.1 C Calculates boric acid flow:

flow.

l47lppm X 75gpm = 14 .74 gpm 7487ppm COMMENTS:

4.C Adjust [2CHS*FCV113A] 4.1 C Calculates the desired flow setpoint:

Boric Acid to Blender to the 14 *74 gpm xlOO = 368 calculated setpoint.

4gpm 4.2C Adjusts 2CHS*FCV113A for the desired flow setpoint, 368 units +/- 5 units.

COMMENTS:

BVPS-TR-0026 Page 5 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx JPM TITLE: Respond to VCT Level Transmitter Failure JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU 5.C Set Boric Acid Flow to EVALUATOR NOTE: Batch amounts are at the Blender Flow Totalizer. operator's discretion. Total volume change is approximately 200 gallons. Candidate must set the appropriate amount of BA volume for the batch amount. If performing full makeup (200 gals) then the amount of BA is:

14.74 gpm X (200gals / 75 gpm) = 39 gal.

5.lC Adjusts 2CHS-FQIS 113 Boric Acid Flow to Blender Flow Totalizer to the desired value.

5.2C Depresses "RESET" on 2CHS-FQIS 113.

COMMENTS:

6.C Adjust [2CHS*FCV114A] 6.lC Adjusts 2CHS*FCV114A for 75 gpm.

setpoint.

(75 gprn/16) xlOO = 468 units+/- 5 units.

COMMENTS:

7.C Set [2CHS-FQIS 168] Total 7.lC Adjusts Total Makeup from Blender Flow Totalizer Makeup From Blender Flow to 200 gallons).

Totalizer to the desired total volume in gallons of makeup 7.2C Depresses "RESET" on 2CHS-FQIS 168.

water to be added.

EVALUATOR NOTE: Batch amounts are at the operator's discretion. Total volume change is approximately 200 gallons (-14 gal/%).

COMMENTS:

BVPS-TR-0026 Page 6 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx JPM TITLE: Respond to VCT Level Transmitter Failure JPM REVISION: 0 STEP STANDARD

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

8. Adjust [2CHS*HIC168] 8.1 Verifies 2CHS*HIC168 is set to 75 gpm.

Blender Total Flow Auto (75 gpm/16) x 100 = 468 units+/- 5 units.

Setpoint.

COMMENTS:

9. Note flow totalizer indication 9.1 Notes the Boric Acid Flow to Blender Flow Totalizer and adds it to the gallon set value on 2CHS*FQ1S 113 and adds the Boric Acid on the batch integrators for volume previously calculated (39 gallons).

2CHS*FQ1S 113 and 2CHS*FQ1S 168. 9.2 Notes the Blender Total Flow value on 2CHS*FQIS168 and adds the Total Volume previously calculated (200 gallons).

COMMENTS:

10. Verify a Reactor Coolant 10.1 Verifies that RCS flow is 2: 3000 gpm flow by Pump is operating in an observing RCP operation or flow indications.

unisolated loop and has 2:

3000 gpm flow through the 10.2 Records information in the Narrative Log.

core and records the commencement of makeup EVALUATOR CUE: Inform the candidate that and flow verification in the another operator will make the Narrative Log entry.

Narrative Log.

COMMENTS:

BVPS-TR-0026 Page 7 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx JPM TITLE: Respond to VCT Level Transmitter Failure JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSA T ::) SIU

11. Verify the inservice Boric 11.1 Verifies 2CHS-P22A is in AUTO.

Acid Transfer Pump in AUTO. 11.2 Control switch has GREEN Target, and GREEN light- LIT COMMENTS:

EV ALU ATOR CUE: If asked, as Unit Supervisor 12.C Open [2CHS*FCV114B],

direct the use of 2CHS*FCV114B.

Blender Outlet to Volume Control Tank. 12.lC Places 2CHS*FCV114B control switch to OPEN.

12.2 Verifies RED Light - LIT and GREEN Light - NOT LIT.

COMMENTS:

13.C Place Mode Selector in 13 .1 C Places the Mode Selector Switch in MAN position.

MAN.

COMMENTS:

BVPS-TR-0026 Page 8 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx JPM TITLE: Respond to VCT Level Transmitter Failure JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 14.C Place Boric Acid Makeup 14.IC Places Boric Acid Makeup Blender Control switch to Blender Control switch to START.

START.

14.2 Verifies 2CHS-P22A starts, RED Light - LIT and

Verify Boric Acid GREEN Light - NOT LIT.

Transfer Pump in AUTO is running. 14.3 Verifies Boric Acid to Blender Flow, and Total MIU

Verify proper boric acid Flow from Blender on 2CHS-FR113.

flow on [2CHS*FR113].

Verify proper total COMMENTS:

makeup flow on

[2CHS*FR113].

FAULT STATEMENT:

When VCT level reaches 38%, 2CHS-LT115 will fail high and cause an auto divert to the Boron Recovery System. Candidate must take manual action to stop diverting letdown flow, and align it back to the VCT.

15. Operate pressurizer heaters 15 .1 N/A step due to sufficient PRZR heaters.

[2RCS*H2A,B,C,D,E],

PRZR Heaters Group A, B, COMMENTS:

C, D, E, to automatically initiate spray as required to equalize boron concentration between coolant loops and pressurizer to within 50 ppm.

(Otherwise NI A)

16. At least once per hour during 16.1 Acknowledges, or N/ As the step.

makeup, Verify a reactor coolant pump operating in an COMMENTS:

unisolated loop with >3000 gpm flow through the core.

BVPS-TR-0026 Page 9 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx JPM TITLE: Respond to VCT Level Transmitter Failure JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU EVALUATOR NOTE: The alarm response procedure may not be referenced if the instrument failure of 2CHS-L Tl 15 is diagnosed based upon plant indications. The following step may not be performed. Candidate may also enter AOP 2.4.1 for the loss of process control.

17. Annunciator A2-2G "Volume 17.1 Acknowledges annunciator A2-2G.

Control Tank Trouble will alarm. 17.2 References 20M-7.4.AAC alarm response procedure probable cause No. 2, Instrument Failure.

17.3 Confirms that 2CHS-LT115 has failed by comparing level indicator 2CHS-Lll 15 and Computer point L2704A for redundant channel 2CHS-LT112.

17.4 Refers to 20M-7.4.IF, Instrument Failure.

COMMENT:

18. Enters 20M-7.4.IF, 18.1 Refers to 20M-7.4.IF, Instrument Failure procedure Instrument Failure procedure Attachment 1 for the high failure of2CHS-LT115.

for the failure of 2CHS-LTl 15. 18.2 Confirms that 2CHS-LT115 has failed by comparing level indicator 2CHS-LI 115 and Computer point L2704A for redundant channel 2CHS-LT112.

COMMENT:

BVPS-TR-0026 Page 10 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-xxx JPM TITLE: Respond to VCT Level Transmitter Failure JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 19.C Place the VCT level Control 19.IC Places 2CHS-LCV1 ISA.control switch to VC Tank Selector Switch in the VCT position.

position.

19.2 Verifies 2CHS*LCV112, VCT RED Light- LIT and Check [2CHS*LCV112], CLNT RCVY RED Light - NOT LIT.

VCT Level Control To Clnt Rcvy Vlv, AND 19.3 Verifies 2CHS*LCV1 ISA, VCT RED Light- LIT

[2CHS*LCV1 ISA], VCT and DEGAS RED Light- NOT LIT.

Level Cont Divert To Degas Vlv, are aligned to the VCT. COMMENT:

20. If necessary raise VCT level 20.1 Evaluates the VCT level response to the failure and by performing a manual determines if action is needed to adjust level.

makeup per 20M-7.4.N, Blender Manual Makeup COMMENT:

Operation.

OR Lower V CT level by diverting letdown flow to the Boron Recovery System.

I EVALUATOR CUE: State "This JPM is complete."

I

',,; ;'. ' ;, ',; ,?;-

,, : STOP TIME:

BVPS-TR-0026 Page 1 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new .

JPM REVISION: 0 JPM TITLE: Respond to Master Pressure Controller Failure KIA

REFERENCE:

002 A2.02 4.2 I 4.4 TASK ID: 0063-039-01-013 010 A4.0l 3.7 / 3.5 0063-011-01-013 JPM APPLICATION: [8J REQUALIFICATION IZI INITIAL EXAM D TRAINING D SROONLY IZI ALTERNATE PATH JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

k8J Perform D Plant Site D AnnualRequalExam D BVT D Simulate k8J Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP#:

Time D Yes Allotted 15 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:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EV ALU ATOR DIRECTION SHEET TASK STAND ARD: Prevent a Reactor trip on Low PRZR pressure, and RCS pressure under operator control with pressurizer spray valves in manual after the Master PRZR Pressure Controller fails high.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS:

Plant is 100% power and stable.

All Initial Conditions are met.

All PRZR heaters are energized.

PRZR Pressure control is in AUTO and stable.

2CHS*FCV122 is in AUTO and stable.

INITIATING CUE:

Your supervisor directs you perform 20M-6.4.AB, Pressurizer Level Control Test starting at Sect B.

Sect A, Test Preparation has been completed.

You are to respond to all annunciators.

REFERENCES:

20M-6.4.AB, Pressurizer Level Control Test, Rev 1 20M-53C.4.2.4.1, Process Control Failure, Rev 1 20M-6.4.AAM, Pressurizer Control Pressure High/Low, Rev 3 TOOLS: None HANDOUT: 20M-6.4.AB, Pressurizer Level Control Test, Rev 1 completed up to section B.

Have copies of the following available for Simulator replacement:

20M-53C.4.2.4.1, Process Control Failure, Rev 1 20M-6.4.AAM, Pressurizer Control Pressure High/Low, Rev 3

BVPS-TR-0026 Page 3 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM REVISION: 0 JPM TITLE: Respond to Master Pressure Controller Failure STANDARD Indicate "S" FOR SAT or "U" FOR UNSA T)~ SIU SIMULATOR SETUP:

Start with any 100% power IC Energize all przr heaters.

Ensure 2CHS-FCV122 is in Auto, and przr master pressure controller and spray valves are in Auto.

TRGSET 6 'XB1D048M >=0.46' sets the trigger to fire when przr level controller reaches 46%.

IMF CNH-PCSlOA (6 20) 70 30 ASIS for 2RCS*PK444A Press Cont Fixed Output MIA at 70.

[write snap]

EVALUATOR NOTE: This is a faulted JPM. When the PRZR level controller is raised to 4.5-5%, the Master Pressure Controller will fail to 70, causing the PRZR spray valves to open.

EVALUATOR CUE: Provide candidate a marked up copy of 20M-6.4.AB.

START TIME:

1. Reviews 20M-6.4.AB, 1.1 Reviews provided procedure 20M-6.4.AB.

Pressurizer Level Control Test. COMMENTS:

2. Verify [2RCS*LI459A, 460, 2.1 Monitors 2RCS*LI459A, 460,461 for stable 461], Pressurizer Level pressurizer level.

stable.

COMMENTS:

BVPS-TR-0026 Page 4 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM REVISION: 0 JPM TITLE: Respond to Master Pressure Controller Failure STEP STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 3.C Place [2RCS*LK459F] 3.lC Depresses 2RCS*LK459F MAN pushbutton PRZR Level Control in MAN 3 .2 Verifies RED MAN light - LIT and AUTO light -

NOT LIT.

COMMENTS:

4. Verify [2RCS*LI459A, 460, 4.1 Verifies 2RCS*LI459A, 460, 461 pressurizer levels 461], Pressurizer Level remain stable.

remains stable.

COMMENTS:

FAULT STATEMENT:

The next step will trigger the fault for the Master Pressure Controller failure, causing the PRZR spray valves to open.

5.C Raise [2RCS*LK459F] 5 .1 C Depresses the controller output .A pushbutton to raise PRZR Level Control output controller output 4.5 to 5 %.

4.5 to 5 % as quickly as possible. 5.2 Monitors system response by observing PRZR level and a rise in charging flow.

COMMENTS:

BVPS-TR-0026 Page 5 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM REVISION: JPM TITLE: Respond to Master Pressure Controller Failure 0

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU EVALUATOR NOTE:

Candidate may refer to Annunciator A4-1 D, Pressurizer Control Pressure High/Low which will correct the lowering pressure.

6. Receives Annunciator A4- 6.1 Recognizes PRZR pressure is lowering by monitoring 10, Pressurizer Control 2RCS-PI444, 445,455,456,457, or PCS.

Pressure High/Low and recognizes PRZR pressure is 6.2 Takes Immediate Operator Actions of AOP- 2.4.1 lowering. Part B for PRZR Pressure Process Control Failure.

COMMENTS:

7. PRZR PORV(s) - CLOSED 7.1 Checks 2RCS*PCV455D, 2RCS*PCV456, and 2RCS*PCV455C CLOSED.

7.2 Verifies GREEN Lights - LIT and RED Lights -

NOT LIT.

COMMENTS:

8. Check PRZR Pressure 8.1 Recognizes PRZR pressure is < 2200 psig and Control lowering.

PRZR Pressure - LESS COMMENTS:

THAN 2200 PSIG

BVPS-TR-0026 Page 6 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM REVISION: JPM TITLE: Respond to Master Pressure Controller Failure 0

STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EVALUATOR NOTE:

2RCS-PK444A is failed at - 70 % and will not respond when the operator attempts to lower demand.

9. Close PRZR spray valves by 9.1 Depresses 2RCS-PK444A MAN pushbutton.

Placing PRZR master pressure controller in MAN 9.2 Verifies RED MAN light - LIT and AUTO light -

AND Adjusting demand to NOT LIT.

<40%.

9.3 Depresses 2RCS-PK444A controller output T pushbutton to lower demand to < 40%, but recognizes the controller does not respond.

COMMENTS:

BVPS-TR-0026 Page 7 of 8 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM REVISION: JPM TITLE: Respond to Master Pressure Controller Failure 0

STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT ~ SIU EVALUATOR NOTE:

The intent of this step is to control RCS pressure with manual control of the spray valves, therefore the candidate may not fully close the spray valves. This is permitted to meet the critical step if RCS pressure is under their control.

10.C IF spray valves do NOT 10.1 Recognizes that the spray valves failed to close.

Close, THEN Place spray valve controllers in MAN I0.2C Depresses 2RCS-PCV455A MAN pushbutton.

AND Adjust as necessary to control pressure. 10.3 Verifies RED MAN light- LIT and AUTO light -

NOT LIT.

10.4C Depresses 2RCS-PCV455A controller output 'Y pushbutton until valve is CLOSED.

10.5 Verifies GREEN light - LIT and RED light - NOT LIT.

10.6C Depresses 2RCS-PCV455B MAN pushbutton.

10.7 Verifies RED MAN light - LIT and AUTO light -

NOT LIT.

10.8C Depresses 2RCS-PCV455B controller output 'Y pushbutton until valve is CLOSED.

10.9 Verifies GREEN light - LIT and RED light - NOT LIT.

COMMENTS:

BVPS-TR-0026 Page 8 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM REVISION: JPM TITLE: Respond to Master Pressure Controller Failure 0

STEP STANDARD

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

11. Checks PRZR pressure at or 11.1 Monitors PRZR pressure indicators 2RCS-PI444, trending to 2235 PSIG. 445,455,456,457, or PCS for rising pressure.

EVALU ATOR CUE: If candidate has PRZR pressure rising, as Unit Supervisor, direct a PRZR pressure control band of 2235 psig (+/- 25 psig).

COMMENTS:

12.C Adjusts spray valves to 12.lC Depresses 2RCS-PCV455A OR 2RCS-PCV455B maintain PRZR pressure controller output pushbuttons to control PRZR 2235 psig (+/- 25 psig). pressure 2235 psig (+/- 25 psig).

EV ALU ATOR CUE: At Evaluators discretion, inform candidate that RCS pressure is at 2235 psig, and to control pressure within+/- 25 psig.

COMMENTS:

13. Refers to 20M-53C.4.2.4.l, 13.1 References Part B for PRZR Pressure Process Control Process Control Failure. Failure.

13 .2 Verifies AOP-2.4.1 Part B IO As.

COMMENTS:

EVALUATOR CUE: When PRZR pressure is under control, or at the Evaluators discretion, state "This JPM is complete".

.....*.J*,. ,:.; ,*

i STOP TIME: _ _ _ _ _ __

BVPS-TR-0026 Page 1 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-044 JPM TITLE: Fill SIS Accumulator A JPM REVISION: 7 KlA

REFERENCE:

006 Al.13 3.5/3.7 TASK ID: 0111-059-04-013 0111-060-01-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D SRO ONLY D ALTERNATEPATHJPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[2J Perform D Plant Site D Annual Requal Exam D BVT D Simulate [2J Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP#:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page2of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Accumulator "A" level restored to clear the low pressure alarm.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS: Excessive sampling has caused a lower than desired level and a low pressure alarm on "A" SI Accumulator.

INITIATING CUE: The Unit Supervisor directs you to fill 2SIS*TK21A to clear the low pressure alarm by using 20M-1 l.4.D steps IV.A.9 through 18. 2SIS-41 is being continuously manned. You are responsible for all alarms on Annunciator panel A 1.

REFERENCES:

20M-11.4.D, Makeup To A Safety Injection Accumulator, Rev. 26 TOOLS: None HANDOUT: 20M-11.4.D, Makeup To A Safety Injection Accumulator, Rev. 26

BVPS-TR-0026 Page 3 of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-044 JPM TITLE: Fill SIS Accumulator A JPM REVISION: 7 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT =>

SIMULATOR SETUP: Start with any Mode 1 thru 3 IC, lower "A" Accumulator level and pressure until Al-4A alarms due to low pressure. Open 2SIS-38 and 2SIS-41, Turn on Hydro Test Pump breaker DC, freeze and SNAP.

LOA-LOV065 LOA-SIS002 Open 2SIS-38 LOA-SIS003 Open 2SIS-41 EVALUATOR NOTE: Provide copy of20M-11.4.D marked complete to step 9.

START TIME: - - - - - - -

1. Reviews copy of procedure 1.1 Reviews procedure 20M-11.4.D.

COMMENTS:

EVALUATOR NOTE:

When 2SIS*MOV851A, is open in modes 1, 2 or 3 (RCS pressure above 1000 psig), the accumulator shall be declared inoperable per TS 3 .5 .1.

2. Informs Shift Manager of 2.1 Informs Shift Manager that 'A' SI Accumulator will inoperable SI Accumulator. be inoperable per TS 3.5.1 when 2SIS*MOV851A is OPEN.

EVALUATOR CUE: Inform candidate that the SM/US will refer to the Technical Specifications.

COMMENTS:

BVPS-TR-0026 Page 4 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-044 JPM TITLE: Fill SIS Accumulator A JPM REVISION: 7 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 3.C Open SI Accumulator Water 3.lC Places CS for 21 A SI Accumulator Water Makeup Makeup Isolation Valve Vlv 2SIS*MOV851A to OPEN.

[2SIS*MOV851A]. (BB-A) 3.2 Verifies RED Light - LIT and GREEN Light - NOT LIT.

COMMENTS:

4. Log starting level and 4.1 Records level (2SIS-LI920/922) and pressure (2SIS-pressure for 2SIS-TK21 A. PI921/923) indicator readings.

EVALUATOR CUE: Inform candidate that logging will be performed by another operator.

COMMENTS:

5. Place [2SIS-SOV94 7] Hydro 5.1 Adjusts (verifies) SI Ace Hydro Test Pump Speed Test Pump speed control Control 2SIS-SOV94 7 controller to zero percent station to zero percent output. output.

(BB-A)

EVALUATOR NOTE: Candidate may request another operator to monitor Hydro Test Pump flow.

Instructor may perform this function.

COMMENTS:

BVPS-TR-0026 Page 5 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-044 JPM TITLE: Fill SIS Accumulator A JPM REVISION: 7 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EVALUATOR CUE:

If asked, inform candidate that Hydro Test Pump prestart checks have been completed.

6.C Start [2SIS-P22], Hydro Test 6.lC Places CS for Hydro Test Pump 2SIS-P22 to the Pump. (BB-A) START position.

/

6.2 Verifies RED Light - LIT and WHITE Light - NOT LIT.

COMMENTS:

7.C Operate [2SIS-SOV94 7] as 7.lC Adjusts SI Ace Hydro Test Pump Speed Control necessary to regulate pump [2SIS-SOV947] controller to greater than 0% output, speed. but less than 50%.

7.2 Verifies flow is less than or equal to 15 gpm on Hydro Test PP Disch Flow 2SIS-F1990.

EVALUATOR NOTE:

Hydro Test PP Disch Flow 2SIS-FI990 is located inside vertical board C. Normally 2 operators are assigned to perform this task.

EVALUATOR CUE:

If necessary, inform the candidate that another operator will monitor the Hydro Test pump while they obtain the Hydro Test PP Disch Flow 2SIS-FI990.

COMMENTS:

BVPS-TR-0026 Page 6 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-044 JPM TITLE: Fill SIS Accumulator A JPM REVISION: 7 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT =>

EVALUATOR CUE: When the Low pressure alarm is clear, as Shift Manager, inform candidate to secure filling the accumulator.

8. Verify venting of 8.1 Verifies 21A Ace Press 2SIS-PI921 and 923 have accumulator is not necessary. remained less than 667 PSIG COMMENTS:

9.C When [2SIS*LI920, 922] 9.1 Verifies "A" Accumulator low pressure alarm, Al-21A Ace Level is 6% to 4A, has reset.

96%, Stop [2SIS-P22],

Hydro Test Pump. 9.2C Places CS Hydro Test Pump 2SIS-P22 to STOP position.

Check [2SIS-P22], Hydro Test Pump, white stop 9.3 Verifies WHITE Light - LIT and RED Light is -

light ON. NOT LIT.

Place [2SIS-P22], Hydro 9.4C Places CS Hydro Test Pump 2SIS-P22 to PTL Test Pump, control position.

switch to PULL-TO-LOCK. EVALUATOR NOTE: Pump has a delayed stop.

EVALUATOR CUE: Ifrequested, another operator will perform the Independent Verification.

COMMENTS:

10. Place [2SIS-SOV947] SI Ace 10.1 Adjusts SI Ace Hydro Test Pump Speed Control Hydro Test Pump, Speed 2SIS-SOV947 controller to zero percent output.

Control to ZERO percent output. COMMENTS:

BVPS-TR-0026 Page 7 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-044 JPM TITLE: Fill SIS Accumulator A JPM REVISION: 7 STEP STANDARD

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

11. Record final level and 11.1 Records level (2SIS-LI920/922) and pressure (2SIS-pressure for the accumulator PI921/923) indicator readings.

being filled in the Narrative Log. EVALUATOR CUE: Inform candidate that logging will be performed by another operator.

COMMENTS:

12.C Close [2SIS*MOV851A], 12.1 Waits at least 30 seconds from securing the Hydro 21A SI Accumulator Water Test Pump prior to closing 2SIS*MOV851A.

Makeup Vlv.

12.2C Places CS for 21A SI Accumulator Water Makeup Vlv 2SIS*MOV851A to CLOSE.

12.3 Verifies GREEN Light-LIT and RED Light-NOT LIT.

EVALUATOR CUE: If requested, another operator will perform the Independent Verification.

COMMENTS:

EVALUATOR CUE: This completes the JPM.

STOP TIME: - - - - - - -

BVPS-TR-0026 Page 1 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation I ATWS JPM REVISION: 1 KIA

REFERENCE:

007 EA2.04 4.4 / 4.6 TASK ID: 0533-001-05-013 JPM APPLICATION: iZ] REQUALIFICATION iZ] INITIAL EXAM O TRAINING 0 SRO ONLY iZ] ALTERNATE PATH JPM O ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

r2:J Perform D Plant Site D Annual Requa! Exam D BVT D Simulate r2:J Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RES UL TS Performer Name: Performer SAP#:

Time D Yes Allotted 15 Minutes Actual minutes Critical: IZl No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STAND ARD: The immediate actions of FR-S. l are completed and verified by procedure. Then alternate emergency boration flowpath is established at > 30 gpm Boric Acid flow, for a minimum of 1000 gallons.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS:

The plant is in the process of shutting down.

Reactor power is approximately 23%.

Control Rods are in Manual.

The Main Generator is on-line.

4KV buses are energized from off-site power.

The steam generators are being fed on the feedwater bypass valves.

A failure of the 2IC bypass feedwater control valve causes 2IC SG level to decrease below the reactor trip setpoint, but no automatic reactor trip occurs.

A manual Rx Trip attempt has also failed.

INITIATING CUE: Your supervisor directs you to perform FR-S. l, Response to Nuclear Power Generation - ATWS.

REFERENCES:

20M-53A.1.FR-S. l, Response to Nuclear Power Generation - A TWS, Issue 2, Revision 0 TOOLS: None HANDOUT: 20M-53A.1.FR-S.1, Response to Nuclear Power Generation - ATWS, Issue 2, Revision 0

BVPS-TR-0026 Page 3 of JO Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation / ATWS JPM REVISION: 1 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)~ S/U SIMULATOR SETUP:

Insert Malf PPLOIA & PPLOIB to fail Rx Trip breakers in auto and manual.

Insert VLV-CFW039A to zero to fail closed 2FWS-FCV499.

Insert failure EHC08B to fail the turbine trip PB's.

Set CB 'C' group counter at 168 steps to trip Rx.

TRG 4 = 'MCRFNS(37) <=168' DMF PPLOlA TRG 5 = 'MCRFNS(38) <=168' DMF PPLOlB Insert VLV-BAT014 to 2 to fail closed 2CHS-MOV350.

Allow simulator to run until LoLo level in 21 C S/G.

Freeze simulator and Snap IC.

EVALUATOR NOTE: Allow the candidate to perform the Immediate Operator Actions from memory, then evaluate the actions as the steps are verified by procedure.

START TIME: - - - - - - -

FAULT STATEMENT:

Turbine will not trip via the turbine trip pushbuttons.

l .C Manually trip the turbine. 1.1 Depresses both Main Turbine Trip push buttons, and recognizes that the turbine fails to trip.

l .2C Depresses the DOWN pushbutton for the Valve Position Limiter and verifies all 4 Governor Valves CLOSE.

OR Manually initiates Steam Line Isolation by depressing the Main Stm Line Isol Actuation Train A ORB pushbuttons and verifies the MSLI Valves CLOSE.

COMMENTS:

BVPS-TR-0026 Page 4 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation/ ATWS JPM REVISION: 1 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT):::> SIU EVALUATOR NOTE: When CB 'C' group counter indicates 168 steps, the reactor will trip.

2.C Insert control rods. 2.1 C Manually inserts control rods to lower reactor power.

OR Places the control rods to AUTO and monitors the control rods inserting.

EVALUATOR NOTE: If rods are taken to Auto for rod insertion, they may have to place rod control back to manual to continue inserting due to Tavg-Tref deviation.

COMMENTS:

3. Locates the FR-S.1 3.1 Locates the FR-S.l procedure.

procedure.

3.2 Verifies the appropriate immediate operator actions were taken in accordance with step 1.

COMMENTS:

BVPS-TR-0026 Page 5 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation/ ATWS JPM REVISION: 1 STEP STANDARD

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

4. Verify AFW Status 4.1 Checks 2FWE-23A and B both RUNNING, RED lights - LIT, GREEN lights - NOT LIT.

Motor-driven AFW Pumps - RUNNING 4.2 Checks 2MSS*SOVI05A-F OPEN,

Turb Driven AFW Pump RED lights - LIT, GREEN lights - NOT LIT.

Stm Supply Isol Valves -

OPEN 4.3 Checks 2FWE*HCV100A-F OPEN,

AFW Throttle Valves -

RED lights- LIT, GREEN lights- NOT LIT.

FULL OPEN COMMENTS:

5. Initiate Emergency Boration 5.1 Checks 2CHS-P21A or 2CHS-P21B RUNNING, OfRCS RED light - LIT, GREEN light - NOT LIT.

Verify Charging Pumps -

5.2 Recognizes that Safety Injection has not actuated by AT LEAST ONE observing Annunciator A12-1D NOT LIT. Other RUNNING available indications are permissible to use.

Check Safety Injection -

ACTUATED 5.3 Goes to Step 3.e based on the RNO.

COMMENTS:

BVPS-TR-0026 Page 6 of I 0 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation/ ATWS JPM REVISION: 1 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)::> S/U FAULT STATEMENT:

In the next step 2CHS*MOV350 will fail to open requiring the alternate emergency boration flowpath to be established.

6. Align boration path: 6.1 Places control switch for 2CHS*MOV350 to OPEN, GREEN light - LIT, RED light - NOT LIT.

Open [2CHS*MOV350)

Start in-service boric acid 6.2 Recognizes the failure to open, and performs RNO transfer pump.

steps for establishing alternate emergency boration.

Verify Emergency Boration Flow -

COMMENTS:

GREATER THAN 30 GPM 7.C Establish alternate 7 .1 C Places control switch for 2CHS *SOV206 to OPEN.

emergency boration path.

7.2 Verifies RED light - LIT, GREEN light - NOT LIT.

Open [2CHS*SOV206]

COMMENTS:

8.C Place the makeup Mode 8.1 C Places the Mode Selector Switch to BORA TE.

Selector to BORA TE.

COMMENTS:

BVPS-TR-0026 Page 7 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation I ATWS JPM REVISION: 1 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT):::::> S/U 9.C Adjust [2CHS*FCVI 13A] to 9.IC Adjusts 2CHS*FCVI 13A to >30 gpm, >750 units.

a rate of greater than 30 GPM. COMMENTS:

10.C Set Boric Acid Flow to 10.1 C Adjusts 2CHS-FQIS 113 Boric Acid Flow to > 1000 Blender Flow Totalizer to gallons. (GREEN LED) greater than I 000 GALLONS. 10.2C Depresses "RESET" on 2CHS-FQIS113.

Reset [2CHS-FQIS 113]. COMMENTS:

11. Verify the in-service boric 11.1 Verifies 2CHS-P22A is in AUTO.

acid transfer pump is in AUTO. 11.2 Control switch has GREEN Target, and GREEN light- LIT COMMENTS:

12.C Place the Boric Acid Makeup 12.1 C Places Boric Acid Makeup Blender Control switch to Blender Control to START. START.

12.2 Verifies 2CHS-P22A starts, RED light - LIT and GREEN light - NOT LIT.

COMMENTS:

BVPS-TR-0026 Page 8 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation / ATWS JPM REVISION: 1 STEP STANDARD

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

13. Verify [2CHS-FCV113A] 13.1 Verifies 2CHS-FCV113A OPEN.

opens.

13.2 RED light - LIT and GREEN light - NOT LIT.

COMMENTS:

14. Verify [2CHS-FR113] Boric 14.1 Observes 2CHS-FR113 to verify >30 gpm Boric Acid Acid To Blender Total MIU flow.

Flow from Blender -

GREATERTHAN30GPM COMMENTS:

15.C Align charging flow path: 15.lC Adjust 2CHS*FCV122 by placing in MANUAL, RED MAN light - LIT and RED AUTO light - NOT

Adjust [2CHS*FCV122]

LIT.

to establish Charging Flow

- OREA TER THAN 40 15.2C Depresses T OUTPUT push button until flow is >40 GPM gpm as indicated on 2CHS-FI122A or PCS.

COMMENTS:

16. Check PRZR pressure - 16.1 Checks PRZR pressure is < 2330 psig on 2RCS-LESS THAN 2330 PSIG PI455, 456,457, or PCS.

COMMENTS:

BVPS-TR-0026 Page 9 of 10 Revision 0 OPERATIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation / ATWS JPM REVISION: 1 STEP STANDARD

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

17. Alert Plant Personnel 17.1 Sounds standby alarm and makes plant announcement.

Sound the standby alarm.

Announce the Unit 2 17.2 N/A's step to open Rx Trip and Output breakers due reactor trip without a to Rx previously tripping.

SCRAM.

Locally trip reactor (Rod COMMENTS:

Control Bldg - 755')

Open reactor trip breakers

Open rod drive MG sets output breakers

18. Verify Turbine Trip And 18.1 Verifies Turbine is tripped by all Turbine Throttle and Reheat Steam Isolation Governor valves CLOSED. GREEN lights - LIT and RED lights - NOT LIT. -

Turbine - TRIPPED

Verify [2MSS 18.2 Verifies 2MSS MOVlOOA,B CLOSED by checking MOVlOOA,B] CLOSED GREEN lights -LIT and RED lights - NOT LIT.

Reset reheater controller.

18.3 Depresses reheater controller RESET pushbutton, and verifies RED pushbutton light - LIT.

COMMENTS:

19. Check SI Signal Status 19.1 Recognizes that Safety Injection has not actuated by observing Annunciator Al2-1D NOT LIT. Other

Safety Injection -

available indications are permissible to use.

ACTUATED

Check if the first nine COMMENTS:

steps of E-0, "Reactor Trip Or Safety Injection", have been performed.

BVPS-TR-0026 Page 10 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-542 JPM TITLE: Nuclear Power Generation/ ATWS JPM REVISION: 1 STEP STANDARD

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

20. Check If Reactor Is 20.1 Checks Power Range NI channels are <5 %.

Subcritical 20.2 Checks negative SUR on 2NMI-NI35D/36D.

Power range channels -

LESS THAN 5%

20.3 Informs Unit Supervisor that steps of FR-S.1 are

Intermediate range complete, and recommends returning to E-0.

channels - NEGATIVE STARTUP RATE COMMENTS:

Continue boration, as necessary, to obtain adequate shutdown margin during subsequent actions.

RETURN TO procedure and step in effect.

EV ALU ATOR CUE: After candidate recommends returning to procedure and step in effect, or at the discretion of the evaluator, state "This JPM is complete".

STOP TIME:

BVPS-TR-0026 Page 1 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-136 .

JPM REVISION: 2 JPM TITLE: Swap RHS Trams KIA

REFERENCE:

025 AAl.01 3.6/3.7 TASK ID: 0101-008-01-043 JPM APPLICATION: ~ REQUALIFICA TION ~ INITIAL EXAM O TRAINING D SRO ONLY 0 ALTERNATE PATH JPM 0 ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[SJ Perform D Plant Site D Annual Requa! Exam D BVT D Simulate [SJ Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RES UL TS Performer Name: Performer SAP:

Time D Yes Allotted 30 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SAP: Name/SAP:

Name/SAP: Name/SAP:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: RHS Train B is in service and RHS Train A is in standby.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS:

The plant is in Mode 4

RHS Train 'A' is in service providing RCS cooling

RHS Train 'B' is in standby

Both Pumps and Trains are Filled & Vented

All P&L's and initial conditions are met

20ST-I0.4 has been completed INITIATING CUE: Your supervisor directs you to place the 'B' train of RHS in service IAW 20M-10.4.B, Residual Heat Removal System Running step IV.D, and then place the' A' train of RHS in standby IA W step IV.E.

REFERENCES:

20M-I0.4.B, Residual Heat Removal System Running, Rev. 33 TOOLS: None HANDOUT: 20M-10.4.B, Residual Heat Removal System Running, Rev. 33

BVPS-TR-0026 Page 3 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-136 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT => SIU SIMULATOR SETUP:

Start with IC-24 Place/remove caution tags as needed.

Shutdown 'B' Train RHS and place in standby IAW 20M-10.4.B Part F.

Stabilize plant with slight CID and snap IC.

EVALUATOR NOTE: Provide candidate a copy of 20M-10.4.B. Place simulator in run when candidate is ready to begin.

START TIME: - - - - - - -

1. Reviews 20M-10.4.B. 1.1 Reviews Section D, "To Place RHS Train B in Service from a Standby Condition".

EVALUATOR CUE: If asked, inform the candidate that ASME valve testing is not required. RHS Train B has been filled and vented, and 20ST-I0.4 has been completed per the initial conditions.

COMMENTS:

2. Verify CCP is greater than 2.1 Checks temperature on 2CCP-TI100A(lOOB)(lOOC) 50F on (2CCP- >50°F.

Tll OOA(l OOB)( 1OOC)],

[2CCP-P21A(2IB)(21C)] Pri COMMENTS:

Comp Cooling Hx Disch Temp, Vertical Board-Section C, for the inservice CCP Hxs.

BVPS-TR-0026 Page 4 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-I36 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

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

3. If RCS temperature> 120F, 3.1 Determines RCS/RHS temperature> 120F.

Open [2CCP*MOV112B]

RHR PP Seal Clr 22B and 3.2 Verifies 2CCP*MOV1128 is OPEN, Hx 21B. RED light - LIT and GREEN light - NOT LIT.

COMMENTS:

4.C Align RHS valves. 4.1 Verifies 2RHS*MOV701B OPEN, RED light - LIT and GREEN light - NOT LIT.

4.2 Verifies 2RHS*MOV702B OPEN, RED light- LIT and GREEN light- NOT LIT.

4.3C CLOSES 2RHS*FCV605B by verifying controller is in MAN, and depressing T output pushbutton until demand is at zero.

4.4 Verifies 2CHS*HCV142 OPEN, demand not at zero.

EVALUATOR CUE: Role play Unit Supervisor and direct that 2CHS*HCV142 be left at current position.

4.5 Verifies 2RHS*MOV750B CLOSED, GREEN light- LIT and RED light- NOT LIT.

4.6C CLOSES 2RHS*HCV758B by depressing .6. output pushbutton until demand is at 100%.

4.7 Verifies 2RHS*MOV720B OPEN, RED light - LIT and GREEN light- NOT LIT.

COMMENTS:

BVPS-TR-0026 Page 5 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-136 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

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

5. Monitor RHS 21 B HX Inlet 5.1 Monitors RHR Hx DiffTemp on 2RHS*TR604B temperature using one of the and/or (T0630A).

following:

EVALU ATOR NOTE: Candidate may use computer

[2RHS*TR604B], RHR PIO to determine differential temperature. Computer Hx Diff Temp recorder (inlet) (VB-A) point (T0630A) is only the heat exchanger inlet temperature.

T0630A, RHR HX 21B INLET TEMP COMMENTS:

6. If desired, Vent 6.1 Determines step is N/A based on Initial Conditions.

[2RHS*P21B] RHR Pump using Attachment 1. EVALUATOR NOTE: Initial Conditions state both (Otherwise NIA) pumps are filled & vented.

COMMENTS:

7. If containment is at 7.1 Determines containment is NOT at atmospheric atmospheric pressure AND pressure by observing 2LMS-PI950, 951, 952, 953, or the dose rate in the area is the PCS.

acceptable, Monitor the 21 B RHR pump seal for leakage 7.2 Marks step as NIA.

during the pump start.

(Otherwise NIA) COMMENTS:

BVPS-TR-0026 Page 6 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-136 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 8.C When the RCS and RHS 8.1 Verifies RCS and RHS temperature indications on temperature differential is ::S PCS or recorders that temperature differential is ::S 50 50°F OR the rate ofRHS °F or RHS temperature rate of increase is < 5 °F/Hr.

temperature increase is< 5°F per hour (< 1°F/12 mins. ), EVALUATOR NOTE: Candidate may have THEN Start [2RHS*P21B] previously verified temperature is within limits.

RHR Pump from Benchboard Section A. 8.2C Places 2RHS*P21B Control Switch to START.

8.3 Verifies RED light - LIT and WHITE light - NOT LIT.

8.4 Verifies amps increasing on 2RHS-I21 B.

COMMENTS:

9. If required, Maintain PRZR 9 .1 Verifies PRZR pressure is between 275 and 350 psig pressure control between 275 by observing 2RCS-PI440, 441, 2RCS-PR441, or and 350 psig by any or all of PCS.

the following methods while performing the following 9.2 Marks step as NIA.

steps: (otherwise NIA)

COMMENTS:

Adjust [2CHS*PCV145]

Adjust [2CHS*FCV122]

Adjust [2CHS*HCVI 86]

1O.C Slowly Throttle 10.1 C Throttles 2RHS *FCV 605B OPEN by verifying

[2RHS*FCV605B], 21B controller is in MAN, and depressing

output RHR Hx Bypass Viv, not to pushbutton until a flowrate of< 3500 GPM is exceed 3500 gpm flow indicated on 2RHS*FI605B OR PCS.

indicated on

[2RHS *FI605B]. COMMENTS:

BVPS-TR-0026 Page 7 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-136 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

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

11. Verify [2RHS*HCV758B] 11.1 Verifies 2RHS*FCV605B controller is in MAN by partially strokes to RED MAN light - LIT.

demonstrate heat removal capability prior to using 11.2 Records RHS flow from 2RHS-FI605B or Computer Train B for core cooling: Point F0627 A indication in gallons per minute.

11.3 Depresses 2RHS*FCV758B controller output T pushbutton to increase flow by 100 to 200 gpm.

11.4 Depresses 2RHS*FCV758B controller output A pushbutton to return flow to the previously recorded value.

COMMENTS:

EVALUATOR CUE:

Role-play the Unit Supervisor and inform the candidate that it is NOT desired to raise RHS flow.

12. If desired to raise RHS flow, 12.1 Marks step as NIA.

Slowly throttle

[2RHS*FCV605B] not to COMMENTS:

exceed 4000 gpm flow indicated on

[2RHS*FI605B]. (Otherwise NIA)

Transfer [2RHS*FCV605B],

21 B RHR Hx Bypass Vlv to automatic flow control.

BVPS-TR-0026 Page 8 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-l 36 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

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

13. lfRCS temperature< 120F 13.1 This step is NIA due to RCS temperature> 120F.

AND CCP is not supplied to the RHR pump seal cooler, COMMENTS:

Perform the following:

(otherwise NIA)

14. Throttle 14.1 Throttles 2RHS*HCV758B to maintain RCS

[2RHS*HCV758A(758B)], temperature by using output pushbuttons maintain 21A (21B) RHR Hx Flow RCS temperature stable at its current value.

Control Vlv to maintain the desired rate of cooldown or EVALUATOR CUE: You are to maintain RCS to hold the RCS at a constant temperature stable at its current value.

temperature.

COMMENTS:

15. Verify 15.1 Verify 2RHS*FCV605A/605B modulate in AUTO to

[2RHS*FCV605A(605B)] maintain RHS flow on 2RHS*FI605A/ B.

21A(B) RHR Hx Bypass automatically controls RHS COMMENTS:

flow when in AUTO.

BVPS-TR-0026 Page 9 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-136 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EVALUATOR CUE: Role play Unit Supervisor and direct to opening of 2RHS*MOV750B.

16. If desired, Open 16.l Places 2RHS*MOV750B Control Switch to OPEN.

[2RHS*MOV750B] RHS Train B Cross Conn Viv. 16.2 Verifies RED light - LIT and GREEN light - NOT (otherwise NIA) LIT.

EVALU ATOR CUE: This section of the procedure is completed and routed as required. You are now to place RHS Train 'A' in standby.

COMMENTS:

17. Reviews procedure 17.1 Transitions to procedure Section E, to place RHS Section E. Train' A' in standby.

COMMENTS:

EVALUATOR CUE: If requested, role play US and state that it is desired to have 2RHS*MOV750B open.

18. IF desired, Verify Open 18.1 Verifies 2RHS*MOV750B OPEN

[2RHS*MOV750B], RHS RED light - LIT and GREEN light - NOT LIT.

Train B Cross Connect Vlv (Otherwise NIA). COMMENTS:

BVPS-TR-0026 Page JO of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-136 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ S/U 19.C Verify Closed 19.1 C Places 2RHS*MOV750A Control Switch to

[2RHS*MOV750A], RHS CLOSED.

Train A Cross Connect Vlv.

19.2 Verifies GREEN light- LIT and RED light- NOT LIT.

COMMENTS:

20.C Verify stopped 20.IC Places 2RHS*P21A Control Switch to STOP.

[2RHS*P21A] RHR Pump.

20.2 Verifies WHITE light- LIT and RED light- NOT LIT.

COMMENTS:

21. If [2RHS*MOV720A], 21A 21.1 This Step is NIA.

RHR Return Isol Vlv is caution tagged for low boron COMMENTS:

concentration in accordance with 20M-10.4.A, then remove the caution tag.

22. Verify open 22.1 Verifies 2RHS*MOV720A OPEN,

[2RHS*MOV720A] 21A RED light - LIT and GREEN light - NOT LIT.

RHR Hx Return Isol Viv.

COMMENTS:

BVPS-TR-0026 Page 11 of 11 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-l 36 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

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

23. Open [2RHS*FCV605A] 23.1 OPENS 2RHS*FCV605B by verifying controller is in RHR Hx Bypass Viv. MAN, and depressing

output pushbutton.

COMMENTS:

24. Throttle [2RHS*HCV758A] 24.1 Throttles 2RHS*HCV758A by depressing the 21 A RHR Hx Flow Control controller output * 'f' pushbuttons until the valve Viv to 35% valve position position indication is at 35%.

indication.

COMMENTS:

EVALUATOR CUE: If needed, report RHR hx Diff Temp, on 2RHS*TR604A is< 120F.

25. Allow CCP flow to continue 25.1 Places 2CCP*MOV112A Control Switch to through [2RHS*E21A] RHR CLOSED.

Hx until :S l 20F on

[2RHS*TR604A] RHR hx 25.2 Verifies GREEN light- LIT and RED light- NOT DiffTemp, THEN Close LIT.

[2CCP*MOV112A] RHR PP Seal Cir 22A and Hx 21 A COMMENTS:

cooling Water Inlet Viv.

EVALUATOR CUE: When candidate has temperature and flow controlled, state "This JPM is COMPLETE."

STOP TIME: - - - - - - -

BVPS-TR-0026 Page I of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 2 Test KIA

REFERENCE:

008 A4.01 3.3/3.1 TASK ID: 0151-012-01-012 JPM APPLICATION: lZJ REQUALIFICATION lZJ INITIAL EXAM O TRAINING D SRO ONL y D AL TERNATE PATH JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D Annual Requa! Exam D BVT D Simulate ~ Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RES UL TS Performer Name: Performer SAP#:

Time D Yes Allotted 15 Minutes Actual minutes Critical: lZI No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EV ALU ATOR DIRECTION SHEET TASK STANDARD: Transfer 2CCP*DCV 100-1 and 100-2 between automatic and manual operation without invalidating test data. Determine acceptance criteria is met> .98 for reverse flow test of 2CCP*4, "21A Discharge Check Valve." Restore 2CCP*P21A operability.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS: The plant is in Mode 3 on hold to perform a reactor startup.

[2CCP*P21B] is running and [2CCP*P21A] is in standby. (BOTH Pumps are OPERABLE)

All test preparations for 20ST- l 5 .1, Primary Component Cooling Water Pump [2CCP*P21A] Test are completed, and the procedure is signed ready to begin at Step VII.B. l.

An NLO has been briefed and is standing by to support this OST.

INITIATING CUE: The Unit Supervisor directs you to perform 20ST-15.l, steps VII.B.1 through 3, and determine if acceptance criteria in Step VII.B.3.j is met.

REFERENCES:

20ST-15.l, "Primary Component Cooling Water Pump [2CCP*P21A]

Test", Rev. 58 TOOLS: None HANDOUT: 20ST-15.l, "Primary Component Cooling Water Pump [2CCP*P21A]

Test", Rev. 58, place kept up to step VII.B. l.

BVPS-TR-0026 Page 3 of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 2 Test STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU SIMULATOR SETUP:

Select any Mode 3 steady state IC.

Ensure 2CCP*P21B is in operation and 2CCP*P21A is in standby.

Verify 2CCP*DCV100-1 and 100-2 in AUTO.

EVALUATOR NOTE:

After providing a marked up copy of20ST-15. l, when candidate is ready to begin, place the simulator in RUN.

START TIME: - - - - - - - -

1. Reviews procedure. 1.1 Candidate reviews 20ST-15.1.

COMMENTS:

2. Verify [2CCP*P21A], 2.1 Requests NLO to verify 2CCP*P21A bearing oil "Component Cooling Water level NORMAL on local constant level oiler.

Pump" bearing oil level is normal on local constant EVALUATOR CUE: Role play NLO and report level oiler. 2CCP*P21 A local bearing oil level is NORMAL.

COMMENTS:

BVPS-TR-0026 Page 4 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 2 Test STEP STANDARD

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

3. If [2CCP*P2 l A], Pri Comp 3.1 Recognizes 2CCP*P21A is in standby and requests Clg Wtr P21A, is in standby, NLO to report 2CCP-Pll 50A - local suction pressure Record [2CCP-PI150A], reading.

"Primary Component Cooling Water local suction EVALUATOR CUE: The NLO reports 2CCP-pressure. Pll 50A is reading 19 .4 psig.

3.2 Records 2CCP-Pll 50A in step VII.B.2.

COMMENTS:

4. If [2CCP*P21A], Pri Comp 4.1 Records 2CCP-PI145B pressure in step VII.B.3.a Clg Wtr P21A, is in standby AND another CCP pump is 4.2 N/A's 2CCP-PI145C pressure in step VII.B.3.a operating, Verify [2CCP*4], (pump is not running).

"Component Cooling Water Pump 21A Disch Check Vlv" COMMENTS:

CLOSED as follows:

Record operating CCP Pump discharge pressure( s).

(NI A IF NOT operating)

[2CCP-PI145B],

"21 B CCP Pump Disch Press - PSIG

[2CCP-PI145C],

"21 C CCP Pump Disch Press - PSIG

BVPS-TR-0026 Page 5 of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 2 Test STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U 5.C Verify [2CCP*DCVI00-1 5.lC Places 2CCP*DCV100-1 in MAN by depressing AND 2CCP-DCV100-2] , MAN pushbutton.

"Pri Comp Cooling Pump Recirc Vlvs" are in MAN. 5.2 Verifies RED MAN light - LIT and RED AUTO light

-NOT LIT.

5.3C Places 2CCP*DCV100-2 in MAN by depressing MAN pushbutton.

5.4 Verifies RED MAN light- LIT and RED AUTO light

-NOT LIT.

5.5C Does NOT operate 2CCP*DCV100-1 or 100-2 while in MANUAL until pressure data is recorded in procedure step VII.B.3.e.

EVAULATOR NOTE: If 2CCP*DCVI00-1 or 100-2 are operated in MANUAL prior to recording pressures in step VII.B.3.e, this will invalidate the data and will be considered UNSAT.

COMMENTS:

BVPS-TR-0026 Page6of9 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-l 57 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 2 Test STEP STANDARD

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

6. If in MOD Es 1-4, perform 6.1 Determines Mode 3 applies and either directs an either of the following: operator stationed at 2CCP*7 with specific instructions to open 2CCP*7 if directed by control

Station an operator at room staff OR make a narrative log entry that

[2CCP*7], "Component 2CCP*P21 A is to be declared unavailable for Cooling Pump P21A documentation of Maintenance Rule Unavailability.

Disch Isol." with specific instructions to open EVALUATOR CUE: Role play either the NLO or

[2CCP*7] if directed by SM/US based on which choice is taken by the control room staff. candidate and acknowledge the request.

OR COMMENTS:

Record date and time below AND in narrative log that 2CCP*P21A is to be declared unavailable for documentation of Maintenance Rule Unavailability.

7.C Close [2CCP*7], "Component 7.lC Directs the NLO stationed in the Aux Building to Cooling Pump P21 A Disch CLOSE 2CCP*7.

Isol.".

EVALUATOR NOTE: 2CCP*7 is not modeled therefore 2CCP* 151 will be closed. Coordinate with the simulator operator and CLOSE 2CCP* 151 by selecting Primary Component Cooling Water Drawing (CCP2), clicking on 2CCP* 151, Enter O into remote value with a 10 second ramp time and ensure 2CCP* 151 CLOSES.

EVALU ATOR CUE: Once valve is closed, Role Play the NLO and report 2CCP*7 is CLOSED.

COMMENTS:

BVPS-TR-0026 Page 7 of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 2 Test STEP STANDARD

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

8. Record operating CCP Pump 8.1 Records 2CCP-PI145B pressure in Step VII.B.3.e.

discharge pressures. (N/A IF NOT operating) 8.2 N/A's 2CCP-PI145C pressure in Step VII.B.3.e.

(Pump is NOT operating).

[2CCP-PI145B], 21 B CCP COMMENTS:

Pump Disch Press _

PSIG

[2CCP-PI145C], 21C CCP Pump Disch Press _

PSIG 9.C Open [2CCP*7], "Component 9.lC Directs the NLO stationed in the Aux Building to Cooling Pump P21 A Disch OPEN 2CCP*7.

Isol.".

EV ALU ATOR NOTE: Coordinate with the simulator operator and REOPEN 2CCP* 151 by clicking on 2CCP* 151. Enter 1 into remote value with a 10 second ramp time and ensure 2CCP* 151.

EVALUATOR CUE: Once valve is opened, Role Play the NLO and report 2CCP*7 is OPEN.

COMMENTS:

BVPS-TR-0026 Page 8 of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 2 Test STEP STANDARD

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

10. IF [2CCP*P21A] was 10.1 If 2CCP*P21 A was declared unavailable in previous declared unavailable in Step step AND IF desired to return pump to "available",

VII.B.3.c AND IF desired to record date and time below in the Narrative Log AND return pump to "available", declare 2CCP*P21A available for operation. IfNOT record date and time below in applicable, mark step NI A.

the Narrative Log AND declare [2CCP*P21 A] EVALUATOR CUE: If applicable, it is desirable to available for operation. return 2CCP*P21A to available status. Narrative Log entries will be made.

COMMENTS:

EVALUATOR CUE: It is NOT desirable to maintain 2CCP*DCV100-1 and 100-2 in MANUAL.

11. IF manual operation of 11.1 This step will be marked NI A

[2CCP*DCV100-1 AND 100-2] is desired, adjust valves as COMMENTS:

necessary UNTIL [2CCP-DI100-1 AND 2] indicate 93 to 97 psid. '

12.C IF automatic operation of 12.lC Places 2CCP*DCV100-1 in AUTO by depressing

[2CCP*DCV100-1 and 100-2] AUTO pushbutton.

is desired, place valves in AUTO. 12.2 Verifies RED AUTO light- LIT and RED MAN light

-NOT LIT.

12.3C Places 2CCP*DCV100-2 in AUTO by depressing AUTO pushbutton.

12.4 Verifies RED AUTO light- LIT and RED MAN light

-NOT LIT.

COMMENTS:

BVPS-TR-0026 Page 9 of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 2 Test STEP STANDARD

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

13. C Calculate the ratio between 13 .1 C Calculates the ratio between operating pump operating pump discharge discharge pressure with standby pump discharge pressure with standby pump valve closed and open as follows:

discharge valve closed and open RA TIO= Indicated press with 2CCP*7 open (step VII.B.3.a)

Indicated press with 2CCP*7 shut (step VII.B.3.e) 13.2C Determines that the ratio for 2CCP*P21B is >.98 acceptance criteria and records ratio in step VII.B.3.j.

13.3 N/A's ratio for 2CCP*P21C.

13.4 Requests a second check for acceptance criteria.

COMMENTS:

14. Verify 2CCP*P21A pump 14.1 Requests on station NLO to verify 2CCP*P21 A shaft is NOT rotating pump shaft is NOT rotating backwards.

backwards.

EV ALU ATOR CUE: Field operator reports that 2CCP*P21A pump is NOT rotating backwards.

COMMENTS:

TERMINATING CUE: Upon calculating acceptance criteria and after getting field report of pump status, inform the candidate, "This JPM is COMPLETE".

STOP TIME: - - - - - - - -

BVPS-TR-0026 Page I of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM TITLE: Containment Spray Manual Actuation - QSS Pump and JPM REVISION: 0 CCP Valve Malfunctions Kl A

REFERENCE:

026 A2.03 4.1/4.4 TASK ID: 0011-066-01-013 026 A2.04 3.9/4.2 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D SROONLY ~ ALTERNATE PATH JPM O ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perfonn D Plant Site D Annual Requa) Exam D BVT D Simulate C8J Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP#:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Manually initiate CIB, start 2QSS*P21B, close 2CCP-MOV151-1 and 2CCP-MOV151-2, and stop the RCP's.

RECOMMENDED Simulator STARTING LOCATION:

INITIAL CONDITIONS:

A reactor trip and safety injection have occurred due to a large break LOCA.

The actions of E-0 are being performed.

INITIATING CUE: The Unit Supervisor directs you to perform Attachment A-0.11, Verification of Automatic Actions, Step 9 to check CIB and Containment Spray status.

REFERENCES:

20M-53A.1.A-0.11, Verification of Automatic Actions, Rev. 9 20M-53A.1.A-0.5, Containment Isolation Phase B Checklist, Rev. 3 TOOLS: None HANDOUT: 20M-53A.1.A-O.l 1, Verification of Automatic Actions, Rev. 9 20M-53A. l .A-0.5, Containment Isolation Phase B Checklist, Rev. 3

BVPS-TR-0026 Page 3 of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM TITLE: Containment Spray Manual Actuation - QSS Pump and JPM REVISION: 0 CCP Valve Malfunctions STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU SIMULATOR SETUP:

Insert MALF RCS03A (Large break LOCA)

Insert MALF PPL07B = 6-7 (for 2QSS-P2 l B)

Fail auto CIB from actuating.

Fail open 2CCP-MOV151-1 Fail open 2CCP-MOV151-2 EVALUATOR CUE: When the candidate is ready to begin the JPM, place the simulator to RUN.

START TIME: - - - - - - -

1. Reviews procedure. 1.1 Reviews 20M-53A.1.A-O. l l, Verification of Automatic Actions.

COMMENTS:

BVPS-TR-0026 Page 4 of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM TITLE: Containment Spray Manual Actuation - QSS Pump and JPM REVISION: 0 CCP Valve Malfunctions STEP STANDARD

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

2. Containment pressure - HAS 2.1 Determines that containment pressure has NOT REMAINED LESS THAN remained less than 11 psig by checking any of the 11 PSIG. following:

Al-2H, "CONTAINMENT ISOLATION PHASE B" in alarm.

2LMS*PR950, Containment Pressure Recorder indicates greater than 11 psig.

Panel 464, High 3 CHM 1 Pressure CH I - IV Lights - LIT.

2LMS-PI950, 951, 952, and 953 indicate greater than 11 psig.

COMMENTS:

EVALUATOR NOTE: It is acceptable that the candidate completes this step out of order and may choose to perform 20M-53A. l .A-0.5, "Containment Isolation Phase B Checklist".

3. Check BLUE CIB marks - 3.1 Checks components properly aligned and determines LIT. CIB components not positioned as required, and CIB NOT actuated.

COMMENTS:

B VPS-TR-0026 Page 5 of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM TITLE: Containment Spray Manual Actuation - QSS Pump and JPM REVISION: 0 CCP Valve Malfunctions STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU EV ALU ATOR NOTE: Either train may be actuated first followed by the opposite train.

4. IF NOT, THEN manually 4.1 C Simultaneously ROTATES (Clockwise) both Train initiate CIB (both switches "A" CIB switches to ACTUATE position.

for both trains).

4.2C Simultaneously ROTATES (Clockwise) both Train "B" CIB switches to ACTUATE position.

COMMENTS:

FAULT STATEMENT:

2QSS*P21B failed to start, and 2CCP-MOV151-1 and 2CCP-MOV151-2 failed to close.

5. Check BLUE CIB marks - 5.1 Candidate checks all indicating lights with BLUE LIT. CIB marks LIT.

5.2 Determines that 2QSS*P21B failed to start, and 2CCP-MOV151-1 and 2CCP-MOV151-2 failed to close.

EVALUATOR NOTE: If requested, provide Candidate a copy of Attachment A-0.5.

COMMENTS:

BVPS-TR-0026 Page 6 of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-new JPM TITLE: Containment Spray Manual Actuation - QSS Pump and JPM REVISION: 0 CCP Valve Malfunctions STEP STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT => S/U 6.C IF CIB NOT actuated, THEN 6.1 C Places 2QSS *P2 l B control switch in START.

manually align equipment. If necessary, refer to 6.2 Verifies RED light- LIT and WHITE light- NOT Attachment A-0.5, LIT, and pump amps indicate on 2QSS-1121B.

"Containment Isolation Phase B Checklist". 6.3C Places 2CCP-MOV151-l control switch to CLOSE.

6.4 Verifies GREEN light- LIT and RED light- NOT LIT.

6.5C Places 2CCP-MOV151-2 control switch to CLOSE 6.6 Verifies GREEN light- LIT and RED light - NOT LIT.

COMMENTS:

7.C Stop all RCP's. 7.lC Places control switches for 2RCS*P21A, 21B and 21C to STOP.

7.2 Verifies WHITE lights - LIT and RED lights - NOT LIT for 2RCS*P21A, 21B and 21C.

7.3 Verifies 2RCS-FI414 (415)(416); 2RCS-FI424 (425)( 426); 2RCS-FI434 (435)( 436) flow is lowering.

7.4 Verifies 2RCS-1121A(B)(C) amps zero.

COMMENTS:

EVALUATOR CUE: That completes this JPM.

STOP TIME: - - - - - - -

BVPS-TR-0026 Page I of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-172 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 2 Auxiliary Feed Pump Suction K/A

REFERENCE:

061 Kl.07 3.6/3.8 TASK ID: 0241-054-04-012 061 Al.04 3.9/3.9 0532-010-05-043 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D SRO ONLY 0 ALTERNA TE PATH JPM O ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform ~ Plant Site D AnnualRequalExam D BVT

~ Simulate D Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RES UL TS Performer Name: Performer SAP#:

Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Bvaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 7 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE EVALU ATOR DIRECTION SHEET TASK STANDARD: Service water vented and aligned to 2FWE*P23B Motor Driven Auxiliary Feed Pump suction.

RECOMMENDED In-Plant STARTING LOCATION:

INITIAL CONDITIONS:

The Control Room has responded to an Inadequate Core Cooling Accident and is now in E-1, "Loss of Reactor or Secondary Coolant".

Containment Isolation Phase B (CIB) actuation has occurred.

PPDWST level has decreased to the low-level alarm setpoint.

PPDWST level indicators 2FWE*LI104Al and 2FWE*Lll04A2 both indicate 20".

Both Demineralized Water Pumps 2WTD-P23A and B, are unavailable, and the Demin Water Storage Tank, 2WTD-TK23 is also unavailable.

2SWS*MOVI 03B, Recirc. Spray HXs Service Water Sup "B" Isolation Valve has been verified OPEN.

S/G Pressure is approximately 400 psig.

INITIATING CUE: Your supervisor directs you to supply 2FWE*P23B Motor Driven Auxiliary Feed Pump suction from Service Water by completing EOP Attachment A-1.8 beginning with step 9.

REFERENCES:

20M-53A.1.A-1.8 Revision 7 TOOLS: Keys (simulated)

Proper PPE

.-fANDOUT: 20M-53A. l .A-1.8 Revision 7

BVPS-TR-0026 Page 3 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-172 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 2 Auxiliary Feed Pump Suction STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU EVALUATOR CUE: Provide candidate a copy of 20M-53A.1.A-l .8.

START TIME:

1. Review 20M-53A. l .A-l .8. 1.1 Reviews 20M-53A. l .A-l .8.

COMMENTS:

')

IF PPDWST Level Drops to 2.1 Recognized from the Initial Conditions that CIB has 25 inches, THEN align occurred and performance of this step is not required.

Service Water to the Auxiliary Feedwater Pumps COMMENTS:

by performing the following:

If Containment Isolation Phase B has NOT occurred, then perform the following:

Close [2SWS*MOVI 04B]

Close [2SWS*M0Vl04D]

3. Verify Open 3.1 Recognized from the Initial Conditions that the

[2SWS*MOV103B], Recirc Control Room has already performed this step.

Spray HX Service Water Supply Header B Isolation. COMMENTS:

BVPS-TR-0026 Page 4 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-1 72 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 2 Auxiliary Feed Pump Suction STEP STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT)~ S/U 4.C Close [2FWE*356], Service 4.lC Closes 2FWE*356, Service Water Supply Tell Tale Water Supply Tell Tale Drain.

Drain. (North SFGDS above 2FWE*23B - 718) I EVALU ATOR CUE: 2FWE*356 is Closed.

I COMMENTS:

5.C Vent SWS to AFW pump 5.lC Simulates removing locking device and opening suction as follows: 2FWE*98, Service Water Isolation.

1) With Key SR/14, open EV ALU ATOR CUE: 2FWE*98 is unlocked and

[2FWE*98], Service Open.

Water Isolation, (North SFGDS, above 5.2C Removes pipe cap from 2FWE-122 vent discharge.

2FWE*P23B - 718').

I EVALUATOR CUE: Pipe cap is Removed.

I

2) Remove pipe cap at

[2FWE-122], Service 5.3C Opens 2FWE-122, Service Water Supply Vent Isol Water Supply Vent Isol Vlv.

Vlv. (North SFGDS -

718') EVALUATOR CUE: 2FWE-122 is Open, and a solid stream of water is discharging for the vent line.

3) Open [2FWE-l 22]

UNTIL a solid stream of 5.4C Closes 2FWE-122, Service Water Supply Vent Isol water appears, THEN Vlv ..

close [2FWE-122).

I EVALU ATOR CUE: 2FWE-122 is Closed.

I COMMENTS:

I

BVPS-TR-0026 Page 5 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-1 72 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 2 Auxiliary Feed Pump Suction STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT ::::, S/U

6. For [2FWE*P22], Turbine 6.1 2FWE*P22 alignment is not required. Step is marked Driven AFW Pump, perform NIA.

the following:

EVALUATOR CUE: If needed, remind candidate Slowly Open [2FWE*90], that it is only desired to align 'B' MDAFW pump per Service Water Supply to the initiating cue.

[FWE*P22]

(South Safeguards 718') COMMENTS:

7. For [2FWE*P23A], Motor 7.1 2FWE*P23A alignment is not required. Step is Driven AFW Pump, perform marked NIA.

the following:

EVALUATOR CUE: If needed, remind candidate Slowly Open [2FWE*91), that it is only desired to align 'B' MDAFW pump per Service Water Supply to the initiating cue.

[FWE*P23A]

(South Safeguards 718') COMMENTS:

8.C For [2FWE*P23B], Motor 8.1 C Opens 2FWE*92, Service Water Supply to Driven AFW Pump, perform FWE*P23B.

the following:

j EVALUATOR CUE: 2FWE*92 is Open.

Slowly Open [2FWE*92],

Service Water Supply to COMMENTS:

[FWE*P23B]

(North Safeguards 718')

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

BVPS-TR-0026 Page 6 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-172 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 2 Auxiliary Feed Pump Suction STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 9.C With KEY CRIT/19, close 9.lC Unlocks and Closes 2FWE*95, Primary DWST

[2FWE*95], Primary DWST Supply to 2FWE*P23B.

Supply to [2FWE*P23B].

(North Safeguards 718') I EVALUATOR CUE: 2FWE*95 is Closed. I COMMENTS:

I 0. Observe AFW pump 10.1 Observe 2FWE*P23B pump discharge pressure to discharge pressure to ensure ensure proper operation.

proper operation.

EVALUATOR CUE: 2FWE*P23B discharge pressure is normal.

COMMENTS:

11. Locally monitor running 11.1 Monitors 2FWE-PI156B, 'B' MDAFW Suction Auxiliary Feedwater Pump Pressure to ensure suction pressure is > 10 psig.

suction pressure:

EVALUATOR CUE: 'B' MDAFW Suction Pressure

[2FWE-PI156], 2FWE- is> 10 psig.

P22 Suction Pressure

[2FWE-PI156A], 2FWE- COMMENTS:

P23A Suction Pressure

[2FWE-PI156B], 2FWE-P23B Suction Pressure

BVPS-TR-0026 Page 7 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL- l 72 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 2 Auxiliary Feed Pump Suction STEP STANDARD

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

12. IF any running Aux Feedwater 12.1 Candidate recognizes that flushing the strainers is not Pump suction pressure drops required with suction pressure > 10 psig. Step is less than 10 PSIG, THEN marked NIA.

flush [2FWE-STRY200],

Service Water Supply COMMENTS:

Strainer, as follows:

1) Open [2FWE-121),

2FWE-STR Y200 Blowdown Isol Viv.

2) Allow strainer to flush for several seconds.

3) Close [2FWE-12 l ].

4) IF suction pressure remains less 10 PSIG, THEN repeat steps UNTIL suction pressure is greater than 10 PSIG.

13. Notify the Control Room that 13.1 Candidate reports to the Control Room that EOP attachment A-1.8 is attachment A-1.8 is complete.

complete.

EVALUATOR CUE: As Unit Supervisor acknowledge the report.

COMMENTS:

EVALUATOR CUE: This JPM is complete.

STOP TIME: _ _ _ _ _ __

BVPS-TR-0026 Page l of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-086 JPM TITLE: Place Instrument Air Bypass Filters in Service JPM REVISION: 7 Kl A

REFERENCE:

078 K4.02 3.2/3.5 TASK ID: 0341-034-01-043 078 A2.0l 2.9/3.2 02.1.20 4.6/4.6 JPM APPLICATION: ~ REQUALIFICA TION ~ INITIAL EXAM D TRAINING D SRO ONLY D ALTERNATEPATHJPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform ~ Plant Site D Annual Requa) Exam D BVT

~ Simulate D Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SAP: Name/SAP:

Name/SAP: Name/SAP:

EVALUATOR Evaluator (Print): Date:

I Evaluator Signature:

BVPS-TR-0026 Page 2 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EV ALU ATOR DIRECTION SHEET TASK STANDARD: [2IAS-FLT37 (39)] placed in service and air dryers [2IAS-DRY23A]

removed from service, with filters being blown down.

RECOMMENDED In-Plant STARTING LOCATION:

INITIAL CONDITIONS:

The plant is operating normally at 100% power.

All systems are aligned for normal operation.

All procedure initial conditions are satisfied.

INITIATING CUE: Your supervisor directs you to place the Instrument Air Bypass Filters

[2IAS-FLT37 & 39] in service and remove the Instrument Air Dryer

[2IAS-DRY23A] from service in accordance with 20M-34.4.F.

REFERENCES:

20M-34.4.F, "Placing Instrument Air Bypass Filters In And Out of Service And Changing Cooling Water Supplies For The Station Air Compressors" Revision 11.

TOOLS: Proper PPE HANDOUT: 20M-34.4.F, "Placing Instrument Air Bypass Filters In And Out of Service And Changing Cooling Water Supplies For The Station Air Compressors" Revision 11.

BVPS-TR-0026 Page 3 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-086 JPM TITLE: Place Instrument Air Bypass Filters in Service JPM REVISION: 7 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSA T)=> SIU EVALUATOR CUE: Provide candidate with a copy of 20M-34.4.F.

START TIME:

1. Reviews 20M-34.4.F, 1.1 Reviews section IV.A of 20M-34.4.F.

"Placing Instrument Air Bypass Filters In And Out of COMMENTS:

Service And Changing Cooling Water Supplies For The Station Air Compressors".

2. Verify closed the following 2.1 Verifies handwheel for the following valves are valves: CLOSED. (perpendicular to the flowpath)

a. [2IAS-1244], Instrument Air

2IAS- l 244 (Turb Bldg 730')

Dryer Bypass Line Filter Drain Trap Bypass Isolation.

2IAS-l 246 (Turb Bldg 730')

b. [2IAS-l 246], Instrument Air Dryer Bypass Line Filter EVALUATOR CUE: Handwheels are perpendicular Drain Trap Strainer Drain to the flowpath.

Isolation.

COMMENTS:

BVPS-TR-0026 Page 4 of 5 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-086 JPM TITLE: Place Instrument Air Bypass Filters in Service JPM REVISION: 7 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=:> SIU 3.C Open the following valves: 3.IC Rotates the handwheel for the following valves until they are OPEN. (parallel to the flowpath)

a. [2IAS-1233], Instrument Air Dryer Bypass

2IAS-1233 (Turb Bldg 730')

Upstream Isolation.

2IAS-1148 (Turb Bldg 730')

b. [2IAS- l 148], Instrument Air Dryer Bypass EV ALU ATOR CUE: Handwheels are parallel to the Downstream Isolation. flowpath.

COMMENTS:

4.C Blowdown [2IAS-FLT37], 4.IC Rotates 2IAS-1244 hand wheel until it is OPEN.

Instrument Air Bypass Filter, (parallel to the flowpath) as follows:

EVALU ATOR CUE: Handwheel is parallel to the

a. [2IAS- l 244], Instrument flowpath.

Air Dryer Bypass Line Filter Drain Trap Bypass 4.2 Verifies no water discharging from the blowdown Isolation. line.

b. When no water is observed discharging from EVALUATOR NOTE: No more water is discharging the blowdown line, Close from the blowdown line.

[2IAS- l 244], Instrument Air Dryer Bypass Line 4.3C Rotates 2IAS-1244 handwheel until it is CLOSED.

Filter Drain Trap Bypass (perpendicular to the flowpath)

Isolation.

EVALUATOR CUE: Handwheel is perpendicular to the flowpath.

COMMENTS:

I

BVPS-TR-0026 Page 5 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-086 JPM TITLE: Place Instrument Air Bypass Filters in Service JPM REVISION: 7 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => S/U 5.C Remove [2IAS-DRY23A], 5.lC Rotates 2IAS-1215 hand wheel until it is CLOSED.

Instrument Air Train A (perpendicular to the flowpath)

Dryer, from service as follows: EVALUATOR CUE: Handwheel is perpendicular to the flowpath.

a. Close [2IAS-1215],

Instrument Air Dryer 5.2 Checks instrument air pressure 2IAS-PI 109 is > 98 2IAS-DRY23A Inlet ps1g.

Isolation.

EV ALU ATOR CUE: Instrument air pressure 2IAS-

b. Check Instrument Air PI 109 is 105 psig and STABLE.

Pressure is being maintained > 98 psig. 5.3C Places ON-OFF-AUTO control switch to OFF position.

c. Place the On-Off-Auto control switch to the OFF EVALUATOR CUE: 2IAS-DR Y23A control switch position. is OFF.

d. Push in the red Push Stop- 5.4C Pushes in the RED Push Stop-Pull Start pushbutton.

Pull Start pushbutton at the dryer. EVALUATOR CUE: RED Push Stop-Pull Start pushbutton has been depressed.

COMMENTS:

EVALUATOR CUE: State "This JPM is complete."

STOP TIME:

BVPS-TR-0026 Pagel of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-OXX JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power KJA

REFERENCE:

EAl.04 3.5 I 3.9 TASK ID: 0391-027-06-043 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM O TRAINING D SROONLY D ALTERNATEPATHJPM D ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform ~ Plant Site D Annual Requal Exam D BVT

~ Simulate D Simulator D Initial Exam D NRC D Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

'l'ime D Yes Allotted 20 Minutes Actual minutes

-..:ritical: ~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SAP: Name/SAP:

Name/SAP: Name/SAP:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The DC loads on [DC*SWDB2-l and 2-2] and [PNL-VITBS2-1D and 2D] are repositioned per the procedure.

RECOMMENDED In-Plant STARTING LOCATION:

EV ALU ATOR NOTE: This JPM is designed to start with Enclosure 2 of procedure FSA-11.

INITIAL CONDITIONS: A Loss of All AC Power has required implementation of20M-53E.l.FDA-l l, DC/ UPS ELAP Load Shed. Assume you have all required personal protective equipment.

INITIATING CUE: Your supervisor directs you to continue by performing Enclosure 2, Rod Control Building Load Shed, of the procedure and complete the electrical alignments for [DC*SWDB2-l and 2-2] and [PNL-VITBS2-1D and 2D]. Report back to your supervisor when the steps are complete.

REFERENCES:

20M-53E.l.FSA-ll, "DC/UPS ELAP Load Shed", Issue O Rev._71 TOOLS: None HANDOUT: 20M-53E.l.FSA-l l, DC/UPS ELAP Load Shed, Enclosure 2

BVPS-TR-0026 Page 3 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-OXX JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT =>

EVALUATOR NOTE: Throughout this JPM, if necessary, provide the CUE that the breaker alignments are as simulated. Refer to the breaker positions in the tables on the left of each step. For breakers that are BOLD and UNDERLINED provide a Cue that the as found position in ON. For all other breakers, the as found position will be as listed in the table.

EVALUATOR CUE: Provide candidate a copy of 20M-53E.l.FSA-11, Enclosure 2.

START TIME: - - - - - - - -

1. Reviews procedure. 1.1 Reviews the provided copy of20M-53E.1.FSA-1 l, Enclosure 2.

COMMENTS:

BVPS-TR-0026 Page 4 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-O:XX JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 2.C Align the following panel circuit breakers to the EVALUATOR NOTE: Steps that require breaker required position using this positions that are their normal system alignments enclosure. [DC*SWBD2-1]: (NSA) will be "Verify" steps, breakers that require a (AE SWGR, El 730') position other than NSA will be "Place" steps. These components will be bold and underlined in the required position table. Cue the as found positions as describe in the Evaluator Note on the previous page.

SWBD LOAD (CKT) Req BRK Pos 2.1 Verifies breaker 1-1 in the ON position.

Uninterruptible Pwr 1-1 ON Supply 2-1 Erner Diesel Gen 2.2C Places breaker 1-2 in the OFF position.

1-2 OFF 2-1 1-3 4,160 V Switchgear OFF 2.3C Places breaker 1-3 in the OFF position.

Unit2 AE 480 V Unit 1-4 OFF 2.4C Places breaker 1-4 in the OFF position Substation 2-8 125 VDC 1-5 ON 2.5 Verifies breaker 1-5 in the ON position Distribution Panel 3 125 VDC 1-6 OFF Distribution Panel 7 2.6C Places breaker 1-6 in the OFF position Reactor Trip 1-7 OFF Switchgear 125 VDC 2.7C Places breaker 1-7 in the OFF position 1-8 Distribution Panel OFF 11 2.8C Places breaker 1-8 in the OFF position 1-9 SPARE OFF 125 VDC 2.9 Verifies breaker 1-9 in the OFF position 1-10 Distribution Panel ON 15 2.10 Verifies breaker 1-10 in the ON position EVALUATOR CUE: Breakers are in the stated position.

COMMENTS:

BVPS-TR-0026 Page 5 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-OXX: JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 3.C Align the following panel circuit breakers to the required position using this EVALUATOR NOTE: The alignments for enclosure. [PNL *VITBS2- [PNL*VITBS2-1D continue on the following page.

lD]: (AE SWGR, El 730')

SWBD LOAD(CKT) Req BRK Pos ID-1 SPARE OFF 3.1 Verifies breaker lD-1 in the OFF position.

125 VDC ISOL TRANSDUCERS ID-2 ON 3.2 Verifies breaker lD-2 in the ON position.

[BAT*BKR 2-1]

(CKTBYS3C)

ID-3 SPARE OFF 3.3 Verifies breaker lD-3 in the OFF position.

ID-4 SPARE OFF TUNNEL SUMP LEVEL 3.4 Verifies breaker lD-4 in the OFF position ID-5 OFF

[2DAS*LT213]

(CKT DAS14) 3.5C Places breaker lD-5 in the OFF position RECIRC SPRAY SUMP LEVEL 3.6C Places breaker 1D-6 in the OFF position ID-6 OFF

[2DAS*LT215]

(CKT DAS15)

REACTOR CNMT 3.7C Places breaker 1D-7 in the OFF position SUMP LEVEL ID-7 OFF

[2DAS*LT220] 3.8C Places breaker lD-8 in the OFF position (CKT DAS16)

INCORE INSTR SUMP LEVEL 3.9C Places breaker lD-9 in the OFF position 10-8 OFF

[2DAS*LT22 IA]

(CKT DASAl) 3.lOC Places breaker lD-10 in the OFF position SPENT FUEL POOL LEVEL 10-9 OFF

[2FNC*LT102A]

(CKT FNCAl)

REACTOR CNMT EVALUATOR CUE: Breakers are in the stated SUMP LEVEL position.

lD-10 OFF

[2RSS*LT15IA]

(CKTRSSAI) COMMENTS:

BVPS-TR-0026 Page 6 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-O:XX JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 3.C CONTINUED Align the following panel circuit breakers to the EVALUATOR NOTE: The alignments for required position using this [PNL *VITBS2-1 D continue on this page.

enclosure. [PNL *VITBS2-ID]: (AE SWGR, El 730')

3.11 Verifies breaker 1D-11 in the OFF p?'ition.

SWBD BRK LOAD(CKT) Req Pos

~~

3.12 Verifies breaker 1D-12 in the position.

ID-11 SPARE OFF ID-12 SPARE OFF "'

ID-13 SPARE __.. - ** OFF 3.13 Verifies breaker 1D-13 in the OFF position.

ID-14 SPARE OFF SOUTH 3.14 Verifies breaker ID-14 in the OFF position SAFEGUARDS lD-15 SUMP LEVEL OFF 3.15C Places breaker ID-15 in the OFF position

[2DAS*LT209]

(CKT DAS12)

AUX BLDG 3.16C Places breaker ID-16 in the OFF position SUMP LEVEL ID-16 OFF

[2DAS*LT211] 3.17 Verifies breaker 1D-17 in the OFF position (CKT-DAS13) lD-17 SPARE OFF ID-18 SPARE OFF 3.18 Verifies breaker 1D-18 in the OFF position I

EVALUATOR CUE: Breakers are in the stated position.

COMMENTS:

BVPS-TR-0026 Page 7 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-O:XX JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power STEP STANDARD

( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT => S/U 4.C Align the following panel circuit breakers to the required position using this enclosure. [DC*SWBD2-2]: 4.1 Verifies breaker 2-1 in the ON position.

(DF SWGR, El 730')

4.2 Verifies breaker 2-2 in the OFF position.

SWBD LOAD(CKT) Reg BRK Pos 4.3C Places breaker 2-3 in the OFF position.

Uninterruptible Pwr 2-1 Supply 2-2 ON ruPS*VITBUS2-21 4.4C Places breaker 2-4 in the OFF position 2-2 SPARE OFF 4,160 V Switchgear 4.5 Verifies breaker 2-5 in the ON position 2-3 Unit2DF OFF r4KVS*2DFl 4.6C Places breaker 2-6 in the OFF position 480 V Unit 2-4 Substation 2-9 [480 OFF VUS*2-9l 4.7C Places breaker 2-7 in the OFF position 125 VDC 2-5 Distribution PNL-2 ON 4.8C Places breaker 2-8 in the OFF position rPNL *DC2-02l 125 VDC 2-6 Distribution PNL-6 OFF 4.9C Places breaker 2-9 in the OFF position

[PNL *DC2-06)

Reactor Trip 4.10 Verifies breaker 2-10 in the ON position 2-7 Switchgear OFF fREAC-2T-SWGRJ 125 VDC 2-8 Distribution PNL-10 OFF

[PNL *DC2- l Ol EVALUATOR CUE: Breakers are in the stated 2-2 Emerg DIG position.

2-9 2EGS*EG-2 OFF

[2EGS*EG-2] COMMENTS:

125 VDC 2-10 Distribution PNL-16 ON rPNL *DC2-16)

BVPS-TR-0026 Page 8 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-O:XX JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 5.C Align the following panel circuit breakers to the required position using this EVALUATOR NOTE: The alignments for

[PNL *VITBS2-2D continue on the following page.

enclosure. [PNL *VITBS2-2D]: (DF SWGR, El 730')

SWBD LOAD(CKT) Req BRK Pos 2D-l SPARE OFF 5.1 Verifies breaker 2D-1 in the OFF position.

125 VDC ISOL TRANSDUCER 2D-2 ON 5.2 Verifies breaker 2D-2 in the ON position.

[BAT*BKR 2-2]

(CKTBYS4C) 2D-3 SPARE OFF 5.3 Verifies breaker 2D-3 in the OFF position.

2D-4 SPARE OFF TUNNEL SUMP LEVEL 5.4 Verifies breaker 2D-4 in the OFF position 2D-5 OFF

[2DAS*LT214]

(CKTDAS24) 5.5C Places breaker 2D-5 in the OFF position RECIRC SPRAY SUMP LEVEL 5.6C Places breaker 2D-6 in the OFF position 2D-6 OFF

[2DAS*LT216]

(CKT DAS25)

REACTOR CNMT 5.7C Places breaker 2D-7 in the OFF position SUMP LEVEL 2D-7 OFF

[2DAS*L T222] 5.8C Places breaker 2D-8 in the OFF position (CKT DAS26)

INCORE INSTR SUMP LEVEL 5.9C Places breaker 2D-9 in the OFF position 2D-8 OFF

[2DAS*LT221B]

(CKT DASBI) 5.lOC Places breaker 2D-10 in the OFF position SPENT FUEL POOL LEVEL 2D-9 OFF

[2FNC*LT102B]

(CKTFNCBI)

REACTOR CNMT EVALUATOR CUE: Breakers are in the stated SUMP LEVEL position.

2D-10 OFF

[2RSS*L T151B]

(CKT RSSBI) COMMENTS:

BVPS-TR-0026 Page 9 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-OXX JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 5.C CONTINUED Align the following panel circuit breakers to the EVALUATOR NOTE: The alignments for required position using this [PNL *VITBS2-2D continue on this page.

enclosure. [PNL *VITBS2-2D]: (DF SWOR, El 730')

5.11 Verifies breaker 2D-11 in the OFF position.

SWBD LOAD (CKT) Reg oir-BRK 2D- l l SP ARE Pos OFF s.12 Verifies breaker 2D-12 in th~osition.

2D-12 SPARE OFF 2D-13 SPARE OFF 5.13 Verifies breaker 2D-13 in the OFF position.

2D-14 SPARE OFF NORTH 5.14 Verifies breaker 2D-14 in the OFF position SAFEGUARDS 2D-15 SUMP LEVEL 5.15C Places breaker 2D-15 in the OFF position

[2DAS *LT201]

(CKT DAS22)

AUX BLDG 5.16C Places breaker 2D-16 in the OFF position SUMP LEVEL 2D-16

[2DAS*LT212] 5 .17 Verifies breaker 2D-17 in the OFF position (CKT DAS23) 2D-17 SPARE OFF 5.18 Verifies breaker 2D-18 in the OFF position 2D-18 SPARE OFF EVALUATOR CUE: Breakers are in the stated position.

COMMENTS:

BVPS-TR-0026 Page lOoflO Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-OXX JPM TITLE: Align DC Electrical Power Supplies during an Extended JPM REVISION: 0 Loss of Power STEP STANDARD

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

6. Reports to the Supervisor 6.1 Notifies Supervisor that alignments on [DC*SWDB2-that the breaker alignments 1 and 2-2] and [PNL-VITBS2-1D and 2D] are are complete. complete.

EVALUATOR CUE: Acknowledge report as the supervisor.

COMMENTS:

EVALU ATOR CUE: State "This JPM is COMPLETE."

STOP TIME: - - - - - - -

A.ppen d"1x D scenario o utmer I! ~acili~y: BVPS Unit2 Scenario No. 1 Op Test No.: 2LOT17NRC

bxammers: Candidates: SRO ATC BOP Initial IC-184: -90% power, MOL, CB "D" @210 steps, RCS boron - 915 ppm.

Conditions:

Turnover: IA W 20M-52.4.B, Load Follow, Reduce power to remove 2HDH-P22B from service.

Control Rods are in Manual due to ongoing MSP.

Critical Tasks: 1. Initiate Feed and Bleed IAW FR-H.1 criteria

2. Restore AFW flow within 10 minutes of EDG start

3. Start SWE pump before EDG trip due to loss of cooling.

4. Dispatch operator to start EDG prior to step 28 of FR-H.1.

Event Malf. No. Event Type Event Description No.

(R) ATC la Reduce power using load follow.

(N) BOP, SRO lb (N) BOP, SRO Shutdown 2HDH-P22B when discharge flow is zero.

"B" SG Feedwater flow control valve, 2FWS-FCV488

" 2 CNH-CFW12C (C,A) BOP, SRO controller malfunction, requires manual control.

(C,A) BOP, SRO 3 SIS028 SIS Accumulator, 2SIS-TK2IB gas space leak.

(TS) SRO (C,A) ATC, SRO 4a XMT-RCS019A PRZR level transmitter (2RCS *LT460) fails low, (TS) SRO 4b (N) ATC, SRO Let down restoration using 20M-7.4.AB.

Loss of feed water due to large break on condensate pump 5 FLX-CFW07 (M) All discharge header.

Reactor trip with loss of offsite power, SG safety valves fail 6a SWD01 (M) All open.

6b DSGOIB 2-2 EDG fails to start automatically or from the Control room.

PMP-AFWOOI 7,8 LOA-AFW022 (M) All AFW pump failures, requires transition to FR-H.1.

2-2 EDG loading failures after local start, PMP-SWS007 (C) ATC, SRO 9a 9b PPL07B 2SWS*P21B failure, ATC required to start 2SWE*P21B.

(C) BOP, SRO BOP required to start 2FWE*P23B.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-O-FR-H.l NUREG-1021, Revision 11 FENOC Facsimile Rev. 1

Appendix D Scenario Outline 2L 17N1 The crew will assume the shift at 90% power, MOL, with the control rods in manual due to an ongoing MSP. Additionally, the turnover instructions are to reduce power using Load Follow procedure, 20M-52.4.B and shutdown 2HDH-P22B due to an oil leak.

After the crew has commenced a power reduction, the "B" SG feedwater flow control valve will experience a controller malfunction requiring the BOP to place the controller in manual and stabilize the SG flow IA W AOP 2.4.1, Process control failure.

A gas space leak will develop on the "B" SIS accumulator requiring the BOP to initiate nitrogen makeup.

The SRO will address TS.

The controlling PRZR level channel, 2RCS*LT460 will fail low causing letdown to automatically isolate.

The crew will enter the Instrument failure procedure to address the failed channel and place the alternate channel in service. The US will determine appropriate Tech Spec action.

After the alternate channel is placed in service, the ATC will restore normal letdown to service.

A large leak will develop on the discharge header of the condensate pumps, causing a main feedwater pump to trip on low suction pressure, requiring a reactor trip.

A loss of offsite power will occur after the hot bus transfer occurs, the 2-1 EDG will start and load as expected however, the "A" motor driven AFW pump will fail to start. The 2-2 EDG will fail to start either automatically or from the control room. The turbine driven AFW pump will trip immediately upon starting requiring the crew to transition from E-0 to FR-H.1.

Additionally on the reactor trip, secondary safety valves on the "A" and "B" SG's will fail open.

The plant conditions will degrade to the point that an RCS Bleed and Feed will be required IA W FR-H. l.

(Critical task)

After the crew has initiated Bleed and Feed, local attempts to start the 2-2 EDG will be successful. (Critical task) However, the "B" Service water pump will fail requiring the ATC to start the "B" standby service water pump, 2SWE*P21B. (Critical task) Also, the "B" motor driven AFW pump will fail to automatically start on the sequencer requiring the BOP to manually start 2FWE*P23B (Critical task)

The scenario will be terminated when the crew restores AFW flow and shuts the first PORV for recovery.

(Evaluator discretion on termination point dependant upon crews timing and progression thru procedures)

Expected procedure flow path is E FR-H. l.

NUREG-1021, Revision 11 FENOC Facsimile Rev. 1

BEAVER VALLEY POWER STATION INITIAL CONDITIONS: 90 % Power, D@210 steps, XE increasing, MOL, 915 PPM Boron, IC-184 ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS EOUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S)

SHIFT TURNOVER INFORMATION

1. Due to an oil leak, 2HDH-P22B needs to be removed from service.

2. Reduce load to 85% using 20M-52.4.B, Load Follow and secure 2HDH-P22B IAW Attachment 18.

3. Control Rods are in Manual due to an ongoing MSP, Auto rods is not available.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. Reactivity plan - provide MOL Rapid Power Reduction reactivity plan E-0

2. 20M-52.4.B place kept FR-H.l Attachment A-1.24 AOP 2.4.1 AOP 2.7.1 20M-7.4.AB 20M-l l.4.F 6 IF, Attach 1 Insert pre loads per the simulator pre load section of the HTML file for this scenario:

BVPS - 2Ll 7 NRC Scenario 1, rev 1 3 of 15

BEAVER VALLEY POWER STATION l 1 f' Tu cY frA"l ~J,t\\f (4 I INSTRUCTIONAL GUIDELINES I PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 1 and 2:

Reduce Load using 20M-52.4.B and SID 2HDH-P22B IA W attach. 18. SRO directs the crew to continue power decrease IA W 20M-52.4.B and shutdown 2HDH-P22B IA W Attachment 18 when pump flow reduces to zero IA W reactivity plan, ATC borates 75 gallons and RCS temperature lowers in response to rod manually inserts control rods 6 steps.

insertion.

Event 2: Reactor power lowers. BOP reduces turbine load by; 2FWS *FCV 488 controller oscillation

Verifying turbine control in "l ST STG OUT" in automatic.

Sets the desire turbine load by adjusting the EHC SETTER. (final setting -770)

IMF CNH-CFW12C (4120) 20 0 0

Setting the LOAD RATE thumbwheel to (preloaded to occur 2 minutes after the desired rate (5%/min max).

BOP depresses the "GO" pushbutton to

Depressing "GO".

reduce turbine load.)

BOP verifies/maintains the following while reducing ROLE PLAY: load, 2 minutes after being dispatched to

Valve position limiter -5% above current valve locally investigate 2FWS*FCV488, position.

report back that nothing obvious

Maintains MV AR slightly to right of zero.

identified locally at the valve.

Maintains generator power factor 0.9 - 1.0 lagging.

BVPS - 2Ll 7 NRC Scenario 1, rev 1 4 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ROLE PLAY: IAW 20M-52.4.B, Attachment 18, crew establishes a 1 min after being dispatched to close trend of heater drain pump parameters.

2HDH-698, insert IMF VLV-FWH052 (0 0) 0, then Crew monitors 2HDH-P22B flow via computer point report back that 2HDH-698 is closed. F2012A.

When computer point indicates zero flow, BOP shuts down 2HDH-P22B.

Event 2: A6-l OE, SG lB Level Deviation From Setpoint IA W AOP 2.4.1, BOP notes erratic automatic 2FWS*FCV488 controller malf. operation informs SRO and establishes manual control of main feed regulating valve, 2FWS *FCV 488 and restores stable level at setpoint.

ROLE PLAY:

2 minutes after being dispatched to SRO provides a control band of 44% +/-5% and Rx trip locally investigate 2FWS *FCV 488, criteria of 25% low and 85% high for operation of report back that nothing obvious 2FWS*FCV488 in Manual.

identified locally at the valve. Crew dispatches operator to locally investigate.

Crew notifies I&C and Ops management of 2FWS*FCV488 controller auto control failure with satisfactory manual control.

EVENT 3:

NOTE:

SIS accumulator, 2SIS*TK21B gas 2SIS*TK21B pressure begins to slowly lower. It's not likely that the crew will identify pressure trend space leak initiates after the turbine until the low pressure alarm annunciates. The scripting "GO" button is depressed for the power for event 3 will follow event 4.

reduction, it will take -20 minutes for low pressure alarm to annunciate.

IMF SIS02B (4 120) 20 Insert Event 4 malfunction at LE discretion.

BVPS - 2Ll 7 NRC Scenario 1, rev 1 5 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4: ,,-1; ATC reports unexpected PRZR level deviation alarm.

Pressurizer level transmitter IMMEDIATE PLANT RESPONSE: ATC identifies 2RCS*LT460 has failed low.

2RCS*LT460 fails low. ALARMS: IAW AOP 2.41, Part C, IOA's ATC removes A4-1B, PRZR Control Lvl High/Low, 2RCS*LT460 from service by placing PRZR level IMF XMT-RCS020A (0 0) 0 4 A4-1C, PRZR Control Lvl Dev High/Low, control channel selector to POS I/III (459/461 ).

A4-1G,PRZR Control Htr Group Trouble, NOTE: A4-2G, PRZR B/U Htr Group Auto On/Off, A TC reports that letdown has isolated.

The ATC may not immediately remove A2-3E, Charging Flowpath Trouble.

2RCS*LT460 from service if letdown 2RCS-LI460 indicates downscale. BOP refers to ARP.

isolation is immediately recognized, as Letdown isolates, 2CHS*LCV460A and 2CHS-IOA's of AOP 2.7.1 Part B will be AOV200A & B close. ATC performs IO A's for the loss ofletdown IA W higher priority. All PRZR heaters de-energize. Part B of AOP 2.7.1 by:

Verifying 2CHS*AOV200A,B,C are closed.

Closing 2CHS*FCV122.

Adjusting 2CHS*HCV186 to adjust seal injection flow tojust above low seal injection alarm setpoint.

SRO enters AOP 2.7.1 Part B, Loss of Letdown SRO verifies ATC performed IOA's.

ATC checks 2CHS*FCV122 remains closed.

A TC checks letdown flowpath in proper alignment, and reports that 2CHS*LCV460A is shut due to low failure of2RCS*LT460.

SRO enters 20M-6.4.IF, attachment 1. SRO transitions to Reactor Coolant System Instrument failure procedure, 20M-6.4.IF, attachment 1.

BVPS -2Ll 7 NRC Scenario 1, rev 1 6 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ATC places PRZR level control channel selector to POS I & III. (may have been previously performed IAW AOP 2.4.1 IOA's.)

ATC verifies PRZR level recorder selector is positioned to record the controlling level channel.

ATC verifies there is adequate makeup to the VCT.

ATC verifies PRZR heaters (Control & Backup) groups have returned to normal or manually energizes heaters as necessary.

SRO directs A TC to restore letdown IA W 20M-7.4.AB.

SRO contacts Operations management and notifies I&C of level transmitter failure.

BVPS- 2Ll 7 NRC Scenario 1, rev 1 7 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4: (continued) SRO directs A TC to restore letdown IA W A TC establishes letdown as follows:

20M-7.4.AB.

Verifies 2CHS*FCV122 is closed in Manual.

Verifies 2CHS*MOV289 & 310 open.

Verifies 2CHS*AOV200A, B, & C closed.

Verifies 2CHS*AOV204 is open.

Places 2CHS*PCV145 in MAN & 50% open.

Verifies open, 2CHS*MOV100A.

Opens 2CHS*LCV460A and 460B.

Adjusts 2CHS*FCV122; 30-50 gpm.

Places 1st orifice in service by opening, as desired, 2CHS* AOV200A(B)(C).

Increases charging flow to >60 gpm.

Lowers LD pressure to 120 -140 psig.

Places 2°ct orifice in service by opening, as desired, 2CHS* AOV200A(B)(C).

Adjusts letdown pressure to 260 psig using 2CHS*PCV145 and places PCV in AUTO.

Adjusts seal injection and charging flow as necessary & returns FCV-lCH-122 to AUTO.

SRO references Technical Specifications: 3.3.1 (RTS Instrumentation) Condition A; immediately enter the Condition referenced in Table 3.3.1-1 function 9 (PRZR level high) Condition K; trip channel in 72 hrs. or reduce power to < P-7 in 78 hrs.

SRO determines following TS are for tracking only 3.3.3 (PAM instrumentation) Table 3.3.3-1 function 11 is met ifLT459 and LT461 are operable.

3.3.4 (Remote Shutdown System) Table B.3.3.4-1 function 4.a requirement is met ifLT461 is operable.

BVPS - 2Ll 7 NRC Scenario 1, rev 1 8 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 3:

ALARMS:

SIS accumulator, 2SIS*TK21B gas Al-4A, Accumulator Level/Pressure High/Low A TC announces unexpected accumulator alarm.

space leak. A TC reports "B" SIS accumulator pressure low.

Crew reviews ARP.

SRO directs crew to repressurize the "B" SIS Crew dispatches an operator to align the nitrogen ROLE PLAY: accumulator IA W 20M-1 l.4.F. header.

1 minute after being dispatched to align Crew verifies A2-1D, NITROGEN SUPPLY the nitrogen header, INSERT command A2-1D will alarm when the nitrogen header is SYSTEM AVAILABLE is ON.

LOA-CAS002 1 to open 2GNS-440. pressurized. Crew adds Nitrogen to the "B" SIS accumulator by:

Then report back that nitrogen

Opening 2GNS*AOV101-1 and 101-2.

alignment is complete.

Opening either 2GNS*SOV853B or E.

Observing accumulator pressure increase.

Closing 2GNS*SOV853B(E)

SRO references Technical Specifications: 3.5.1 (ECCS Accumulators) Condition B, restore accumulator to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Insert Event 5 malfunction at LE discretion.

BVPS- 2Ll 7 NRC Scenario 1, rev 1 9 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE

\~~')

EVENTS:

Loss of feed water due to large break on ALARMS: BOP reports multiple feedwater related annunciators.

condensate pump discharge header. A6-5E, Condensate pump disch/suct press low.

A6-10B, SG Feed pump suet press low. Crew recognizes loss of feedwater capability.

A6-5D, Condensate pump Auto start/auto stop.

Feed pump suction pressure lowers Due to loss of feed, SRO directs ATC to manually trip Condenser hotwell level lowers the reactor.

SG NR levels lower SRO directs the crew to perform IOA's for E-0.

EVENTS 6, 7, 8 & 9:

Malfunctions occurring upon Rx trip. Offsite power lost after hot bus transfer 2FWE*P22 trips after auto starting.

All malfunctions are preloaded. EDG 2-2 fails to start either automatically or manually from CR. (will be recovered later)

"A" MDAFW pump failed, won't start.

SG "A" & "B" safety valves open and fail open upon trip.

EDG 2-2 loading failures upon recovery, "B" MDAFW pump fails to auto start.

"B" Service water pump fails to start, requires starting 2SWE*P21B.

SRO enters E-0. ATC and BOP commence IO A's of E-0.

ATC verifies reactor trip:

A5-6D-LIT.

Power range indication is <5%.

Neutron flux is dropping.

BVPS - 2Ll 7 NRC Scenario 1, rev 1 10 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8 & 9:(continued) BOP verifies turbine trip:

Throttle OR Governor valves ALL closed.

Main Generator output brks - open.

Exciter Circuit breaker - open.

NOTE: After E-0 IOA's are BOP verifies power to AC emergency busses completed, the BOP will dispatch an

Using VB-C voltmeters, verifies either 2AE or operator to locally investigate the 2-2 2DF has voltage indicated.

EDG start failure.

BOP identifies 2AE bus is energized via the 2-1 EDG.

Critical Task, Dispatch operator to locally investigate 2-2 EDG start failure BOP identifies that 2DF bus is de-energized and that before step 28 ofFR-H. l. the 2-2 EDG failed to auto start.

ROLE PLAY: SI automatically actuated Check SI status:

As the operator dispatched to ATC reports SI automatically actuated and investigate the 2-2 EDG start failure, manually actuates SI by turning both trains' wait 2 minutes then report back that the control switches.

EDG has tripped on overspeed and you are attempting to reset the overspeed trip.

ATC/BOP, sounds standby alarm, announces Unit 2 reactor trip and safety injection.

BVPS - 2Ll 7 NRC Scenario 1, rev 1 11 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Check ifHHSI flow should be secured by checking the following:

CNMT & Secondary radiation

CNMT pressure & sump level

SG - pressures and levels

RCS subcooling

Secondary heat sink exists

RCS pressure - stable or rising

PRZR level-> 17%

SI occurred automatically Due to SG pressures not being consistent with pre-event, crew determines SI is required; SI flow should not be secured at this time.

Only Train "A" has power at this time. ATC verifies SI System status:

2CHS*P21A running, 2CHS*P21B not running.

2SIS*P21A running. 2SIS*P21B not running.

HHSI Flow indicated on 2SIS-FI943.

ROLE PLAY: Wait 2 minutes then BOP verifies AFW System status respond as appropriate to the following

Motor-driven AFW Pumps - NONE directions/requests from the crew RUNNING and won't start from CR.

concerning AFW status:

Turb driven AFW Pump Stm Supply Isol

-2FWE*P23A - Overcurrent relay 51- Valves - OPEN but turbine is tripped.

VE218 is tripped on ACB 2El8.

AFW Throttle Vlvs - FULL OPEN

-2FWE*P23B not running, has no

Total AFW Flow - < 340 GPM power. BOP reports no Aux Feedwater pumps running and no

-2FWE*P22 - the trip/throttle valve is aux feed water flow exists.

tripped and the latch yoke is broken.

BVPS - 2Ll 7 NRC Scenario 1, rev 1 12 of 15

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS7 & 8: SRO recognizes that AFW flow cannot be ATC checks if secondary heat sink is required by:

established and enters FR-H.l, Response to Loss

Verifying RCS press is> any non-faulted SG.

of Secondary Heat Sink.

RCS hot leg temperatures >350°F.

Crew determines a secondary heat sink is required.

Crew checks SG WR levels and determines if RCS bleed and feed should be initiated.

BOP verifies WR lvl in at least 2 SG's is> 14%.

NOTE: Due to SG safety valves failing Crew determines bleed and feed is not required at this open RCS Bleed and Feed will be time and continues to monitor WR level.

required, The crew will monitor all SG WR levels while attempting to restore Crew continues attempting to restore AFW flow.

AFW flow until Bleed and Feed criteria is met at which time the SRO will When pt SG WR level drops to <14%, BOP closes the return to step 3 of FR-H.1. affected SG AFW throttle vlvs. (only Tm A has pwr)

Critical Task CT-46 (FR-H.1.B)- 2 SG WR levels <14% SRO directs ATC to stop ALL RCP's and initiate RCS Crew establishes RCS feed and bleed Bleed and Feed by:

before PORVs open automatically. SRO returns to FR-H.l, step 3.

Actuating SL

Verifying a RCS Feed path with HHSI flow SAFETY SIGNIFICANCE -- Failure to indicated and at least 1 charging pump initiate RCS bleed and feed before the running.

RCS saturates at a pressure above the

Establish RCS Bleed path by opening all shutoff head of the high-head ECCS unisolated PORV's and BLOCK valves.

pumps results in significant and

Verify at least 2 sets of PORV's and associated sustained core uncovery. If RCS bleed block valves are open.

is initiated so that the RCS is depressurized below the shutoff head of the high-head ECCS pumps, then core uncovery is prevented or minimized BVPS - 2Ll 7 NRC Scenario 1, rev 1 13 of 15

A.ppen d"1x D scenano . 0 utrme Facility: BVPS Unit 2 Scenario No. 2 Op Test No.: 2LOT17 NRC Examiners: Candidates: SRO ATC BOP Initial IC-18: 100% power, MOL, equilibrium Xe, CB "D" @229 steps, RCS boron - 890 ppm.

Conditions:

Tl_;lrr10ver: Maintain 100% power,

" 2CHS*P21A inservice, 2CHS*P21B in standby.

2CHS*P22B inservice, 2CHS*P22A in standby.

2SWS*P21C inservice on 2DF bus due to failure of 2SWS*P21B.

Critical Tasks: 1. Start EDG locally and start SWS pump before EDG fails due to loss of cooling.

2. Closes PORV block valve prior to exiting ECA-0.0

3. Performs correct procedure transition from ECA-0.0

4. Crew manually trips the reactor from the Control room before FR-S.1 entry.

Event Malf. No. Event Type Event Description No.

2MSS*PT101C fails high causing 2SVS*PCV101C to la IMF XMT-MSS027A (N) BOP, SRO fail open, Rx power increases requiring power reduction.

During manual closure attempt, 2SVS*PCV101C fails at lb IMF CNH-MSS04A (TS) SRO 90%, requires local isolation.

2a NIS03D (I,A) ATC, SRO N-44 fails i auto rod l (AOP 2.1.3)

(N) BOP, SRO 2b Removes N-44 from service (AOP 2.2.1 C)

(TS) SRO (C,A) ATC, SRO AE 4KV bus fault, (AOP 2.36.2) requires ATC to start

" 3 HIVOlE (TS) SRO standby charging pump.

(R) ATC 4 TS required Shutdown.

(N) BOP, SRO 5 VLV-MSS005 (M) All Spurious closure of Main steam isolation valve.

Automatic reactor trip failure, requires crew to manually trip 6 PPLOlA,B (C) ATC, SRO the reactor from the Control Room.

Automatic Main steam line isolation failure, requires BOP to 7 PPLlOA,B (C) BOP, SRO manually isolate main steam lines.

SWDOl Loss of all AC upon transfer to offsite power, requires entry 8 DSG01B (M) All into ECA-0.0, 2-2 EDG starts and trips on overspeed.

Master Pressure Controller, 2RCS*PK444A fails high in Auto 9 XMT-RCS030A (C) ATC, SRO causing PORV 455C to fails open, MOV block valve is de-energized until EDG is restored.

2SWS*P21 C fails to auto load after EDG is restored, requires 10 PPL07B (C) BOP, SRO manual start.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 -- ECA-o.o-- ECA-0.2 NUREG-1021, Revision 11 FENOC Facsimile Rev. 1

_ Appendix D Scenario Outline 2L 17N2 The crew will assume the shift at 100% power, MOL, with instructions to maintain power at 100%.

After the crew has assumed the shift, 2MSS-PT101 C will fail high causing "C" SG atmospheric steam dump valve, 2SVS-PCV101C, to go full open. The crew will respond IAW the alarm response procedure and attempt to manually close 2SVS-PCV101C which will fail at 90% open causing Rx power to increase.

The crew will reduce turbine load using Load Following procedure, 20M-52.4.B.1. The crew will dispatch an operator to locally isolate failed open valve and the SRO will evaluate applicable TS for failed valve.

Power Range Nuclear instrument, N-44 will then fail high causing the control rods to automatically insert.

The crew will perform the IOAs for AOP 2.1.3, Unexpected Control Rod Movement. The ATC will identify the N-44 failure and place the rods in manual. The SRO will then transition to AOP 2.2.lC, Power Range Channel Malfunction, and direct the BOP to remove the failed channel from service. The SRO will address Tech Specs for the failed instrument.

4KV emergency bus 2AE will de-energize due to a bus fault, the running charging pump will lose power and the 2-1 EDG will automatically start but cannot restore power due to the bus fault. The crew will enter AOP 2.36.2, Loss of 4KV Emergency Bus. The ATC will start the "B" charging pump IAW IOA's of AOP 2.36.2. The SRO will determine appropriate Tech Spec actions.

Due to the faulted bus, the Shift Manager will request the crew to take the plant offline at 2%/minute using AOP 2.51.1 for an unplanned power reduction.

During the power reduction, the "C" Main steam Isolation valve will spuriously fail closed, the reactor will fail to automatically trip requiring the ATC to manually trip the reactor (Critical task - Manual trip from the control room before entry into FR-S. l ). Additionally, automatic Main steam line isolation will fail to occur requiring the BOP to manually actuate MSLI.

A loss of offsite power will occur after the hot bus transfer, The 2-2 EDG will automatically start and then trip due to overspeed 5 seconds after starting.

The SRO will enter E-0 due to the reactor trip and then transition to ECA-0.0 following loss of AC power.

After the loss of offsite power, the Master pressure controller, 2RCS-PK444A will fail high in automatic causing PORV, 2RCS-PCV455C to open, the PORV will fail open, requiring the ATC to close the motor operated block valve after power is restored to the 2DF bus. (Critical task)

When the SRO is evaluating if AC power to at least one 4KV emergency is capable of being restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and the crew has directed field actions, the 2-2 EDG overspeed will be reset and the EDG will be restored to service. (Critical task)

When the 2DF bus is recovered, 2SWS*P21C will fail to auto start, the BOP is required to start the SWS pump and restore cooling water flow. (Critical task)

After power is restored, the crew will continue thru ECA-0.0 and transition to ECA-0.2. The crew will progress thru ECA-0.2 and restore ECCS flow (start the "B" charging/HHS! pump) (Critical task) at which point the scenario will be terminated.

Expected procedure flow path is E-0---+ ECA-0.0---+ ECA-0.2.

NUREG-1021, Revision 11 FENOC Facsimile Rev. 1

BEAVER VALLEY POWER STATION INITIAL CONDITIONS: 100 % Power, ARO, EQU XE MOL, 8900 PPM Boron, IC-185 (18)

ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS EOUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION(S)

SHIFT TURNOVER INFORMATION

1. 100% power, MOL equilibrium conditions, shift goal is to maintain 100% power.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. None Required E-0, - 1st 4 steps AOP 2.51.1 ECA-0.0 AOP 2.51.2 ECA-0.2 20M-7.4.AB Attachment A-0.12 20M-52.4.B. l Attachment A-1.4 Attachment A-1.5 AOP 2.1.3 AOP 2.2.lC AOP 2.4.1 AOP 2.36.2 Insert preloads per the simulator preload section of the HTML file for this scenario:

BVPS -2Ll 7 NRC Scenario 2, rev 1 3 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE r

EVENT 1: \ l, ~ -:i.

IMMEDIATE PLANT RESPONSE:

2MSS-PT101C fails high Crew recognizes that 2MSS-PT101C is failing high A6-7A, Steamline Pressure High. and that 2SVS-PCV101C has opened in response.

IMF XMT-MSS027A (0 0) 1500 15 2MSS-PI101C trending offscale high.

(preloaded) 2SVS-PCV101C strokes open 95%. ATC monitors RCS temperature and reactor power, RCS temperature decreases. informs SRO that power is rising.

IMF CNH-MSS04A (4 0) 50 Reactor power increases.

(preloaded) IAW AOP 2.4.1, SRO directs ATC to take manual control of open ADV, (2SVS-PCV101C) and close it.

ADV will NOT close from BB control. ATC places controller for 21 C SG ADV in manual and attempts to close ADV.

Reactor power slowly rising. Crew recognizes Rx power is slowly rising.

SRO directs the crew to lower Rx power using BOP reduces turbine load by; NOTE: SRO may elect to use AOP 20M-52.4.B.1

Verifying turbine control in" 1ST STG IN" 2.51.2, Reactor Overpower, to reduce

Sets the desire turbine load by adjusting the load, the process will be the same as Reactor power lowers. EHC SETTER.

scripted, however, AOP specifies

Setting the LOAD RATE thumbwheel to 5%/min rate. desired rate (5%/min max).

Depressing "GO" BOP verifies/maintains the following while reducing load,

Valve position limiter -5% above current valve position.

Maintains MV AR slightly to right of zero.

Maintains generator power factor.0.9 - 1.0 lagging.

BVPS - 2L 17 NRC Scenario 2, rev 1 Page 4 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 1: (continued) Crew notifies field operator to close 2SVS-PCV101C Valve requires manual isolation, valve using 20M-21.4.J will not close via either local manual Or locally isolate via 2SVS-25 or de-energize via operation or by de-energizing MCC.

ROLE PLAYS (as appropriate):

If requested to de-energize 2SVS-PCV101 C, insert TRG! 7, wait 2 minutes, After lights are off; report to CR that valve has been de-energized.

IOR XA30009G (7 120) 0 IOR XA30009R (7 120) 0 (preloaded)

(valve will stay at 90% open- don't actually de-energize valve - just tum off red/green lights.)

If requested to verify local position, report that valve appears to be -90%

open and you can hear flow through it.

When requested to isolate 2SVS-25, insert:

LOA-MSS018 (0 0) 0 60 wait 2 minutes then report to the control room that 2SVS-25 is isolated.

NOTE: Due to scenario progression, it SRO refers to TS 3.7.4, Condition A for inoperable may be necessary to ask SRO follow up atmospheric dump valve. Requires restoring within 7 question regarding TS applicability for days.

2SVS-PCV101C failure.

Insert next event at LE discretion BVPS-2Ll 7 NRC Scenario 2, rev 1 Page 5 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 2:

Rods automatically step inward in response to N-44 fails high N-44 failure. A TC reports unexpected alarms and rod motion.

IMF NIS03D (0 0) 200 0 ASIS Crew enters AOP 2.1.3, Unexpected Control ATC verifies no load rejection in progress and places Rod Movement. rod control to manual to stop the rod insertion.

A TC verifies reactor overpower has not occurred.

BOP verifies 2MSS*PT446 and 447 are consistent with current power level and Tref.

ATC reports N-44 indication is not consistent with other power range channels.

SRO transitions to Power Range Channel Malfunction procedure, AOP 2.2.1 C to address BOP removes N-44 from service.

failed NI channel.

ATC reports only one PR channel (N-44) has failed, and verifies rods previously placed in manual.

BOP turns "Rod Stop Bypass Switch" for N44 on NIS Rack N50 to BYPASS.

ATC verifies status light for Overpower Rod Stop Bypass forN44 is lit. (status pnl 308, D-14)

BOP turns "Comparator Channel Defeat Switch" on NIS rack N37/N46 to N44 position.

Within 1 hr, verifies P-8, P-9, & P-10 interlocks in required state for 100% power.

BVPS - 2L 17 NRC Scenario 2, rev 1 Page 6 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 2: (continued) ATC verifies reactor power is> 50%.

BOP determines all PR channel upper and lower NOTE: Crew may initiate performance detector inputs to QPTR are operable.

of 20ST-2.4A, however next event will SRO directs BOP to perform 20ST-2.4A, QPTR occur before completion of OST. Manual calculation, after completion of AOP 2.2.1 C.

BOP determines all detector inputs to AFD monitor alarm are operable.

Within 72 hrs, trips nuclear bistables by removing control power fuses from Drawer A for N44 or directing I&C to remove the failed ch from service.

ATC ensures VB recorders are selected to operable detectors.

After removing rod block, ATC withdraws control rods to restore Tavg.

SRO addresses TS for N-44 failure: 3.3.1, Function 2.a, PR high flux, Condition D, trip ch w/in 72 hrs and QPTR every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3.3.1, Function 3, PR Hi flux rate, Condition E, trip ch w/in 72 hrs.

3 .3 .1, Functions 17 .c, d, Rx trip interlocks, Condition P, verify in required state w/in 1 hr.

3 .3 .1, Function 17 .e, Rx trip interlocks, Condition 0, verify in required state w/in 1 hr.

3.3.3, for PAM instrumentation - for Info Only.

3.4.1 DNB Condition A, Restore DNB parameters to within limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

INFO ONLY, 3.3.1, Function 2.b, PR low flux, Proceed with next event at LE Conditions E, R, & S.

discretion BVPS -2Ll 7 NRC Scenario 2, rev 1 Page 7 of 19

BEAVi=R VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT/)

I Loss of 2AE 4kv emergency bus with an auto start failure of 2-1 EDG. IMMEDIATE PLANT RESPONSE:

4KV ACB 2A10 trips open IMF BKR-HIVOl (0 0) 0 4KV bus 2AE voltage reduces to zero (VB-C) BOP reports multiple unexpected electrical alarms.

Multiple electrical related annunciators. BOP identifies 4kv Bus 2AE is de-energized and that the 2-1 EDG has failed to start.

BOP reports that 4kv Bus 2DF is energized.

ATC reports that 2CHS*P21A is NOT running.

SRO enters AOP 2.36.2 for Loss of 4KV SRO directs the crew to perform IOA's for Loss of Emergency Bus. 4KV Emergency Bus.

BOP verifies at least 1 4KV Emergency bus is energized. ( 2DF Bus)

ATC responds to no charging pumps running by:

Closing 2CHS*FCV122

Closing 2CHS *HCV 186

Starting 2CHS*P21B

Restore charging and seal injection by throttling open 2CHS*FCV122 and 2CHS*HCV186.

ROLE-PLAY: BOP identifies 2AE as the de-energized bus and As operator dispatched to switchgear, verifies ACB-2E7 and ACB-2Al0 are both OPEN.

wait 3 minutes then report that there are OC relays flagged on ACB-2E7. BOP reports A8-2B, Orange Bordered alarm is lit As electrical maint, report that you indicating an Overcurrent trip for ACB-2E7.

expect it to take at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for repairs.

BVPS-2Ll 7 NRC Scenario 2, rev 1 Page 8 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ATC verifies Component Cooling Water flow to All RCP thermal barriers.

BOP sounds the standby alarm and announces Unit 2 Loss of 4KV Emergency Bus.

SRO evaluates TS for emergency bus and EDG 3.8.1, AC sources; Conditions A & B, perform SR 2-1. j, J. Lr A oll, 3.8.1.1 in 1 hr., Condition D, restore offsite circuit or EDG to OPERABLE within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3.8.4, DC sources, Condition A, restore in 2 hrs.

1

5) }) 1,1 3.8.9, Distribution systems, Condition A, restore 8 hrs.

SRO determines 20ST-36.7 is required within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to verify operability of remaining sources per TS 3.8.1, Conditions A and B.

EVENT 4: TS Shutdown. SRO enters AOP 2.51.1, Unplanned Power BOP initiates turbine load reduction If necessary Role-play: Reduction

Depress 1st STG IN pushbutton.

Plant Management directs a power

Set EHC SETTER to desired load.

reduction to Mode 3 IA W AOP 2.51.1

Set LOAD RATE thumbwheel to 2%.

Unplanned Power Reduction,at

Depress GO.

2%/minute, since it isn't likely that

Maintain power factor within limits.

power will be restored to the AE bus in the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . ATC determines required Boration using the "Reactivity Plan for Rapid Power Reduction Activitites".

BVPS -2Ll 7 NRC Scenario 2, rev 1 Page 9 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ATC initiates boration IA W Attachment 1; (2% per minute power reduction).

Places boric acid makeup blender control switch to STOP.

Places mode selector switch to BORATE.

Sets 2CHS*FCV113A to flow rate desired.

Sets 2CHS-FQIS 113, BA totalizer, to total volume of BA to be added per reactivity plan.

Resets 2CHS*FQIS113

Ensures 2CHS*FQIS168 is set to "zero", then depresses reset.

Places boric acid makeup blender control switch to START, then verifies inservice BA pump starts, 2CHS*FCV113B opens and boric acid flow is indicated on 2CHS-FR113.

Adjusts 2CHS*FCV113A setpoint as desired to control boration flowrate.

Crew sounds the standby alarms and announces a Unit 2 Unplanned power reduction.

ATC places all available PRZR heaters to ON.

ATC adjusts rods in MANUAL and maintains Tavg within+/- SF of Tref.

Insert next event at LE discretion.

BVPS-2Ll 7 NRC Scenario 2, rev 1 Page 10 of 19

BEAVER VALLEY POWER STAT ION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE =:J EVENT 5:

Spurious closure of "C" Main Steam Al-3A, Stmline Stop Vlv Not Fully Open Isolation Valve Reactor trip and SLI (signals only).

IMF VLV-MSSOOS (0 0) 2 A12-1D, Safety Injection actuation ATC reports Safety Injection has actuated and 1st out "C" MSLI valve closes annunciator is in without an automatic reactor trip.

A6-11F, Loop C Feedflow > Steam Flow "A" & "B" SG pressures dropping.

EVENTS 6, 7, 8, &9:

Malfunctions occurring upon MSLI Automatic Rx trip failure.

valve closure. Automatic MSLI actuation failure.

Offsite power lost after hot bus transfer All malfunctions are preloaded. Master Pressure controller failure causes PORV SRO directs ATC to manually trip the reactor 2RCS*PCV455C to fail open.

SRO enters E-0, Reactor Trip or Safety ATC and BOP commence IOA's ofE-0.

Injection.

CRITICAL TASK: CT-1 (E-0.A) A TC verifies reactor is not tripped:

Crew manually trips the reactor from Automatic reactor trip failure.

A5-6D - is not LIT.

the Control Room before performing

Power range indication is > 5%.

the mitigation strategy of FR-S.1.

Neutron flux is not dropping.

SAFETY SIGNIFICANCE -- Failure to IAW E-0, step 1, Immediate operator action RNO, manually trip the reactor causes a ATC manually trips the reactor from BB-B or BB-A.

challenge to the subcriticality CSF beyond that irreparably introduced by A TC verifies reactor trip.

the postulated conditions.

Additionally, it constitutes an "incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy and demonstrates the inability by the crew to recognize a failure of the automatic actuation of the RPS."

BVPS-2Ll 7 NRC Scenario 2, rev 1 Page 11 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6 &7:(continued) 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 2AE or 2DF has voltage indicated.

BOP identifies that 2DF bus is de-energized and that the EDG auto started and tripped immediately.

BOP identifies that 2AE bus was previously de-energized.

BOP performs CR actions to start EDG 2-2.

BOP reports that both emergency busses are de-energized and EDG 2-2 will not start from the control room.

SRO enters ECA-0.0 ATC and BOP commence IOA's ofECA-0.0.

A TC verifies reactor trip:

A5-6D - LIT.

Power range indication is <5%.

Neutron flux is dropping.

BOP manually initiates SLI:

Verifies all MSLI & bypass valves are closed.

BVPS - 2L 17 NRC Scenario 2, rev 1 Page 12 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS S, 6 &7:(continued) ATC/BOP, sounds standby alarm, announces "Unit 2 reactor trip and loss of emergency power."

Checks if RCS is isolated:

ATC closes 2CHS* AOV200A and B.

ATC closes 2CHS*LCV460A and B.

ATC verfies PORV's closed.

ATC reports PORV 455C is open with RCS pressure decreasing.

ATC manually attempts to close open PORV.

ATC reports PORV 455C will not close and block valve is de-energized.

ATC verifies 2CHS*HCV137 is closed.

RCP's will be off due to LOOP in progress.

ATC verifies all RCP's are stopped.

Verifies total AFW flow > 340 gpm:

BOP verifies AFW flow >340 gpm.

BOP verifies Primary Plant Demineralized Water Storage Tank Level is > 85 inches.

BOP verifies generator trip:

Main Generator output brks - open.

Exciter Circuit breaker - open.

If not previously performed, BOP verifies no electrical fault alarms are in and attempts start of EDG 2-2.

Crew dispatches operator with Attachment A-1.5 to attempt local start EDG 2-2.

BVPS - 2L 17 NRC Scenario 2, rev 1 Page 13 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ROLE PLAY:

5 minutes after being dispatched to check the status of the EDGs, report that the 2-2 EDG has tripped on overspeed and will not reset, Crew requests maintenance and system engineering maintenance assistance needed. assistance to investigate EDGs.

ROLE PLAY: Crew attempts to restore offsite power using When contacted as system operator, Attachment A-1.4 prior to continuing with procedure.

report the cause of the loss of offsite power to BVPS Unit 2 is unknown and Crew recognizes offsite power is not available and that a traveling operator has been contacts system operator for status.

dispatched to investigate, ETA is -45 minutes. SRO determines offsite power is not available and continues in ECA-0.0.

NOTE: This is a continuous action Check power restored to an AC emergency bus:

step, when power comes back, the SRO

BOP verifies no voltage on AE or DF busses.

will return to this step to expedite exiting from ECA-0.0.

Select cross-tie path:

ROLE PLAY:

SRO determines that No Unit 1 4KV SBO When asked, as SM report that Unit 1 is power sources are available and continues with also in ECA-0.0. ECA-0.0 step 14.

Crew dispatches operators to stage 3FP-P-7 IA W Attachment A-1.22.

ATC/BOP places 4kv and 480v equipment in PTL.

BVPS - 2Ll 7 NRC Scenario 2, rev 1 Page 14 of 19

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ROLE PLAY: After being dispatched Close valves to isolate RCP seals:

to locally isolate valves, wait 5 minutes

ATC closes 2CCP-AOV107A, B, C then insert commands IAW HTML

BOP dispatches an operator to locally close, then report back that the RCP seals are 2CHS-178, 179, 180 and 2CHS*MOV381 isolated.

Check SG status:

BOP verifies Blowdown isolation vlvs closed.

BOP verifies Main and Bypass Feed Reg vlvs are in MANUAL with ZERO DEMAND.

Check PRZR PORV's closed:

ATC reports 2RCS*PCV455C remains stuck open with block valve de-energized .

Crew checks power is not restored to any AC Emergency Bus.

BVPS - 2Ll 7 NRC Scenario 2, rev 1 Page 15 of 19

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6 &7:(continued)

ROLE PLAY:

When the SRO is evaluating if power to at least one emergency bus is capable of being restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (ECA-0.0 step 21), provide the following role play.

ROLE PLAY: 2-2 EDG starts, output breaker closes, loads BOP verifies EDG 2-2 is running and 2DF bus As the operator at the 2-2 EDG, report sequentially load on the 2DF bus. (except for indicates voltage.

that the overspeed trip has been reset 2SWS*P21C) and, at the crew's discretion, EDG Crew recognizes power restored to 2DF Bus.

engine start selector switch can be Crew checks power restored to AC Emergency Bus.

returned to the auto start position (was Verifies at least 1 AC emergency bus is energized taken to local start to disable EDG from a BV-2 source. (EDG 2-2) during overspeed trip repairs).

When directed to select auto start, insert:

DMFDSGOlB IRF LOA-HIV002 (0 0) RESET BVPS - 2L 17 NRC Scenario 2, rev 1 Page 16 of 19

BEAVER VALLEY POWER STATIOt\i INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS8&9:

SWS pump auto start failure BOP verifies 2SWS*P21C auto started on EDG IMF PPL07B (1 180) 3 sequencer.

(preloaded)

BOP reports 2SWS*P21C failed to auto start.

Critical Task CT-25 (ECA-0.0.F)

Crew manually starts the SWS(SWE) BOP waits until discharge valve travels to full closed pump such that the EDG does not fail position and manually starts 2SWS*P21C.

because of damage caused by engine overheating.

Critical Task Crew manually closes ATC recognizes power is restored to 455C PORV the open PRZR PORV Block valve block valve, 2RCS-MOV535.

when power is restored.

ATC closes PORV 455C MOV block valve, 2RCS-MOV535.

When power is restored, SRO returns to continuous action step 10 then proceeds to step 39.

Stabilize SG pressures:

BOP manually controls SG ADV's to stabilize SG pressures.

ATC checks SI has actuated.

ATC resets SI- both trains.

BVPS -2Ll 7 NRC Scenario 2, rev 1 Page 17 of 19

BEAVER VALLEY POWER Sl ATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Crew verifies "B" train equipment has loaded onto 2DF bus.

2FWE*P23B, AFW pump

2CCP*P21B, Primary component cooling pp.

2CHS *P21 B, Charging / HHSI pump

2SIS*P21B, LHSI pump Crew verifies "B" Train Emergency Motor Control Centers have energized.

MCC*2-E02, MCC*2-E04, MCC*2-E06, MCC*2-E08, MCC*2-E10, MCC*2-El2, MCC*2-E14 EVENTS 8 & 9: (continued) Verify service water system in service:

BOP checks 2SWS*MOV107A,B,C & Dall Critical Task CT-25 (ECA-0.0.F) closed .(valves closed due to CIA signal, Crew manually starts the SWS pump however "A" train (A&C) remains open due to such that the EDG does not fail because loss of power.)

of damage caused by engine

BOP verifies 2SWS*P21C running.

overheating. If not previously started, BOP starts 2SWS*P21C.

BOP verifies SWS header press >55psig.

BOP verifies 2SWS*MOV113D open.

Due to PORV being stuck open, Select recovery procedure; conditions will not support recovery

RCS subcooling > attachment A-5.1.

without SI.

PRZR level > 17% (3 8%)

Check HHSI and LHSI flow not indicated.

SRO determines recovery cannot be accomplished without SI.

BVPS - 2Ll 7 NRC Scenario 2, rev 1 Page 18 of 19

BEAVER VALLEY POVVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE Critical Task Crew transitions to SRO transitions to ECA-0.2 Loss of All AC Crew verifies SI has been RESET.

correct recovery procedure for current Power Recovery With SL Crew verifies RWST level is> 369 inches.

plant conditions.(ECA-0.2)

BOP performs Attachment A-0.12 to manually align components to establish SI injection alignment.

Check RCP seal isolation status:

A TC verifies all CCP pumps are stopped.

ATC verifies 2CCP*AOV107A,B,C-closed.

Crew confirms report that RCP seal local isolation valves were closed.

ATC starts "B" charging pump.

ATC verifies HHSI flow on 2SIS-FI943.

Terminate scenario when the crew starts a charging pump and re-establishes HHSI flow.

BVPS - 2Ll 7 NRC Scenario 2, rev 1 Page 19 of 19

, Apoe,ndix D Scenario Outline 2L17N3

" Facility: BVPS Unit 2 Scenario No. 3 Op Test No.: 2LOT17NRC Examiners: Candidates: SRO ATC BOP Initial IC-17: 75% power, MOL, equilibrium Xe, CB "D"@ 189 steps, RCS boron - 980 ppm.

Conditions:

Turnover: Maintain 75% power, Critical Tasks: 1. Crew manually trips the Turbine before entry into ECA-2.1 (CT-13)

2. Crew manually opens high head SI isolation valves. (CT-6)

3. Crew isolates feed flow into and steam flow from ruptured SG (CT-18)

Event Malf. No. Event Type Event Description No.

(I,A) BOP, SRO 1 XMT-MSS047A 2MSS*PT476 drifts low, "A" SG steam pressure.

(TS) SRO (C, A) ATC, SRO 2 RCS04B B SG Tube Leak (AOP 2.6.4).

(TS) SRO (R) ATC Shift Manager cues crew to shut down the plant, if crew does 3

BOP, SRO not make determination.

Turbine Vibrations require turbine trip. Crew trips Reactor 4 EHC08 (C,A) BOP, SRO and Turbine fails to automatically trip, requiring manual turbine trip. (CT-13)

IMF CRF08-H14 5 (C, A) ATC Two stuck rods, requiring emergency boration IMF CRF08-P8 6 RCS04B (M) All B SGTR 550 occurs after emergency boration flow 2SIS*MOV867A and 2SIS*MOV867B fail to open on SI VLV-SIS025 7 (C, A) ATC signal, requiring manual operation to ensure high head SI VLV-SIS070 flow (CT-6)

VLV-AFW025 "B" SG steam supply to 2FWE*P22 failed open, 8 (C) BOP, SRO VLV-AFW028 (2MSS*SOV105B and 105E) (CT-18)

Break occurs between MSIVs and Containment (Fault) when 9 MSS02B (M) All MSIV close, requires transition to E-2 7E-37ECA-3.1.

i (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 .- ES-0.1.- E-O.- E-3.- E-2.- E-3.-ECA-3.l NUREG-1021, Revision 11 FENOC Facsimile r2

Appendix D Scenario Outline 2L17N3 The crew will assume the shift at 75% power, MOL, with instructions to maintain power at 75%.

2MSS*PT476 will then drift low causing indicated steam flow to reduce, feed flow will reduce in an attempt to match steam flow causing SG level to lower. IA W AOP 2.4.1, The BOP will place the "A" main feed regulating valve in manual and control SG level. The SRO will enter AOP 2.4.1 then transition to Attachment 4 of the Instrument Failure procedure. The SRO will address TS.

A steam generator tube leak (20 gpm) will then occur on the "B" steam generator, the crew will identify the conditions and enter AOP 2.6.4 to quantify the leakage. The SRO will address TS for the SG tube leak.

Based on the steam generator tube leak size, the crew will initiate an unplanned reactor shutdown in accordance with AOP 2.51.1. If necessary, the Shift Manager will provide a cue to initiate the shutdown.

After reactor power has been reduced to <70%, a high turbine vibration will occur. The SRO will direct the crew to manually trip the reactor, but the automatic trip of the turbine will fail. As a result, the BOP will depress the manual turbine trip pushbuttons {CT), and enter E-0.

The crew will transition to ES-0.1, "Reactor Trip Response", step 1 after determining SI is NOT required.

The crew will recognize that 2 stuck control rods did not insert, requiring emergency boration and a shutdown margin calculation. After establishing a flowpath to emergency borate, a SGTR on the B SG is inserted.

The crew will identify the degrading plant conditions, initiate SI, and enter E-0, step 1.

2SIS*MOV867A and 2SIS*MOV867B fail to open on SI signal, requiring the ATC to manually open those valves (CT.)

The crew will continue through E-0 and transition to E-3 due to the SGTR. The crew will isolate the ruptured SG (CT) which is complicated by a failure of the "B" SG steam supply to the turbine driven AFW pump failing open. The crew will take contingency action by manually tripping 2FWE*P22, Turbine Driven AFW pump (CT). When the crew closes 2MSS*AOV101B Main Steam Isolation Valve, insert B SG fault upstream of MSIVs and the crew will transition to E-2.

The crew will evaluate ruptured SG on step 7, and the crew will transition back to E-3, step 1.

After the crew completes a cooldown of the RCS, the fault will cause ruptured SG pressure to drop to < 250 psig above the intact SGs, requiring the crew to transition to ECA-3.1 The scenario will be terminated after the crew transitions to ECA-3.1.

Expected procedure flow path is E-0---+ ES-0.1---+ E-0---+ E-3---+ E-2---+ E-3---+ECA-3.1 NUREG-1021, Revision 11 FENOC Facsimile r2

BEAVER VALLE:Y POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE INITIAL CONDITIONS: IC-17: 75% power, MOL, equilibrium Xe, CB "D"@ 189 steps, RCS boron- 980 ppm.

ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP Normal Splash w/ Mid Power Screen, on VB-A EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S)

SHIFT TURNOVER INFORMATION

1. 75% power for the past week, MOL equilibrium conditions, shift goal is to maintain current power.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. MOL Reactivity Placard E-0 ES-0.1 E-2 E-3 Attachment A-0.11 AOP 2.4.1 AOP 2.6.4 20M-24.4.IF Attach 4 AOP 2.51.1 BVPS - 2Ll 7 NRC 3 REV3 3 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Insert the following per the simulator Insert all pre-loads required to support the preload section of the HTML file for scenano.

this scenario:

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, Simulator running. Crew assumes control of the unit.

place the simulator to RUN and commence the scenario.

BVPS - 2L 17 NRC 3 REV3 4 of22

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT t: '-l 7~

SG Steam Pressure 2MSS*PT476 slowly lowering. BOP diagnoses 2MSS*PT476 failing low.

2MSS*PT476 drifts low "A" SG Steam flow and feed flow slowly lowering. IAW AOP 2.4.1, BOP places 2FWS*FCV478, in IMF XMT-MSS047 A 21A SG main feedwater control vlv slowly MAN and adjust feed flow to restore proper SG level.

closing.

SRO establishes a control band of 44 +/- 5% and SRO enters AOP 2.4.1, Process Control Failure. transient Rx trip criteria of 25% low and 85% high for manual SG level control.

A6-9G, Loop A Steamline Pressure Low A6-9C, Loop A Steamline High Rate of Press ATC reviews ARPs.

NOTE: Change BOP identifies 2MSS*PT476 failed low.

A6-9F, Loop A Feedwater Flow> Steam Flow The steam flow signal is compensated by the steam pressure signal. The loss SRO transitions to the Feedwater Instrument BOP places 2FWS-FR478, 21A SG Feedwater Flow of a steam pressure transmitter has the Failure procedure, 20M-24.4.IF, Attachment 4, Signal Selector, in Position FT 474.

same effect on feedwater control as if a section F.

steam flow transmitter has failed, therefore the steam flow signal selector NOTE: IAW the IF procedure, the crew will switch has to be used to regain control. place the alternate CH in service within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or request a BCO be written.

BVPS - 2Ll 7 NRC 3 REV3 5 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENT 1: (continued) SRO references Tech. Specs. for 2MSS*PT476. SRO declares 2MSS*PT476 inoperable.

Tech Spec 3.3.2 Table 3.3.2-1 functions: l.e, 4.d. l and 4.d.2, Condition D, Place channel in trip condition within 72 hrs.

Tech Spec 3.3.4 Table B 3.3.4-1 function 3c, Condition A, Restore in 30 days.

Proceed with next event at LE discretion BVPS - 2L 17 NRC 3 REV3 6 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ~

EVENT 2:

20 gpm S/G tube leak - IMMEDIATE PLANT RESPONSE: ATC reports alarms to the SRO.

Insert IMF RCS04B (0 0) 30 Rad Monitor alarms (preloaded) A4-5A; Radiation Monitoring Sys Trouble - LIT BOP checks DRMS panel and determines that 2MSS-A4-5C, Radiation Monitoring Level High - LIT RQ102B is indicating a 10,000 gpd tube leak in the VCT level decreases (-0.5%/min) "B" S/G.

ATC reports VCT level decreasing.

BOP refers to the ARP and determines entry to AOP 2.6.4 is necessary.

SRO enters AOP 2.6.4 Estimate initial pri-sec leakrate SRO determines that the leak rate is> 75 gpd.

SRO monitors S/G Tube leak by performing ATTACHMENT 1 of AOP 2.6.4 and continues with procedure.

Check if PZR level can be maintained A TC determines value and trend for PZR level BVPS - 2L 17 NRC 3 REV3 7 of22

BEAVER VALLEY POWEF. STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Crew identifies "B" S/G as the affected S/G due to radiation monitor alarms. (N-16 monitor 2075)

ATC verifies V CT level can be maintained by normal makeup.

ATC verifies RCS temperature is stable at -566 F ATC maintains a constant PRZR level ATC places 2CHS*FCV122 and 2CHS*HCV186 is manual and adjusts them to maintain constant PRZR level.

EVENTS 2 & 3: (continued) SRO monitors SIG Tube leak by performing ATTACHMENT 1 of AOP 2.6.4. SRO notifies Chemistry of entry into AOP-2.6.4, requests them to obtain grab samples and identify S/G, ROLE PLAY: and quantify leakrate.

As chemistry, acknowledge need to identify S/G and quantify leakrate. SRO notifies RP of entry into AOP-2.6.4, requests surveys and analysis to identify and quantify leakrate.

As RP acknowledge need to perform surveys and analysis. Wait 5 miutes SRO determines leak rate is> 30 gpd and proceeds to then report back that the "B" Steam line ACTION LEVEL 1 of Attachment 1.

has elevated radiation levels.

ATC determines leak rate to be approximately SRO enters ACTION LEVEL 3 of Attachment 1 and 20gpm determines the requirement to be less than 50% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND in MODE 3 in the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

BVPS -2Ll 7 NRC 3 REV3 8 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 2 & 3: (continued) SRO enters AOP 2.51.1, "Unplanned Power Reduction" BOP depresses the 1st STG UB pushbutton and sets CUE: IF the crew does NOT initiate EHC setter to the desired load the shutdown, inform the SRO that BOP sets EHC setter to desired load "Shift Manager instructs you to BOP sets LOAD RA TE thumbwheel per SM/US commence a shutdown to MODE 3 at direction, NOT to exceed 5%.

2°/o/min" BOP depresses "GO" CUE: Event 4 will automatically Alert Plant Personnel Of Rapid Power Reduction BOP sounds standby alarm and announces "Unit 2 insert after Reactor power is lowered Rapid Power Reduction."

to <70%.

Place All PRZR Heaters to ON ATC Places All PRZR Heaters to ON ATC will verify automatic rod control and that TAVG is within +/-5F ofTREF.

SRO directs BOP to perform Attachment 4, "Hot ATC performs Attachment 4, "Hot Bus Transfer Of Bus Transfer OfNormal 4KV Busses To Offsite Normal 4KV Busses To Offsite Power".

Power".

SRO notifies FE Asset Utilization And SRO notifies them and provides a reason.

Duquesne Light Sysytem Control Center As Soon As Practical During Or Following The Load Adjustment.

BVPS - 2L 17 NRC 3 REV3 9 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4&5: Turbine Vibrations +2 stuck rods Main turbine bearings #4 & #5 high Bearing #4 & #5 vibrations at 15 mils, adjacent BOP acknowledges and reports bearing vibration vibration. bearings also indicate abnormally high vibration. indications.

IMF TUR01D (5 0) 15 30 0 A7-3H,Turbine Supervisory Instrument Power A TC reviews ARP.

IMF TUROlE (5 30) 150 30 0 Off/Trouble NOTE:

ARP directs an immediate turbine trip Crew determines that a manual turbine trip is if bearing vibration exceeds 14 mils warranted.

SRO directs the A TC to manually trip the reactor.

SRO directs the crew to perform the IOA's of E-0 and report when ready to read.

A5-5H, Manual Reactor Trip SRO enters E-0, "Reactor Trip or Safety Injection" ATC and BOP commence IOA's ofE-0.

ATC verifies reactor trip:

A5-6D - LIT.

Power range indication is < 5%.

Neutron flux is dropping.

BVPS - 2L 17 NRC 3 REV3 10 of 22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES I PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Critical Task: CT-13 (E-0.0} Automatic turbine trip failure. BOP verifies Turbine trip did NOT occur:

Crew manually trips the main turbine

Throttle OR Governor valves NOT closed.

before a Severe (orange path) challenge

Main Generator output brks - Not open.

develops to either the Sub-criticality or

Exciter Circuit breaker - not open.

the Integrity CSF or before transition to ECA-2.1,. whichever occurs first. BOP manually trips the turbine, then verifies:

Throttle OR Governor valves ALL closed.

SAFETY SIGNIFICANCE -- Failure to

Main Generator output brks - open.

trip the main turbine under the

Exciter Circuit breaker - open.

postulated plant conditions causes challenges to CSFs beyond those irreparably introduced by the postulated conditions. Additionally, such an omission constitutes a demonstrated inability by the crew to "take an action ... that would prevent a challenge to plant safety."

BOP verifies power to AC emergency busses:

Using VB-C voltmeters, verifies either 2AE or 2DF has voltage indicated.

BOP identifies that both 2AE and 2DF busses are energized from offsite power.

NOTE: SI may automatically actuate SI is NOT actuated nor required at this time. Check SI Status to determine if SI is required:

depending on the timing of tripping the

A TC checks CNMT press > 5psig Turbine

A TC checks PRZR press < 1860 psig

ATC or BOP checks Steamline pressure< 500 ps1g Crew determines SI is NOT required.

BVPS -2Ll 7 NRC 3 REV3 11 of 22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE CREW DETERMINES SI IS NOT REQUIRED, TRANSITIONS TO ES-0.1 STEP 1.

SRO transitions to ES-0.1 Crew alerts plant personnel of reactor trip.

Crew monitors RCS temperature for proper response:

RCS Temp- STABLE AT OR TRENDING TO 547F:

Using Tavg since RCPs are running.

NOTE: A TC verifies letdown flow is indicated.

It is likely that letdown flow automatically isolated due to low PRZR level caused by the cooldown due to turbine trip failure. The crew may recognize reason for loss of letdown and AOP 2.7.1 actions are not required.

RCS temperature maintained by condenser Crew maintains RCS temperature by verifying:

steam dumps:

Station instrument air press >90 psig.

MSIV's at least 1 open.

Condenser available.

Condenser steam dump mode selector in TAVG.

BVPS - 2Ll 7 NRC 3 REV3 12 of 22

BEAVER VALLEY POWER STA flON INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ~

SRO directs BOP to place Condenser Steam Dumps into Steam Pressure Mode by;

Set stm hdr press slightly above existing press.

Place controller in MAN.

Verify demand - ZERO.

Place in STM PRESS Mode.

Verify TAVG defeat not required OR defeats the TAVG interlock.

Place controller in AUTO.

Adjusts setpoint as necessary to maintain temp.

Crew checks feedwater status:

STOPS one feedwater pump

Verifies A5-2C(3C)(4C) 'SG 21A(21B)(21C)

Level Low-Low Reactor Trip' - NONE LIT AS FIRST OUT

RCS Tavg - <554F

ALL main feetl reg valves - CLOSED

Total feed flow to SGs - >340 GPM (available, may be throttled ifNR > 12%)

BOP controls feedwater flow to maintain NR level between 12% and 50%.

NOTE: All Control Rods - FULLY IN SERTED ATC verifies control and shutdown rods fully inserted EVENT 6: SGTR event will be in the core.

triggered as soon as emergency DETERMINES 2 RODS ARE STUCK OUT AND boration valve OPENS. INITIATES EMERGENCY BORATION.

BVPS - 2Ll 7 NRC 3 REV3 13 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE A TC initiates emergency boration flow by:

Once Emergency Boration is initiated,

Verifying at least 1 charging pump running.

550 gpm "B" SGTR occurs. "B" SG level begins to rise

Opens 2CHS*MOV350.

IMF RCS04B (3 0) 550 RCS level and press reduce

Starts in-service boric acid pump.

(Triggered on 2CHS*MOV350 opening

Verifies emergency boration flow is > 30gpm or SI actuation) on VB-A.

The crew will continue in ES-0.1 until

Verifies charging flow is >40 gpm on VB-A.

plant parameters degrade to SI

Continues boration until adequate SDM actuation. Further ES-0.1 actions are verified IAW OST 2.49.2.

not scripted.

EVENTS 6, 7, 8 550 gpm "B" steam generator tube rupture after BOP initiates SI.

emergency boration flow is established requiring the crew to initiate SI.

SRO enters E-0, "Reactor Trip or Safety ATC and BOP commence IOA's ofE-0.

Injection."

ATC verifies reactor trip:

A5-6D - LIT.

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.

BVPS - 2Ll 7 NRC 3 REV3 14 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8 (Continued) BOP verifies power to AC emergency busses:

Using VB-C voltmeters, verifies both 2AE and 2DF busses have voltage indicated.

SI is actuated and was manually actuated Check SI status:

A TC reports SI manually actuated by turning both trains' control switches as directed by SRO ATC/BOP, sounds standby alarm, announces Unit 2 reactor trip and safety injection Check if HHSI flow should be secured by checking the following:

CNMT & Secondary radiation

CNMT pressure & sump level

SG - pressures and levels

RCS subcooling

Secondary heat sink exists

RCS pressure - stable or rising

PRZR level - > 17%

SI occurred automatically Due to "B" SGWL increasing due to "B" SGTR, crew determines that SI should not be secured and goes to step 8.

BVPS - 2Ll 7 NRC 3 REV3 15 of22

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8 (Continued) 2SIS*MOV867A and 2SIS*MOV867B fail to ATC verifies SI status:

EVENT 7: MOV Failure open on SI signal.

2CHS*P21A & 2 CHS*P21C running

2SIS*P21A & 2SIS*P21B running.

VLV-SIS069

HHSI Flow NOT indicated on 2SIS-FI943.

VLV-SIS070 o Notices 2SIS*MOV867A and 2SIS*MOV867B fail to open on SI signal.

CRITICAL TASK 6: Crew manually ATC opens 2SIS*MOV867A and 2SIS*MOV867B.

opens high head SI isolation valves by the completion of A-0.11.

BOP verifies AFW status:

Both motor-driven pumps running.

Turb driven pump, all stm supply SOV's open.

AFW throttle valves all FULL OPEN.

Total AFW flow is NOT >340 gpm. (may have been preemptively reduced ifNR level adequate.)

However, SGWL in "B" SG is> 12%

List of Attachment A-0.11 Discrepancies: SRO directs BOP verify automatic actions by 2SIS*MOV867A and 2SIS*MOV867B fail to performing Attachment A-0.11, in a timely manner.

open on SI signal.

BVPS - 2L 17 NRC 3 REV3 16 of 22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8 (Continued)

RCS Temperature< 547°F, but trending to 547° Crew checks RCS Tavg stable at or trending to 547F.

F A TC verifies PRZR isolated:

PORVs - CLOSED.

Spray Valves-CLOSED.

Safety relief valves- CLOSED (use PSMS).

PRT conditions - CONSISTENT WITH EXPECTED VALUES.

Power to at least one block valve - ALL AVAILABLE.

Block valves - AT LEAST ONE OPEN (All).

ATC checks if RCPs should be stopped:

DIP between RCS pressure and highest SG pressure - <205 PSID.

Crew determines criteria for stopping RCPs is not met.

ATC/BOP 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.

BVPS - 2Ll 7 NRC 3 REV3 17 of 22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE =:]

EVENTS 6, 7, 8 (Continued) 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 is rising in an uncontrolled manner and verifies HHSI valves, 2SIS*MOV867A,B,C,D all open & transitions to E-3, "Steam Generator Tube Rupture", Step 1.

SRO transitions to E-3, Steam Generator Tube SRO directs STA to commence control room Rupture. ventilation actions. Refer to Attachment A-2.5.

A TC checks if RCPs should be stopped:

DIP between RCS pressure and highest SG pressure - <205 PSID.

Crew determines criteria for stopping RCPs is not met.

"B" SG ruptured Crew notes that "B" SG was previously identified as the ruptured SG based upon unexpected NR level rise.

BOP verifies "B" SG NR level> 12%.

SRO directs BOP to isolate feed flow to ruptured SG.

BVPS - 2L 17 NRC 3 REV3 18 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL*GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8 (Continued) 2SVS*28 NOT CLOSED ATC/BOP isolates flow from the ruptured SG.

Critical Task: CT-18 (E-3.A)

Crew isolates feed flow into and steam BOP verifies "B" SG atmospheric steam dump, flow from the ruptured SG and directs 2SVS*PCV101B, closed and raises setpoint to 100%.

operator to close isolation valve(s) operated from outside of the control SRO dispatches operator to locally close 2SVS*28.

room before a transition to ECA-3.1 BOP verifies residual heat removal valve- CLOSED.

occurs.

Isolate ruptured SG to turbine driven AFW pump.

SAFETY SIGNIFICANCE -- Failure to

BOP reports 2 motor driven AFW pps running.

isolate the ruptured SG causes a loss of SRO directs ATC/BOP to Trip the turbine-

BOP reports 2MSS*SOV105B and I05E will differential pressure between the driven AFW pump NOT close ruptured SG and the intact SGs. Upon a loss of differential pressure, the crew ATC/BOP trips turbine-driven AFW pump.

must transition to a contingency procedure that constitutes an incorrect Verify closed ruptured SG blowdown isolation valve.

performance that necessitates the crew

BOP verifies 2BDG*AOV100Bl is closed.

taking compensating action which complicates the event mitigation Close main steamline drain from ruptured SG.

strategy.

BOPcloses2SDS*AOV111Bl.

ROLE PLAY: Close 2SDS* AOV129A, RHR piping drain isolation.

5 minutes after being dispatched to

BOP closes 2SDS* AOV129A.

locally isolate 2SVS*28, insert IRF LOA-MSS010 (0 0) 0 0 Close ruptured SG main steam isol & bypass vlvs.

then report back that 2SVS*28 has been

BOP closes 2MSS* AOVIOIB.

closed.

BOP verifies 2MSS*AOV102B closed.

SG pressure -850 psig EVENT 8: VLV-AFW025 & VLV-BOP checks ruptured SG pressure - >240 PSIG AFW028 (2MSS*S0V105B and E) are preloaded malfunctions BVPS - 2Ll 7 NRC 3 REV3 19 of22

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9 (continued)

EVENT 9: MSL Break Main Steam Line Break occurs between MSIV s SRO transitions to E-2 and Containment when the MSIV s close.

Verify CREVS actuated.

SRO transitions to E-2, "Faulted Steam ATC/BOP reports CREVS not actuated.

Generator Isolation", Step 1.

SRO directs ATC/BOP to actuate both trains of ROLE PLAY: Outside Operator heard CREVS using the CONTROL ROOM EMERG AIR loud noise in MS valve area and exited the SUP ACTUATION pushbuttons, area immediately after closing 2SVS*28

Verifies the control room air intake and exhaust dampers are CLOSED.

Verifies 2HVC*FN241A running after time delay.

SRO requests a BV -1 operator to verify proper CREVS actuation and place CR air intake and exhaust dampers control switches in CLOSE.

SRO directs STA to commence Control Room ventilation actions. Refer to Attachment A-2.4.

ATC/BOP manually initiates steamline isolation Checks all indicating lights with YELLOW SLI mark

-LIT "A" & "C" SG pressures are stable Crew identifies "B" as the faulted SG "B" SG pressure is lower than "A" and "C" AND is lowering BVPS -2Ll 7 NRC 3 REV3 20 of22

BEAVER VALLEY POWER STATION c:=JNSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Isolate Faulted SGs BOP checks Feedwater Isolation (GREEN FWI marks) - PREVIOUSLY VERIFIED

Closes AFW throttle valves on "B" SG 2FWE*HCV100C, D.

Checks Residual Heat Release Valve-CLOSED 2SVS*28 was closed previously

Checks 2SVS*28 is closed

Recognizes that Turbine-driven AFW Pump Steam Supply Isolation Valve 2MSS*SOV105B and E is NOT closed o Understands that the AFW pump was tripped and will NOT close 2MSS*16

Atmospheric Steam Dump was already closed.

BOP verifies SG Blowdown Isolation Valve, 2BDG* AOVlOOB 1 is closed

BOP verifies closed 2SSR*AOVl 17A,B,C SG Blowdown Sample Outside CNMT Isol Vlvs PPDWST should be >300 inches BOP/ATC checks 2FWE-TK210 PPDWST Level is Greater Than 150 inches.

SG Tubes are not intact on "B" SG SRO determines "B" SG tubes are NOT intact due to secondary radiation NOT CONSISTENT WITH PRE-EVEN VALUES.

EXAMINER NOTE: SRO Transitions to E-3, "Steam Generator Tube SRO Transitions to E-3.

Procedural Steps 1-5, the crew is re- Rupture," Step 1.

checking everything performed previously. No actions. See page 19 of this scenario.

BVPS - 2L 17 NRC 3 REV3 21 of 22

~

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Initiate RCS Cooldown SRO determines the required core exit temperature based on the "B" SG pressure.

PRZR Press <2000 PSIG BOP blocks low steamline pressure SI.

BOP SRO directs BOP to dump steam at the max rate

reports that no MSIV s are open from intact SGs using SG atm stm dumps and

dumps steam using 2SVS*PCVI01A and C EXAMINER NOTE: RHR valve

stops cooldown when core exit TCs are less Step 6.j is NOT a HOLD step.

than the required temperature and maintains core exit TCs -LESS THAN REQUIRED TEMPERATURE

Checks Narrow range level-GREATER THAN 12%

Controls feed flow to maintain narrow range level between 26% and 50%

Check PRZR PORVs And Block Valves ATC reports:

Power is AVAILABLE to block valves

PORVs-CLOSED

3 Block Valves OPEN BOP:

Resets SI

Resets CIA And CIB

Reports that ruptured SG pressure is not EXAMINER CUE: Terminate the stable or rising scenario after the SRO successfully transitions to ECA-3.1 or when they "B" SG Pressure is -520 psig and lowering, but SRO transitions to ECA-3.1, "SGTR With Loss Of brief their intentions and is dependent on crew response Reactor Coolant - Subcooled Recovery Desired," Step expectations of going to ECA-3.1.

1.

BVPS - 2L 17 NRC 3 REV3 22 of22

p ;t t P A,ppen d"1x D scenano *otru me 2L17N4 Facility: BVPS Unit 2 Scenario No.:_4 Op-Test No.: 2LOT17 NRC Examiners: Operators: SRO ATC BOP Initial Conditions: IC (172) 4.9% power, BOL, CB "D" @ 110 steps, RCS Boron - 1750 ppm Turnover: Raise power to 10-14% and load the turbine generator in accordance with procedure for plant startup Critical Tasks:

1. Start the Turbine Driven AFP before transition out of E-0 (CT-4)

2. Manually initiating containment isolation phase A (CT-11)

3. Manually trip the RCPs (CT-16)

Event Malf. No. Event Type* Event No. Description 1 (R) ATC Raise power 10-14%

(N) SRO 2 XA4i028L (C,A) ATC Blender fails to stop after dilution is complete.

3 VLV-CFW022 (I, A) BOP Hotwell level high dump valve, 2CNS-MOV105 spuriously opens, requires closinq valve.

4 NIS07B (l,A) ATC N36, Intermediate Range power fuse blows (TS) SRO 5 RCS02A (C,A) ATC "A" Loop RCS Leak, AOP 2.6.7, TS (TS} SRO 6 CNH-CHS01A (C,A) ATC 2CHS*FCV122 fails to fully close, requires closing of 289 & use of VLV-CHS013 2CHS*HCV186 7 RCS02A M "A" loop, SBLOCA ramps in, requires manual reactor trip 8 VLV-AFW024 thru (C,A) BOP Turbine driven AFW pump auto start failure VLV-AFW029

.. 9 PPL08B (C,A), BOP Containment Isolation phase A Train B fails to actuate. Various VLV-SEA015 Train A valves fail to automatically close VLV-CAS002 004

(N}ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Procedure Flowpath: E-0"7 E-1 "7 ES-1.2 The crew will take the shift at 4.9% power with instructions to raise power to 10-14% to place the Turbine in service IAW the reactivity plan and 20M-52.4A. The A TC will initiate a dilution and withdraw the rods. No malfunctions will occur until the desired power increase is observed.

NUREG-1021, Revision 10 FENOC Facsimile r2

Appendix D Scenario Outline 2L 17N4 After power raise is initiated, a blender malfunction will occur such that a dilution will STILL be occurring after it is supposed to stop. The A TC will stop the blender malfunction by placing the Boric Acid Makeup Blender Control Switch in STOP.

2CNS-MOV105, Condensate Spill Bypass valve, fails open, sending condensate to 2WTD-TK211, Turbine Plant Demineralized Water Day Tank, causing hotwell level to drop. The BOP will close the valve.

An Intermediate Range blown power fuse blows N36, requiring the crew to enter AOP, take the channel out of service and evaluate the TS.

The 8 gpm reactor leak on the "A" Loop inside containment is inserted. The crew will balance the inventory and determine leak rate size IAW 20M-53C.4.2.6.7, Excessive Primary Plant leakage. They will check PRT conditions and rad monitors. The crew will instruct chemistry to take samples and a radiation protection survey.

The crew will adjust steam dumps and rods to stabilize Tavg.

The crew will then isolate letdown and charging flow, but 2CHS*FCV122 will fail to close, requiring 2CHS*MOV289 to be closed. 2CHS*HCV186 will be adjusted to obtain NET RCS input (seal injection- seal leakoff) of 10 GPM. 2CHS*MOV289 will be reopened and PRZR level will be maintained by controlling 2CHS*FCV122 and 2CHS*HCV186. The crew will restore charging and letdown to service.

At Chief Examiner's discretion the leak ramps up to a 1400 gpm SBLOCA where the reactor will trip on/requiring a manual reactor trip on low PRZR pressure. The crew will enter E-0.

The motor driven AFP, 2FWE*P23A fails to start. 2FWE*P23B starts with sheared shaft. The Turbine driven AFW Pump, 2FWE*P22, will fail to start, requiring the BOP to start it (CT)

RCP trip criteria will be met in E-0, requiring the ATC to trip the RCPs (CT). This is a symptomatic response/unexpected condition action for both E-O/E-1. This is required to be performed prior to transition out of E-0.

At step 1O of E-0, crew will perform A-0.11, "Verification of Automatic Actions." Phase A Cl train B, will fail to actuate, requiring the crew to manually actuate train B. Several valves on train A will fail to close, also requiring manual closure to prevent a potential radiation release. Refer to A-0.2, Containment Isolation Phase A Checklist (CT). This has to be done before attachment is reported as complete.

The crew will have to energize the Source Range detectors due to previous intermediate range blown power fuse.

At step 16 in E-0, crew transitions to E-1, "Loss of Reactor or Secondary Coolant", step 1.

The crew will continue through E-1, where they will transition to ES-1.2 "Post LOCA Cooldown AND Depressurization."

After the crew initiates a cooldown IAW ES-1.2 step 12 and at the Chief Examiner's discretion, terminate the scenario.

The expected procedural flowpath is: E-07 E-17 ES-1.2 NUREG-1021, Revision 10 FENOC Facsimile r2

BEAVER VALLEY POWER STATION INITIAL CONDITIONS: IC (172) 4.9% power, BOL, CB "D"@ 110 steps, RCS Boron - 1750 ppm ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP Normal Splash w/ Hi Power Screen, on VB-A EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S)

SHIFT TURNOVER INFORMATION

1. Raise power to 10-14% to place turbine online.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. EOL Reactivity Placard E-0 E-1 ES-1.2 Attachment A-0.6 Attachment A-0.11 20M-7.4.L, Blender Dilution Operation IAW 20M-22A.4.AAE, Condensate Spill Valve Bypass Valve AOP 2.6.7 AOP 2.2.lB, Intermediate Range Channel Malfunction Attachment A-1.27 BVPS -2Ll 7 NRC 4, r3 3 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE { EXPECTED STUDENT RESPONSE Insert the following per the simulator preload Insert all pre-loads required to support the section of the HTML file for this scenario: scenario.

BVPS-2Ll 7 NRC 4, r3 4 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE 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, Simulator running. Crew assumes control of the unit.

place the simulator to RUN and commence the scenario.

BVPS - 2Ll 7 NRC 4, r3 5 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE

\0 ,o EVENT 1: Raise power to 10-14% SRO opens 20M-52.4.A Normal Plant Startup, reactor power Startup procedure, Raising Power from 5% to IA W reactivity plan, ATC dilutes and withdraws rods increase to 15% to support turbine Full Load Operation, 20M-52.4.A, step 7.a is in to raise reactor power to> 15%.

startup. progress.

When Rx power is >5%, crew identifies and announces entry into Mode 1.

ATC initiates control rod withdrawal and dilution IAW the reactivity plan.

Places Boric Acid Makeup CS to STOP.

NOTE:

Verifies 2CHS*FCV114A set to desired flow rate.

Reactivity plan requires 200 gallons

Set 2CHS-FQIS168A, Total MIU from Blender dilution and 7 rod steps to raise power Flow Totalizer, to desired dilution quantity.

to 10%. Crew may elect to add total

Reset 2CHS-FQIS168A.

dilution volume in multiple steps.

Verify 2CHS-FQIS113, Boric Acid Flow to Blender Flow Totalizer, is set to zero.

Places Mode Selector switch in DIL or ALT DIL.

Places Boric Acid Makeup CS to START.

Verify 2CHS*FCV114A opens.

Verify correct flow rate on 2CHS-FR113.

When 2CHS-FQIS168A reaches preset value, verify dilution automatically stops.

BVPS-2Ll 7 NRC 4, r3 6 of25

BEAVERVALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 2: ATC places the Boric Acid Makeup Blender Control When the dilution is supposed to stop, the Switch in STOP IAW 20M-7.4.L XA4i028L: Blender fails to stop blender keeps running. ~ thereby still diluting the boron concentration in the RCS and inserting positive reactivity.

EVENT 3: Condensate Spill Valve Bypass Valve, 2CNS- SRO directs BOP to close 2CNS-MOV105, MOV105 spuriously opens. A6-5F, Condenser Condensate Spill Valve Bypass Valve IAW 20M-(Preloaded) occurs at 7% Rx power Hotwell Level High/Low comes in. 22A.4.AAE, Condenser Hotwell High/Low.

VLV-CFW022 ROLE PLAY: Turbine Plant Operator to check for leaks.

NOTE: At LE discretion, insert event 4 after Rx power is > 10% AND the crew has inserted Rx Trip Blocks BVPS-2Ll 7 NRC 4, r3 7 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4: SRO enters AOP 2.2. lB, Intermediate Range BOP performs:

Channel Malfunction, Step 5.

Check reactor power-GREATER THAN P-NIS07B: N36 instrument power range 10 fuse blows A4-4E: NIS Compensator Comparator Trouble

Momentarily Place Intermediate Range Block Train A and Train B switches to NOTE: May have already blocked IR INTERRANGE BLOCK.

train A & B iL. -~; (.f-

Place caution tags on Source Range Trip f I" Block/Reset Train A and Train B switches, "Manually unblock source range during plant shutdown".

Verify NR-45 recorder selected to OPERABLE channels

Place Level Trip switch for N36 to BYPASS o Verify Annunciator A4-5E, "NIS Source/Int Range High Flux Trip Bypass" in alarm due to failed channel.

o Verify status light "Level Trip Bypass" on drawer - LIT.

SRO evaluates T.S. and enters T.S. 3.3.3. condition A.

and determines T.S. 3.3.1 condition F.(1 OR 2) is N/A EVENTS:

IMMEDIATE PLANT RESPONSE:

8 gpm unisolable "A" loop RCS leak ATC reports indications of a RCS leak inside CNMT.

inside CNMT. PRZR pressure begins decreasing.

PRZR spray valves close.

IMF RCS02A (0 0) 8 0 0 A4-5A/5C, DRMS Trouble(Alert)/ High Alarms CNMT Radiation monitors; 2RMR-RQ303A, ALERT/HIGH alarms CNMT humidity increasing.

VCT level slowly decreasing.

BVPS -2Ll 7 NRC 4, r3 8 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 5: (continued) BOP reviews ARPs.

BOP verifies valid Rad monitor indication using ARP.

SRO enters AOP 2.6.7, Excessive Primary Plant ATC checks if PRZR level can be maintained >5%.

Leakage A TC checks if leakage is RCS/CV CS leakage by:

Checking CNMT, P AB and safeguards conditions are consistent with pre-event.

Crew determines CNMT conditions are NOT consistent with pre-event based upon rising sump levels and CNMT radiation levels.

SRO transitions from AOP 2.6.7, step 2 to step 6 Crew verifies RCS temperature is stable.

ATC determines 2CHS*FCV122 is not maintaining constant PRZR level in AUTO and places 2CHS*FCV122 in MANUAL to stabilize PRZR level.

Crew checks VCT level trend and determines that VCT level is DROPPING at< 0.7%/min. and reports to SRO that leakrate is <10 gpm but may be isolable.

NOTE: Due to dynamic nature of SRO recognizes TS 3.4.13 Condition A, is applicable event, a followup question regarding for unidentified leakage.

applicable TS may be necessary.

BVPS -2Ll 7 NRC 4, r3 9 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ATC quantifies leakage & checks for CVCS leakage by:

Isolating charging/letdown by closing valves:

2CHS* AOV200A, B, C Letdown orifice isol.

2CHS*LCV 460A & B Regen Ht Ex inlet.

Reports 2CHS*FCV122, charging flow control EVENT 6: ATC recognizes that 2CHS*FCV122 fails to vlv does not close fully.

FULLY close. o Closes 2CHS*MOV289

ATC adjusts RCP seal injection flow to obtain NET RCS input of 10 gpm.

Crew determines PRZR level is rising.

Adjusts 2CHS*HCV186 to obtain 6-9 gpm per RCP SRO informs Shift Manager to evaluate EPP due to RCS leakrate being < 10 gpm and is not isolated by charging and letdown.

ATC determines V CT level can be maintained with normal makeup.

ATC determines PRZR level is being maintained in AUTO. ATC opens 2CHS*MOV289 and controls 2CHS*FCV122 and 2CHS*HCV186 as necessary to maintain at approximately programmed PRZR level

.,., NRC 4, r3 10 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 6: (continued) Crew restores charging and letdown to service by:

Adjusting 2CHS*FCV122 to obtain 30-50 At LE discretion, insert EVENT 7: gpm, SBLOCA, before restoring letdown

Verifying PRZR level is > 14%.

and charging.

Placing 2CHS*PCV145 in MAN and at 50%.

Opening 2CHS*LCV460A, B.

Opening 2CHS* AOV200A, Bas desired.

Adjusting 2CHS*PCV145 until backpressure is -260 psig.

Placing 2CHS*PCV145 in AUTO.

Placing 2CHS*FCV122 in AUTO.

EVENT 7: SBLOCA Pressurizer level and pressure decreases rapidly. A TC reports dropping pressurizer level and pressure IMF RCS02A (0 0) 1400 60 0 CNMT sump level rises. along with CNMT sump alarms.

CNMT sump alarms actuate.

A2-2B, UIL trouble Al-2G, Incore Instru RM/CNMT sump lvl high SRO instructs A TC to manually trip the Reactor ATC manually trips the reactor and transitions to E-0, Reactor Trip or Safety Injection ATC and BOP commence IOA's ofE-0.

A TC verifies reactor is tripped:

A5-6D, "Turbine Trip Due to Reactor Trip" -

is LIT.

Power range indication is LESS THAN 5%.

Neutron flux is DROPPING.

BVPS-2Ll 7 NRC 4, r3 11 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8 & 9: (continued) BOP verifies turbine trip:

Throttle OR Governor valves ALL CLOSED.

Main Generator output bkrs-OPEN.

Exciter Circuit breaker- OPEN.

BOP verifies power to AC emergency busses:

Using VB-C voltmeters, verifies both 2AE and 2DF busses have voltage indicated.

Check SI status:

ATC reports SI automatically actuated and manually actuates SI by turning both trains' control switches.

ATC/BOP, sounds standby alarm, announces Unit 2 reactor trip and safety injection.

EVENTS 7, 8 & 9: (continued) HHSI Flow Should NOT be SECURED Check if HHSI flow should be secured by checking the following:

CNMT & Secondary radiation

CNMT pressure & sump level

SG - pressures and levels

RCS subcooling

Secondary heat sink exists

RCS pressure - stable or rising

PRZR level - 17%

SI occurred automatically Based on NOT meeting the CNMT parameters, crew determines NOT to secure HHSI flow and proceeds to step 8.

BVPS-2Ll 7 NRC 4, r3 12 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 7, 8 & 9: (continued) SRO instructs the ATC to TRIP RCPs A TC Verify SI Status:

Charging pumps - TWO RUNNING EXAMINER NOTE:

LHSI - BOTH RUNNING

HHSI Flow - INDICATED CT-16: Trip the RCPs before exiting E-0 Based on meeting RCP trip criteria, A TC will trip the RCPs.

trip criteria will be met about this time based on the DIP and having indicated HHSI flow SAFETY SIGNIFICANCE-- Failure to trip the RCPs under the postulated plant conditions leads to core uncovery and to fuel cladding temperatures in excess of 2200°F, which is the limit specified in the ECCS acceptance criteria. Thus, failure to perform the task represents "mis-operation or incorrect crew performance which leads to degradation of the fuel cladding barrier to fission product release" and to "violation of the facility license condition."

ROLE PLAY: AFW PUMPS Verify AFW Status Terry Turbine: No obvious damage

NO Motor Driven AFW Pump is RUNNING 2FWE-P23A: Overcurrent trip and cannot be manually started 2FWE-P23 B: Sheared shaft

TDAFW Pump Stm Supply Isol Valves - NOT FULL OPEN CT-4: Start TDAFW pump before

Manually opens steam supply valves transitioning out of E-0

AFW Throttle Valves-FULL OPEN

Total AFW Flow - GREATER THAN 340 GPM BVPS-2Ll 7 NRC 4, r3 13 of 25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8 & 9: (continued) SRO instructs the BOP to Perform A-0.11, BOP performs Attachment A-0.11, Verification of "Verification of Automatic Actions", In A Automatic Actions.

Timely Manner List of Attachment A-0.11 Discrepancies: A-0.11 actions are attached at the end of the scenario.

TDAFW Pump required manual start.

Both motor driven AFW pumps failed to start SR required manual energization due to N36 failure.

CIA Train B failed to actuate CIA Train A valves fail to actuate:

2CHS-MOV378 2IAC*MOV133 2IAC*MOV130 RCS COLD LEG Temperature is lower than 547 A TC verifies F AND trending DOWN

steam dumps are CLOSED

reheat steam isolation o 2MSS-MOV100A,B - CLOSED o Resets Reheater Controller o Reduces BUT MAINTAINS AFW Examiner Note: RCS CID will be flow > 340 GPM until NR level is >

occurring due to SI flow. If crew 31 % in at least one SG recognizes this, they may not initiate

May initiate SLI SLI ATC verifies PRZR PORVs and Spray Valves Closed

PORVs-CLOSED

Spray Valves - CLOSED

PRZR Safety Relief Valves - CLOSED

Power to at least one block valve -

AVAILABLE (3)

Block valves-AT LEAST OPEN (3)

BVPS - 2Ll 7 NRC 4, r3 14 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8 & 9: (continued)

NOS/Gs are Faulted Crew determines no S/Gs are Faulted All S/Gs Tubes are intact Crew determines all S/G tubes are intact RCS loop "A" is NOT intact Check if RCS is Intact:

Crew determines the following is NOT consistent with pre-event values o CNMT Pressure o CNMT Sump Level o CNMT Radiation ATC performs the following:

Verify High Head SI Cold Leg Isol Vlvs (downstream)-BOTH OPEN o 2SIS*MOV867C,D

Verify High Head SI Cold Leg Isol Vlvs (upstream) - BOTH OPEN

-,( o 2SIS*MOV867 A,B

\0 \

SRO transitions to E-1, "Loss Of Reactor Or Crew checks if CREVS should be actuated:

Secondary Coolant", Step 1

Control Room Radiation Monitor 2RMC*RQ201,202, - NOT IN HIGH ALARM

CIB - HAS NOT OCCURRED Crew determines CREVS does not need to be actuated.

BVPS - 2Ll 7 NRC 4, r3 15 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8 & 9: (continued) A TC checks if RCPs should be stopped:

DIP between RCS pressure and highest SG pressure - <205 PSID

Criteria for stopping will be met.

RCPs previously TRIPPED.

SRO dispatches An operator to Energize Valves IA W A-0.6 ROLE PLAY: ATC/BOP dispatches an operator to energize valves When dispatched to perform Attach IA W Attachment A-0.6, "Cold Leg Recirculation A-0.6, wait 5 minutes, insert following Component Verification."

commands then report complete.

IRF LOA-LOV093 (0 0) RACKIN IRF LOA-LOV102 (0 0) RACKIN IRF LOA-LOV094 (0 0) RACKIN IRF LOA-LOV103 (0 0) RACKIN IRF LOA-LOV095 (0 0) RACKIN IRF LOA-LOV104 (0 0) RACKIN IRF LOA-LOV096 (0 0) RACKIN IRF LOA-LOVlOS (0 0) RACKIN BVPS - 2Ll 7 NRC 4, r3 16 of 25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 7, 8 & 9: (continued) CIB Not actuated WHEN CIB is actuated Then Perform step 4.b and continue with Step 5.

Crew may not get to 4.b 4.b-d

Recirc spray HXs-SERVICE WATER FLOW TO ALL 4 HXS

RWST Level - LESS THAN OR EQUAL TO 381 INCHES

Verfiy Recirc Spray Pumps-NOT CAVITATING ATC/BOP checks if any SGs are faulted:

SGs are NOT faulted

Pressures in all SGs-ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY SG COMPLETELY DEPRESSURIZED Crew determines NO SGs are faulted.

BOP checks intact SG levels:

NR levels - > 12% [31 % ADVERSE CNMT]

Controls feed flow to maintain NR level between 12%

[31 % ADVERSE CNMT] and 50%.

BVPS -2Ll 7 NRC 4, r3 17 of25

BEAVER VALLEY POWER STA-CION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE

.=:]

EVENTS 7, 8 & 9: (continued) 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 - All open.

SI FLOW CANNOT BE REDUCED. ATC/BOP checks if SI flow can be reduced:

RCS subcooling based on core exit TCs >41 F

[59F ADVERSE CNMT]

Secondary heat sink is available.

RCS pressure is not stable or rising.

Based on RCS pressure trend and subcooling, crew determines SI termination conditions are not satisfied, SRO remains in E-1.

A TC/BOP checks if CNMT spray should be stopped.

Determines CIB has not occurred at this time therefore no quench or recirc spray pumps are running.

A TC resets SI and CIA.

BVPS - 2Ll 7 NRC 4, r3 18 of25

BEAVER VALLEY POVVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8 & 9: (continued) ATC checks if LHSI pumps should be stopped.

NOTE: RCS pressure is dropping ATC determines RCS pressure >225 psig BUT is RCS pressure trend at this point is NOT stable or rising therefore the running LHSI pump dependent upon crew procedural is NOT to be STOPPED.

progression, pressure trend may not support SID of LHSI at this time.

BOP checks ifEDGs should be stopped.

SRO directs the BOP to stop unloaded EDGs using Attachment A-1.27.

SRO directs ATC/BOP to perform Attachment ATC/BOP verifies all components in Attachment A-0.6 and verify cold leg recirculation A-0.6 are available.

capability.

Crew recognizes Aux building and Safeguards radiation - CONSISTENT WITH PRE-EVENT and leak is not outside containment.

SRO determines TSC is not activated:

ROLE PLAY: SM consults with TSC staff to determine

ATC monitors nuclear instrumentation to If SRO requests TSC status - report whether samples can be obtained. confirm adequate shutdown margin.

TSC not yet activated.

SRO dispatches an operator to perform Attachment A-1.1 to start additional equipment to support recovery.

ATC checks if cooldown and depressurization is required:

Determines RCS pressure is >225 psig.

SRO transitions to ES-1.2, "Post LOCA Crew determines transition to ES-1.2 is appropriate at Cooldown And Depressurization", Step 1. this time.

BVPS - 2Ll 7 NRC 4, r3 19 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8 & 9: (continued)

ATC resets SI, CIA and CIB.

(all signals were previously reset in E-1).

ATC checks LHSI pumps - no signs of cavitation.

Establish Domestic Water System Cooling to Station Air Compressors:

BOP opens 2CCS-AOV118, Domestic Water to Station Air Compressor Valve.

Orders Plant Operator to CLOSE 2CCS-78,83 ,84, Station Air Compressor Isol Vlvs Orders Plant Operator to OPEN 2CCS-229,230, Station Air Compressors Discharge Drain Vlvs.

BOP verifies Station Instrument air is available;

Station Instrument Air > 90 psig Establishes Instrument Air to CNMT

Cross Connet station air to CNMT air by opemng

2IAC-MOV131

2IACMOV130

Check instrument air header pressure> 85 psig BOP verifies all AC busses energized by offsite pwr.

ATC places all PRZR heaters in PTL.

BVPS -2Ll 7 NRC 4, r3 20 of25

BEAVERVALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE A TC checks if LHSI pumps should be stopped;

LHSI pumps - 2 RUNNING

RCS pressure is> 225 PSIG (250 PSIG ADVERSE CNMT)

Check RCS pressure - DROPPING ATC determines LHSI should NOT be stopped BOP checks intact SGWLs

NR level - GREATER THAN 12% [31 %

ADVERSE CONTAINMENT]

Control feed flow to maintain NR level to btwn 12% [31 %] and 50%.

EVENTS 7, 8 & 9: (continued) Monitor Shutdown Margin during RCS cooldown.

Requests liquid samples hourly

CNMT sump; pH, boron concentration, etc

CNMT atm; radioactivity and hydrogen.

Verify boron concentration > 200F boron concentration Initiate Cooldown to MODE 5 Maintain cooldown rate in RCS cold legs - LESS THAN lOOF/HR

Intiate trend of RCS cold leg temp and press

Initial every half hour

Refer to attach A-4.1 Press will be <2000 psig ATC; Press <2000#, BLOCK low steamline pressure SI Check Station Air pressure > 90 PSIG BVPS-2Ll 7 NRC 4, r3 21 of 25

BEAVER VALLEY POWER STATION C INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Terminate Scenario: Terminate scenario at LE discretion AND after establishing a stable cooldown less than lOOF /HR.

BVPS-2Ll 7 NRC 4, r3 22 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-0.11 'Verification of BOP performs Attachment A-0.11, 'Verification of Automatic Actions' performed in a Automatic Actions' as follows:

timely manner.

Checks both EDGs running with SWS valve alignment and ventilation in service.

Verifies power to both AC emergency busses.

Checks 2HVS*FN204A or 2HVS*FN204B running.

Ensure reheat steam isolation:

Verify 2MSS-MOV100A and B-closed.

Reset reheater controller.

Verify 2GSS-MOV204, spillover vlv, closed Check if main steamline isolation required:

CNMT pressure - >7 PSIG

-OR-

Steamline pressure - <500 PSIG

-OR-

Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS.

If steamline isolation is required, verifies SLI by checking all YELLOW SLI marks-LIT.

If steamline isolation is not required continues on.

BVPS - 2Ll 7 NRC 4, r3 23 of25

BEAVER VALLEY POWER STATIO:\J INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE J Attachment A-0.11 - (continued) Establish domestic water system cooling to station air NOTE: compressors:

BOP may have already pre-emptively

Opens 2CCS-AOV118.

opened 2CCS-AOV118 to provide

Verifies at least 1 air compressor is running.

cooling to the station air compressors.

Verifies at least 1 CCP pump is running unless a CIB has occurred.

Align neutron flux monitoring for shutdown:

SR require manual energization.

Verifies SR CHs energized when IR <lE-10.

Transfer 2NME-NR45, nuclear recorder, to operable SR and IR displays.

Check CIB and CNMT spray status:

CNMT pressure-has remained <11 PSIG.

Verify service water system in service:

SWS pumps - TWO RUNNING.

Check SWS header pressure - >55 psig.

SWS pump seal water pressure - NOT LOW.

Verify both CNMT hydrogen analyzers running:

2HCS*SOV100Al, Bl -CNMT sample amber lights

-LIT.

BVPS - 2Ll 7 NRC 4, r3 24 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS/ PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-0.11- (continued) Verify ESF equipment status:

Critical Task: CT-4 {E-0.F) 2FWE*P23A tripped & 2FWE*P23B had a

Verify SI status by checking all RED SIS marks Crew establishes the minimum required sheared shaft -LIT.

AFW flow rate to the SGs before

Verify CIA by checking all ORANGE CIA transition out of E-0, unless the marks-LIT.

transition is to FR-H.1, in which case

Verify FWI by checking all GREEN FWI the task must be initiated before RCPs marks-LIT.

are manually tripped in accordance with FR-H.1.

Verify source range channels energized with audible indication functioning properly, adjusts multiplier switch and volume as necessary.

Attachment A-0.11 - COMPLETE Discrepancies: Upon completion, report any discrepancies to SRO.

2FWE*P23A tripped & 2FWE*P23B had a sheared shaft 2FWE-P22 required manual start CIA Train B failed to actuate CIA Train A valves failed to actuate:

2CHS-MOV378 2IAC*MOV133 2IAC*MOV130 SR required manual energization.

BVPS -2Ll 7 NRC 4, r3 25 of25

ML18102A982

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