ML032591138

Draft - Section B Operating

ML032591138
Person / Time
Site:	Susquehanna
Issue date:	08/01/2003
From:	Roush K Susquehanna
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-387/03-301, 50-388/03-301
Download: ML032591138 (137)

Text

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 I Facility: Susuuehanna Date of Examination: 8111-8115 2003 1 Exam Level (circle one): Ro Operating Test No.:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title 1 Type Code*

Safety Function

a. 21 5005 A2.02 3.6/3.7 Bypass an APRM Channel Trip Input

b. 264000 A2.01 3.513.6 I DyS 7

6 Start D/G for surveillance (1)

e. 223001 A2.07 (4.W4.3) D,S, 5 Venting Suppression Chamber within off-site release limits - ES-I 73-001, Section 4.2, Vent Suppression Chamber using two inch vent bypass to SGTS.73.EO.OOl.101 (2) 4 9

Transfer Containment R f . 202001 A2.10 3 3 3 . 9 D, S , E/A, L 1 Respond To A Reactor Recirc Pump Dual Seal Failure IAW ON-164-003

g. 209001 A2.01 3.8/3.7 2 Perform Manual S/U of Core Spray IAW OP-151-001

h. 239001 A4.01 (4.W4.0) 3 Main Steam Line Isolation and Quick Recovery in Accordance with ON-781-007 (2) in-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. 262001 K4.04 2.8/3.1 1 N,R,A I 6 Perform Monthly Surveillance of 4KV Bus Undervoltage Relays

j. 295016 AA1.08 (4.0/4.0)

Perform manual operation of the SRVs Valves from the Remote Shutdown Panel as required by ON-700-009OO.ON.015.703 (3)

k. 271001 A4.09 3.6/3.6 1 D, EIA, C I 4 Bypass RClC Temp or Differential Temperature Isolation signal IAW ES-150-001 I

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, NUREG-I 021, Draft Rev 9 Susquehanna Facsimile 2003 NRC Exam Rev. I

ES-301 Control Room/ln-Plant Systems Outline Form ES-30I-2 Facility: Susuuehanna Date of Examination: 8/1I-8/15 2003 Exam Level (circle one): SR0-I Operating Test No.:

Control Room Systems (8 for RO;7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Safety Code* Function

a. 215005 A2.02 3.6/3.7 Bypass an APRM Channel Trip Input

b. 264000 A2.01 3.513.6 I DyS N, A9 s 7

6 Start D/G for surveillance ( I )

c. 223001 A2.07 (4.W4.3) 0 9 s 9 E 5 Venting Suppression Chamber within off-site release limits - ES-I 73-001, Section 4.2, Vent Suppression Chamber using two inch vent bypass to SGTS.73.E0.001.101(2)

d. 202002 A2.05 (3.814.0) s 9 A 4 RESET Recirc Pump Limiter #2 Runback in accordance with ON-164-002 (2)

e. 272000 A I .01 3.2/3.2 Transfer Containment Radiation Monitor Sample Pumps IAW OP-179-003

f. 202001 A2.1 0 3 3 3 . 9 I NS D, S, E/A, L 9

I Respond To A Reactor Recirc Pump Dual Seal Failure IAW ON-164-003

g. 209001 A2.01 3.8/3.7 2 Perform Manual S/U of Core Spray IAW OP-151-001 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

h. 262001 K4.04 2.8/3.1 Perform Monthly Surveillance of 4KV Bus Undervoltage Relays

i. 295016 AA1.08 (4.014.0) 0 9 RY HA, 7 Perform manual operation of fhe SRVs Valves from the Remofe A Shutdown Panel as required by ON-100-00900.0N.015.103 (3)

j. 271001 A4.09 3.6/3.6 I D, E/A, C 1 4 Bypass RClC Temp or Differential Temperature Isolation signal IAW ES-150-001 I

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (E/A)Emergency/Abnormal, (E)SF NUREG-I 021, Draft Rev 9 Susquehanna Facsimile 2003 NRC Exam Rev. 1

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Susquehanna Date of Examination: 8\11-8/15 2003 I( Exam Level (circle one): SR0-U Operating Test No.:

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Safety Code* Function

c. 223601 A2.07 (4.Y4.3) 0, s, E 5 Venting Suppression Chamber within off-site release limits - ES-173-007, Section 4.2, Vent Suppression Chamber using two inch vent bypass to SGTS.73.EO.OO1.101(2)

e. 272000 A I .01 3 2 / 3 2 N, s 9 Transfer Containment Radiation Monitor Sample Pumps IAW OP-I 79-003

g. 209001 A201 3.8/3.7 Perform Manual S/U of Core Spray IAW OP-151-001 E/A, E In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. 262001 K4.04 2.8/3.1 j.

Perform Monthly Surveillance of 4KV Bus Undervoltage Relays 295016 AA1.08 (4.0/4.0)

I N'R'A 0, R, ffAY 1 7 Perform manual operation of the SRVs Valves from the Remote A Shutdown Panel as required by ON-100-00900.0N.015.103 (3)

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (E/A)Emergency/Abnormal, (E)SF NUREG-1021, Draft Rev 9 Susquehanna Facsimile 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 78.AR.004.103 0 06/17/03 215005 A2.02 3.6/3.7 Appi. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Bypass an APRM Channel BIDIF Trip input to RPS Completed By: Reviews:

Russ Halm 06/17/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head

~-< 15 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory 0Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev. 4, (OYOO)

Page I of 1 2003 NRC Exam Rev. 1 File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 78.AR.004.103 L-

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. AR-103-001, RPS Division IIC651 (Rev. 22)

B. AR-104-001, RPS Division 2 IC651 (Rev. 17)

C. OP-158-001 RPS System (Rev. 26) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. The plant is operating at 100% power.

B. You are the PCOM.

V. INITIATING CUE Respond to alarm conditions.

Vi. TASK STANDARD D APRM input to RPS bypassed and half scram signal reset.

Form STCP-QA-125A Rev. 4, (05/00)

Page I of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 78.AR.004.103 Student Name:

Step Action Standard Eva1 Comments EVALUATOR NOTE:

0 This JPM must be performed in the simulator.

0 Establish task conditions as directed on attached setup instructions.

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

EVALUATOR NOTE:

The upscale failure of D APRM will cause the following annunciators to alarm:

AR-103-A06, AR-103-B06, AR-104-AOI , AR-104-A04, and AR-104-H03 It is acceptable for the candidate to refer to any or all of these AR procedures. The necessary guidance to respond to the failure is contained in AR-103-A06. The JPM is written to follow this guidance.

BOOTH OPERATOR:

30 seconds after the candidate is ready to begin the JPM, Depress P-I.

I Candidate locates procedure and refers to Obtains procedure AR-103-001 appropriate section. and refers to Window A06.

I

• Critical Step #Critical Sequence Form STCP-QA-I25A Rev 4, (OYOO)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 4 of 5 Appl. To/JPM No.: S/RO 78.AR.004.103 Student Name:

Step Action Standard Eva1 Comments 2 Determines Probable cause. Determines D APRM is failed upscale high Verifies:

0 CRT No. 6 D APRM reading 125%.

Status light D APRM UPSC TR OR INOP D UPSCALE ALARM - LIT.

0 AR-104-A01 RPS CHANNEL B1/B2 AUTO SCRAM - LIT.

0 AR-104-HO3 ROD OUT BLOCK - LIT.

3 Ensures automatic actions occurred. Verifies:

Trip to Reactor Protection System channel B.

0 Rod block to Reactor Manual Control System.

4 Determines reactor power reduction is not Determines flow bias setpoint has not been necessary. exceeded on any of the unaffected channels.

5 Determines D APRM is affected. Determine APRM channel causing the trip EVALUATOR NOTE: Verifies:

e D APRM reading 125%.

Candidate may inform Unit Supervisor about the instrument failure before bypassing. 0 All other APRMs reading 100%.

• 6 Bypass D APRM. Places the Division 2 APRM BYPASS joystick to the D position.

• Critical Step #Critical Sequence Form STCP-QA-125A Rev. 4, (05lOO)

Page 1 of 1 2003 NRC Exam Rev. 1

i i' PERFORMANCE CHECKLIST Page 5 of 5 Appl. To/JPM No.: S/RO 78.AR.004.103 Student Name:

Step Action Standard Eva1 Comments EVALUATOR NOTE:

It does not matter which position is selected first in the next step.

• 7 Reset RPS trip system. Places the RX SCRAM RESET switch to the GRP 1/4 position then to the GRP 2/3 position and returns to the NORM position.

8 Observe alarms clear. Verifies the following alarm is clear 0 RPS CHANNEL 61/62 AUTO SCRAM, AR-104-AOI .

EVALUATOR NOTE:

This completes the JPM.

• Critical Step #Critical Sequence Form STCP-QA-IZSA Rev 4,(05/00)

Page I of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS

• - A. The plant is operating at 100% power.

B. You are the PCOM.

INITIATING CUE Respond to alarm conditions.

Page 1 of 2 Form S'CCP-QA-12SA Rev. 4, (OYOO)

Page 1 of I 2003 NRC Exam Rev. 1

TASK CONDITIONS A. The plant is operating at 100% power.

B. You are the PCOM.

INITIATING CUE Respond to alarm conditions.

Page 2 of 2 Form STCP-QA-125A Rev. 4, (OS/OO)

Page I of 1 2003 NRC Exam Rev. 1

1. PCAF NO. 2003--S220 2. P A G E l O F 4 3. PROC. NO. AR-103-001 REV. 22 FORM NDAP-QA-0002-8, Rev. 8, Page 1 of 2 (Electronic Form)

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 04.SO.002.251 0 06/15/03 262001 K4.04 2.8/3.1 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. KJA Task

Title:

MONTHLY 4 W BUS DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST Completed By: Reviews:

Russ Halm 06/15/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head

\~

30 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-lZ5A Rev. 4, (05/00)

Page 1 of 1 File No. A14-50 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 04.S0.002.251 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

6 . All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. SO-204-001 MONTHLY 4KV BUS 2A201,2A202,2A203, AND 2A204 DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST, REV. 8 III. REACTIVITY MANIPULATlONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. Unit 2 is in MODE 1.

6 . No other testing is being performed on Unit 2.

V. INITIATING CUE Perform SO-204-001, MONTHLY 4KV BUS 2A201,2A202,2A203, AND 2A204 DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST.

VI. TASK STANDARD Blocks trip circuit prior to testing and enables trip circuit when testing is complete. Determines acceptance criteria are met for bus 2A201 and acceptance criteria are not met for function 2 on bus 2A202.

2003 NRC Exam Rev. I

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PERFORMAN CE CHECKLIST Page 3 of 12 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:

Step Action Standard Eva1 Comments EVALUATOR This JPM must be performed in plant.

Ensure the following material is available to support performance of this JPM:

A COPY of SO-204-001.

Attach a surveillance authorization coversheet with the appropriate data completed.

0 Stopwatch for each evaluator.

The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

EVALUATOR To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

EVALUATOR CUE Give the candidate a copy of the surveillance to be performed.

Reviews the coversheet. Verifi a ithorization to commence by Shift Supervision signature with date a time completed.

EVALUATOR Provide the candidate time to review the test procedure.

Obtains stopwatch. Stopwatch obtained.

Review precautions. Precautions reviewed.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2,(9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 4 of 12 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:

Step Action Standard Eva1 Comments 4 Record plant MODE. Enters Ifor MODE and initials the confirm line.

EVALUATOR NOTE Candidate may elect to confirm buses are de-energized by contacting the control room.

5 Verify Unit 2 ESS buses energized. Observes white light LIT on OC653 for buses:

2A201 2A203 2A202 2A204 6 Document step completion. Initials confirm space for each bus.

7 Identify testing restrictions. Determines no other testing is permitted on the bus being tested by this surveillance.

8 Document step completion. Initials confirm space.

EVALUATOR Candidate will proceed to Unit 2 Reactor Building inside the RCA to continue.

NOTE 1 Panel OC653 alarm, 4KV BUS LO VOLT/PROT CKT TROUBLE for affected bus will annunciate and clear periodically during test

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2,(9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 5 of 12 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:

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Step Action Standard Eva1 Comments NOTE 2 Those steps of procedure designated by an asterisk (*)

immediately to left of step number require entry(ies) to be recorded on Data Form.

CAUTION BUS REMAINS ENERGIZED. EXERCISE CAUTION WORKING AROUND ENERGIZED BUSES. CARE MUST BE TAKEN NOT TO PUSH, PULL OR DROP ANY OBJECTS NEAR ENERGIZED EQUIPMENT.

9 Inform Shift Supervision to enter TS 3.3.8.1. Using plant page/radio contacts control room/Unit Supervisor to enter TS 3.3.8.1 for bus 2A201.

10 Document step completion. Initials confirm space.

CAUTION DEGRADED GRID PROTECTION FOR ESS BUS 2A201 DISABLED DURING PERFORMANCE OF THIS SECTION.

• I1 Block protection circuit. Place Degraded Voltage Trip Enable Test Switch HSE-2A20102B to TRIP BLOCKED position.

12 Document step completion. Initials confirm space.

• Critical Step #CriticaI Sequence STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 6 of 12 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:

Step Action Standard Eva1 Comments 13 Confirm 4KV BUS 2A(2A201) LO VOLTlPROT CKT Using plant page/radio contacts TROUBLE ALARM received at panel OC653. Unit 2 control room to confirm the alarm was received.

EVALUATOR CUE Inform candidate the alarm was received.

14 Document step completion. Initials confirm space.

15 Perform light test. Place Degraded Voltage Ckt Test Switch HSE-2A20102A to LIGHT TEST and CONFIRM following EVALUATOR CUE Degraded Voltage Ckt Test Light Inform candidate the white lights are LIT. ILLUMINATE:

0 Relay Ckt 2781/2782 0 Relay Ckt 27B3/27B4 Verify white lights LIT.

16 Document step completion. Initials confirm spaces.

17 Return test switch to normal. Place Test Switch HSE-2A20102A to Normal and CONFIRM following J Test lights EXTINGUISH:

EVALUATOR CUE 0 Relay Ckt 27B1/27B2 Inform candidate the white lights are NOT LIT. Relay Ckt 278312784 Verify white lights are NOT LIT.

18 Document step completion. Initials confirm spaces.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 7 of 12 Appl. TolJPM No.: S/RO 04.S0.002.251 Student Name:

Step Action Eva1 Comments "1 9 Test circuit and time relay drop out. Place Test Switch HSE-2A20102A to CIRCUIT TEST and simultaneously starts the stop EVALUATOR CUE watch and CONFIRM following Inform candidate the white lights are LIT with the following Test lights ILLUMINATE:

times: Relay Ckt 27B3/27B4 (-3 Relay Ckt 27B3/27B4 (-3 seconds) seconds)

Relay Ckt 27B1/27B2 (-5 minutes) 0 Relay Ckt 27B1/27B2 (-5 minutes)

Verify white lights are LIT and note times on stopwatch.

EVALUATOR Record acceptance criteria as Bus 2A201 acceptance criteria for function 2 is 1.a (65%) acceptable on the data form by and function 3 is 2.a (93%) on data form. circling yes and initial the confirm space for function 2 and 3.

• 20 Return test switch to normal. Place Test Switch HSE-2A20102A to Normal and CONFIRM following Test lights EXTINGUISH:

EVALUATOR CUE Relay Ckt 27B1127B2 Inform candidate the white lights are NOT LIT. Relay Ckt 27B312784 Verify white lights are NOT LIT.

21 Document step completion. Initials confirm space.

22 Reset relay targets 27B1 through 27B4. Depress the reset button and verify relay target color changes from orange to clear.

23 Document step completion. Initials confirm space for each relay.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 8 of 12 Appl. TolJPM No.: SlRO 04.S0.002.251 Student Name:

Step Action Standard Eva1 Comments

• 24 Enable protection circuit. Place Degraded Voltage Trip Enable Test Switch HSE-2A20102B to TRIP ENABLED position.

25 Document step completion. Initials confirm space.

26 Confirm 4KV BUS 2A(2A201) LO VOLT/PROT CKT Using plant pagelradio contacts TROUBLE ALARM cleared at panel OC653. control room to confirm the alarm cleared.

EVALUATOR CUE Inform candidate the alarm was clear.

27 Document step completion. Initials confirm space.

28 Inform Shift Supervision to clear TS 3.3.8.1. Using plant pagelradio contacts control roomlUnit Supervisor to clear TS 3.3.8.1 for bus 2A201.

29 Document step completion. Initials confirm space.

EVALUATOR Candidate will proceed to bus 2A202.

30 Inform Shift Supervision to enter TS 3.3.8.1. Using plant pagelradio contacts control roomlUnit Supervisor to enter TS 3.3.8.1 for bus 2A202.

31 Document step completion. Initials confirm space.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 9 of 12 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:

Step .--.-..

.Actinn Standard Eva1 Comments CAUTION DEGRADED GRID PROTECTION FOR ESS BUS 2A202 DISABLED DURING PERFORMANCE OF THIS SECTION.

• 32 Block protection circuit. Place Degraded Voltage Trip Enable Test Switch HSE-2A20202B to TRIP BLOCKED position.

33 Document step completion. Initials confirm space.

34 Confirm 4KV BUS 2B(2A202) LO VOLTIPROT CKT Using plant page/radio contacts TROUBLE ALARM received at panel OC653. control room to confirm the alarm was received.

EVALUATOR CUE Inform candidate the alarm was received.

35 Document step completion. Initials confirm space.

36 Perform light test. Place Degraded Voltage Ckt Test Switch HSE-2A20202A to LIGHT TEST and CONFIRM following EVALUATOR CUE Degraded Voltage Ckt Test Light Inform candidate the white lights are LIT. ILLUMINATE:

Relay Ckt 27B1127B2 Relay Ckt 27B3/27B4 Verify white lights LIT.

37 Document step completion. Initials confirm spaces.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 10 of 12 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:

Step Standard Eva1 Comments 38 Return test switch to normal. Place Test Switch HSE-2A20202A to Normal and CONFIRM following Test lights EXTINGUISH:

EVALUATOR CUE Relay Ckt 27B1/27B2 Inform candidate the white lights are NOT LIT. Relay Ckt 27B3/27B4 Verify white lights are NOT LIT.

39 Document step completion. Initials confirm spaces.

FAULT STATEMENT: RELAY CKT 27B3/2764 WILL EXCEED THE TECH SPEC ALLOWABLE VALUE.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 11 of 12 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:

Step Action Standard Eva1 Comments

• 40 Test circuit and time relay drop out. Place Test Switch HSE-2A20202A to CIRCUIT TEST and simultaneously starts the stop EVALUATOR CUE watch and CONFIRM following Inform candidate the white lights are LIT with the following Test lights ILLUMINATE:

times: 0 Relay Ckt 27B3127B4 (-3 0 Relay Ckt 27B3/27B4 (-6 seconds) seconds)

Relay Ckt 27B1/27B2 (-5 minutes) Relay Ckt 27B1/27B2 (-5 minutes)

Verify white lights are LIT and note times on stopwatch.

EVALUATOR Record acceptance criteria is not Candidate may inform control room about the acceptance acceptable on the data form by criteria failure. circling no and initial the confirm Bus 2A202 acceptance criteria for function 2 is 1.b (65%) space for function 2.

and function 3 is 2.b (93%) on data form.

Record acceptance criteria is acceptable on the data form by circling yes and initial the confirm space for function 3.

EVALUATOR CUE If necessary roleplay shift supervision and direct candidate to proceed with surveillance to restore test circuitry for the 2A202 bus.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 12 of 12 Appl. TolJPM No.: S/RO 04.S0.002.251 Student Name:

Step Action Standard Eva1 Comments

• 4 1 Return test switch to normal. Place Test Switch HSE-2A20202A to Normal and CONFIRM following Test lights EXTINGUISH:

EVALUATOR CUE Relay Ckt 27B1127B2 Inform candidate the white lights are NOT LIT. 0 Relay Ckt 27B3/27B4 Verify white lights are NOT LIT.

42 Document step completion. Initials confirm space.

43 Reset relay targets 27Bl-2A20202 through 27B4- Depress the reset button and 2A20202. verify relay target color changes from orange to clear.

44 Document step completion. Initials confirm space for each relay.

• 45 Enable protection circuit. Place Degraded Voltage Trip Enable Test Switch HSE-2A20202B to TRIP ENABLED position.

46 Document step completion. Initials confirm space.

47 Confirm 4KV BUS ZB(2A202) LO VOLT/PROT CKT Using plant page/radio contacts TROUBLE ALARM cleared at panel 06653. control room to confirm the alarm cleared.

EVALUATOR CUE Inform candidate the alarm was clear.

48 Document step completion. Initials confirm space.

• Critical Step #Critical Sequence STCP-CIA-1255 Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 13 of 12 Appl. To/JPM No.: S/RO 04.S0.002.251 Student Name:

Step Action Standard 49 Inform Shift Supervision Bus 2A202 did not meet Using plant pagehadio contacts acceptance criteria. Unit 2 control roorn/Unit Supervisor and informs them bus 2A202 did not meet acceptance criteria for relays 27B3/27B4.

EVALUATOR This completes the JPM.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS A. Unit 2 is in MODE 1.

B. No other testing is being performed on Unit 2.

INITIATING CUE Perform SO-204-001, MONTHLY 4KV BUS 2A20II2A202, 2A203, AND 2A204 DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST.

.~

Page 1 of 2 2003 NRC Exam Rev. I

TASK CONDITIONS LJ A. Unit 2 is in MODE 1.

B. No other testing is being performed on Unit 2.

INITIATING CUE Perform SO-204-001, MONTHLY 4KV BUS ZA201,2A202,2A203, AND 2A204 DEGRADED VOLTAGE CHANNEL FUNCTIONAL TEST.

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Page 2 of 2 2003 NRC Exam Rev. I

L-PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 00.ON.015.153 1 06/13/03 295016 AA1.08 4.0/4.0 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Perform Manual Operation of the ADS Valves from the Remote Shutdown Panels or Rooms as Required by ON-I 00-009 (Alternate Path)

Completed By: Reviews:

Russ Halm 06/13/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 25 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

STCP-QA-125A Rev. 2. (9/93)

Page 1 of 1 File No. A14-5B 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION

.-.- JOB PERFORMANCE MEASURE S/RO 00.ON.015.153 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. ON-100-009 CONTROL ROOM EVACUATION (Rev. 8)

I II. REACTIVITY MANIPULATIONS L-None IV. TASK CONDITIONS A. An incident has occurred at Unit 1, which has required the Control'Room to be Evacuated.

B. Control has been transferred to the Unit 1 RSDP in accordance with ON-100-009.

C. HPCl is operating.

D. Reactor pressure is 875 psig and stable.

E. MSlVs are closed.

F. The Unit Supervisor has directed that SRVs be used for a plant cooldown.

V. INITIATING CUE Lower RPV pressure, from the Unit 1 RSDP, as necessary to initiate a reactor cooldown NOT to exceed 100°F per hour from the present conditions, in accordance with ON-I 00-009step 4.6.

VI. TASK STANDARD Reactor C/D lowest pressure calculated 1 3 2 5 psig and at least 1 SRV opened.

2003 NRC Exam Rev. I

\

PERFORMANCE CHECKLIST Page 3 of 7 Appl. To/JPM No.: S/RO 00.ON.015.153 Student Name:

~~ ~

Step Action Standard Eva1 Comments EVALUATOR NOTE:

. The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

Obtains a controlled copy of ON-100-009, including 3btains a controlled copy ON-I 00-009, Attachments A and B. ncluding Attachments A and B.

NOTE:

Relief mode of SRV's A, B, and C will not auto initiate when applicable Control Transfer Switches are in EMERG position, however, safety function is always operable. Also when SRV Transfer Switches are in EMERG spurious auto actuation is prevented due to a Control Room fire.

Ensure following valves OPEN: Checks:

SV-12651 INSTR GAS TO CONTN ISO. SV-12651 indicating lights Red light LIT.

SV-12605 INSTR GAS CMP OB SUCT ISO. Amber light NOT LIT.

EVALUATOR CUE: AND Inform candidate, Red OPEN lights LIT and amber SV-12605 indicating lights CLOSED lights NOT LIT for SV-12651 and SV-I2605 Red light LIT.

indication. Amber light NOT LIT.

• Critical Step #Critical Sequence STCP-QA-1250 Rev. 2.(9193)As Given Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 4 of 7 Appl. To/JPM No.: S/RO 00.ON.015.153 Student Name:

Step Action Standard Eva1 Comments CAUTION Level 1 (-129") or high drywell pressure (1.72 psig)

LOCA Isolation Signal is defeated for CIG valves when controlled from the remote shutdown panel.

NOTE:

Placing HSS-151148 Transfer Switch U in EMERG causes lnstr Gas CMP OB suction to cycle possibly tripping CIG compressors on low suction pressure.

3 -IF CIG Compressors tripped, Reset as follows at Simulates contacting Reactor building NPO to 1C239 (25-719'): determine the status of the CIG compressors.

Depress Logic Reset push button.

Ensure CIG Compressor STARTS.

EVALUATOR CUE:

Role Play as Reactor Building NPO and Inform candidate that the CIG Compressors are running.

CAUTION (1)

If RPV pressure drops below 650 psig, condensate pumps will inject when RPV level <+35 inches.

CAUTION (2)

Wide range level indication becomes less accurate as RPV pressure decreases.

• Critical Step #Critical Sequence STCP-PA-1256 Rev. 2. (9193)As Given Page 1 of 1 2003 NRC Exam Rev. 1

i i PERFORMANCE CHECKLIST Page 5 of 7 Appl. To/JPM No.: S/RO 00.ON.015.153 Student Name:

Step Action Standard Eva1 Comments EVALUATOR NOTE:

Since the SRVs will not open until the candidate is at the relay room, Calculation of allowable cooldown value may be done anytime during the remainder of the JPM.

This is acceptable.

Operate SRV's as follows:

• 4 Calculates allowable cooldown value for reactor Refers to ON-100-009, Attachment A to pressure. determine current reactor temperature and desired reactor pressure and temperature to achieve a 1OO°F/hr cooldown AND Determines RPV pressure at 875 psig, reactor temperature is -530°F. Cooldown rate of 1OO"F/hr lowers RPV pressure -325 psig.

Should be over 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, so a target pressure 2325 psig is selected.

FAULT STATEMENT:

SRV'S A, B, & C WILL NOT OPEN FROM THE RSDP.

5 Open SRV's A, B, and C as needed. Places switches for SRVs A, B, or C to OPEN.

EVALUATOR CUE: AND Checks for change in RPV pressure If asked, indicate RPV pressure is still stable at 875 psig.

• Critical Step #Critical Sequence STCP-QA-I25B Rev. 2, (9193)As Given Page 1 of1 2003 NRC Exam Rev. 1

( i PERFORMANCE CHECKLIST Page 6 of 7 Appl. To/JPM No.: SlRO 00.ON.015.153 Student Name:

Step Standard Eva1 Comments EVALUATOR CUE: Candidate determines that the valves have not opened and reports this to the SRO.

Acknowledge as SRO and inform the candidate to perform the necessary procedural actions to complete the task. Inform the operator that permission is granted to leave the RSDP - another operator will assume the RSDP station.

6 Chooses alternate method of SRV operation. IF pneumatic supply to SRV's A, B, and C not available, Operate SRV's GIJ, K, L, MI or N (ADS valves) individually from upper (lower) relay room Panel 1C628 (1C631) using keylock switches.

EVALUATOR CUE:

Roleplay SRO as necessary to provide instructions on which SRV is to be opened.

EVALUATOR NOTE:

Operation of the ADS valves from the Relay Room consists of switch manipulation and monitoring cooldown rate while maintaining communication with the RSDP Room. There are six keylock switches in each Relay Room; the operator may select either the Upper or the Lower Relay Room to perform this JPM.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2, (9193)As Given Page 1 of 1 2003 NRC Exam Rev. 1

f

( i PERFORMANCE CHECKLIST Page 7 of 7 Appl. To/JPM No.: S/RO OO.ON.015.153 Student Name:

=

Step Action Standard Eva1 Comments EVALUATOR NOTE:

Keys to operate SRVs are located in sealed Pink sound powered phone storage box, labeled JPI 207, JP1402, JP2201, inside the Remote Shutdown Panel Room.

Use of these keys and the key to the storage box will be SIMULATED

• 6 Simulate obtaining keys for SRVs from Pink sound Demonstrates the ability to find keys in the pink powered phone box, labeled JP1207, JP1402, box labeled JP1207 or JP1402.

JP2201 I.

7 Go to the selected Relay Room, locates Panel IC631 Proceeds to the selected Relay Room, locates or Panel 1C628. Panel IC631 or Panel 1C628.

8 Simulates establishing communication with the RSDP Establishes communication with the RSDP Room. Room (simulate) using sound-powered phone page.

• 9 Simulates inserting key and rotating switch to the Simulates placing any ADS keylock switch in OPEN position. the OPEN position.

EVALUATOR CUE: AND Inform candidate red light LIT and amber light NOT LIT Verifies Red light LIT and amber light NOT LIT.

for each valve place to open.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2,(9193)As Given Page 1 of 1 2003 NRC Exam Rev. 1

t (

PERFORMANCE CHECKLIST Page 8 of 7 Appl. To/JPM No.: S/RO 00.ON.015.153 Student Name:

~

Step Action Standard Eva1 Comments EVALUATOR CUE: Simulates using sound-powered phone g page.

To inform SRO at the RSDP the valve indicates Acknowledge SRV is OPEN. OPEN This completes the JPM.

• Critical Step #Critical Sequence STCP-QA- 1256 Rev. 2, (9193)As Given Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS L'

A. An incident has occurred at Unit 1, which has required the Control Room to be Evacuated.

B. Control has been transferred to the Unit 1 RSDP in accordance with ON-100-009.

C. HPCl is operating.

D. Reactor pressure is 875 psig and stable.

E. MSIVs are closed.

F. The Unit Supervisor has directed that SRVs be used for a plant cooldown.

INITIATING CUE Lower RPV pressure, from the Unit 1 RSDP, as necessary to initiate a reactor cooldown NOT to exceed 100°F per hour from the present conditions, in accordance with ON-100-009 step 4.6.

Page 1 of 2 2003 NRC Exam Rev. I

TASK CONDITIONS A. An incident has occurred at Unit 1, which has required the Control Room to be Evacuated.

B. Control has been transferred to the Unit 1 RSDP in accordance with ON-100-009.

C. HPCl is operating.

D. Reactor pressure is 875 psig and stable.

E. MSlVs are closed.

F. The Unit Supervisor has directed that SRVs be used for a plant cooldown.

INITIATING CUE Lower RPV pressure, from the Unit 1 RSDP,as necessary to initiate a reactor cooldown NOT to exceed 100°F per hour from the present conditions, in accordance with ON-100-009 step 4.6.

Page 2 of 2 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 50.E0.008.101 1 06/15/03 217000 A2.01 3.8/3.7 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Bypass of All RClC Isolation Signals in Accordance With ES-150-001 Completed By: Reviews:

Russ Halm 06/15/03 Writer Date InstructorNVriter Date Ap provaI:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head L-.

40 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-12M Rev. 4, (OSlOO)

Page 1 of 1 File No. A14-5B 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 50.E0.008.101 l - /

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. ES-150-001 RClC Turbine Isolation and Trip Bypass, Rev. 14 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity@):

None

-.-- IV. TASK CONDITIONS A. An accident condition exists and Shift Supervision has determined that it is necessary to rapidly depressurize the RPV as required by EO-I 00-103, Primary Containment Control.

B. EO-100-112, Rapid Depressurization is being executed, and only two SRVs can be opened.

C. A RClC initiation signal is sealed in and RClC started, but tripped and isolated, due to a loss of RB HVAC with a subsequent pipe routing area high temperature.

D. A steam leak does not exist.

E. RClC is needed for support of reactor depressurization.

F. ES-150-001 Section 4.6 is complete, bypassing and resetting the RClC initiation signal.

V. INITIATING CUE Bypass all of the RClC isolation signals in accordance with ES-150-001, Section 4.2.

VI. TASK STANDARD All RClC isolations signals bypassed.

-\---

2003 NRC Exam Rev. I

(,

PERFORMANCE CHECKLIST Page 3 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:

Step Action Standard Eva1 Comments EVALUATOR 0 This JPM must be performed in the plant.

Obtain permission from Shift Manager to perform this JPM and get access to ES tool box.

0 Ensure the following material is available to support performance of this JPM:

0 A copy of the latest revision of ES-150-001.

0 In section 4.0, initial 4.6 and 4.2 under EO-I 12.

0 Enter NA for all other initial blocks in section 4.0.

Authorize the ES by signoff as Shift Manager with date and time.

0 Signoff confirmed and date for steps 4.6.1 .a and 4.6.1 .b.

0 Insert NA for steps 4.6.2.a and 4.6.2.b.

0 Place checkmark at the end of steps 4.6.3 through 4.6.7 indicating their completion.

EVALUAT0 R To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Review Sections 1.O through 3.0. Reviews all sections.

Notes that the approval step for 4.6 and 4.2, under Rapid Depressurization in section 4.0 has been initialed.

Ensure that Shift Supervision has approved performance Notes that Shift Supervision has of Sections 4.6 and 4.2. signed and dated the appropriate signature line.

• Critical Step #Critical Sequence STCP-OA-1256 Rev. 2. (9193)

Pagelof1 .

2003 NRC Exam Rev. 1

(r PERFORMANCE CHECKLIST Page 4 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:

Step Action Standard Eva1 3 Obtain required support materials. Obtains required support materials from the ES box in the Shift EVALUATOR Managers office.

Have the candidate show you the support materials, but do not remove them from the Shift Managers office.

4 Selects correct section. Selects section 4.2.

5 Place following valve control switches to CLOSE: Insert key and rotate counter STM SUPPLY IB IS0 HV-149-FO07 clockwise to CLOSE for HV-149-STM SUPPLY OB IS0 HV-149-FO08 007 and F008.

WARM UP LINE IS0 HV-149-F088 Place control switch to CLOSE for EVALUATOR CUE HV-149-FO88.

After each switch is placed to CLOSE inform the candidate the amber light is LIT and the red light is NOT Verify amber light LIT and red light LIT. NOT LIT.

CAUTION The following steps bypass all isolation signals including manual isolation, however, HV-15012 and HV-149-F008 can still be closed manually using the handswitches.

NOTE: Booting of RClC E51-K15 and K33 contacts below will allow bypass of all isolations but will not inhibit other functions (Le., Alarm and BIS lights).

However, these may be affected momentarily when the relay fingers are spread to install the boots.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 5 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:

~

Step Action Standard Eva1 Comments 6 Bypass all RClC Div 1 isolations. Locate IC621, RClC RELAY PANEL DIVISION 1.

EVALUATOR 1C621 located Upper Relay Room.

Banana Jacks in this JPM have a GREEN stripe.

7 Locate relay, loosen relay cover screws, and remove REMOVE front cover from Relay cover. E51A-KI5, RClC AUTO/MAN ISOLATION SIGNAL F008 CONTROL LOGIC.

• 8 Boot contacts 3/4. Referring to ATT A, INSTALL boot over 314 contact finger of Relay E51A-KI5.

9 Document step completion. SignsAnitials confirmed space and enters date.

• IO Boot contacts 9/10. Referring to ATT A, INSTALL boot over 9/10 contact finger of Relay E51A-KI5.

11 Document step completion. Signs/initials confirmed space and enters date.

12 Locate Terminal Strips - AAA7 and BBB9. Locate Terminal Strips - AAA7 and BBB9.

NOTE: Terminal Strip AAA7 is located left side, back row 4 feet high, and terminal strip BBB9 is located right side, front row, 3 feet high in rear of panel.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i' 4,

PERFORMANCE CHECKLIST Page 6 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:

Step Action Standard Eva1 Comments

• I 3 Install jumper. INSTALL a jumper between terminal points AAA7-4 and BBB9-7.

14 Document step completion. Signs/initials confirmed space and enters date.

15 Bypass all RClC Div 2 isolations. Locate 1C618, RHRlRClC RELAY PANEL DIV 2.

EVALUATOR IC618 is located in the Lower Relay Room.

16 Locate relay, loosen relay cover screws, and remove REMOVE front cover of Relay cover. E51A-K33, RClC IS0 SIGNAL TURB EXH DIAPHRAGM HIGH PRESSURE.

• I7 Boot contacts 314. Referring to ATT B, INSTALL boot over 3/4 contact finger of Relay E51A-K33.

18 Document step completion. Signs/initials confirmed space and enters date.

• I9 Boot contacts 7/8. Referring to ATT B, INSTALL boot over 7/8 contact finger of Relay E51A-K33.

20 Document step completion. Signslinitials confirmed space and enters date.

21 Locate Terminal Strip - EEE8. Locate Terminal Strip - EEE8.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANC'E CHECKLIST Page 7 of 9 Appl. To/JPM No.:S/RO 50.E0.008.101 Student Name:

Step Action Standard Eva1 Comments NOTE: Terminal Strip EEE8 is located right side, 2 feet high in rear of Panel 1C618, third door from right end of panel.

• 22 Install jumper. INSTALL jumper between Terminal Points EEE8-14 and EEE8-20.

23 Document step completion. Signs/initials confirmed space and enters date.

24 Locate Terminal Strips BBBG and EEE7 Locate Terminal Strip -BBB6 and Terminal Strip - EEE7.

NOTE: Terminal Strip BBBG is located right side, 6 feet high. Terminal Strip EEE7 is located 3 feet high in rear of Panel lC618, third door from right end of panel.

• 25 Install jumper INSTALL jumper between Terminal Points BBB6-6 and EEE7-14.

26 Document step completion. Signs/initials confirmed space and enters date.

Pressurize RClC steam line.

• 1. 27 OPEN STM SUPPLY IB IS0 HV-149-FO07. PLACE STM SUPPLY IB IS0 HV-149-FO07 keyswitch to OPEN.

EVALUATOR CUE Inform the candidate the red light is LIT and the amber Verify red light LIT and amber light light is NOT LIT. NOT LIT.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i, (

PERFORMANCECHECKLIST Page 8 of 9 Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:

Step Action Standard Eva1 Comments

• 1. 28 THROTTLE OPEN STM SUPPLY OB IS0 HV-149-F008. PLACE STM SUPPLY OB IS0 HV-149-F008 keyswitch to OPEN for four seconds.

RETURN STM SUPPLY OB IS0 HV-I49-FO08 keyswitch to STOP position.

EVALUATOR CUE Inform the candidate the red light and the amber light are Verify red light and amber light LIT. LIT.

29 OBSERVE steam line pressure increasing. Observe STM SUP PRESS TO RClC TURBINE PI-E51-1R602.

EVALUATOR CUE Inform the candidate that RClC Steam Line pressure is rising.

30 THROTTLE OPEN RClC STM SUPPLY OB IS0 HV-149- PLACE STM SUPPLY OB I S 0 F008 to pressurize RClC steam line -100 psi/min. HV-149-F008 keyswitch to OPEN.

EVALUATOR CUE Inform the candidate that RClC Steam Line is RETURN STM SUPPLY OB IS0 pressurizing at a rate of -80 psi/min. HV-149-F008 keyswitch to STOP position while monitoring PI-E51-1R602 "Critical Step #Critical Sequence STCP-QA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(, i PERFORMANCE CHECKLIST Page 9 of 9 I'

Appl. To/JPM No.: S/RO 50.E0.008.101 Student Name:

Step Action Standard Eva1 Comments 31 When RCIC steam line pressure within 50 psig reactor Compares any reactor pressure pressure as indicated on STM SUP PRESS TO RClC indication to PI-E51-1R602.

TURBINE PI-E51-1R602, FULLY OPEN STM SUPPLY OB IS0 HV-149-FO08.

EVALUATOR CUE Inform candidate that pressures are within 50 psig of each PLACE STM SUPPLY OB IS0 other. HV-149-F008 keyswitch to OPEN.

Inform the candidate the red light is LIT and the amber Verify red light LIT and amber light light is NOT LIT. is NOT LIT.

32 Confirms RClC Steam Lines are drained. Observes Annunciator AR-108-BO4 is CLEAR.

EVALUATOR CUE Check STEAM LINE DRN POT Inform the candidate the amber light is LIT and the red BYPS LV-149-FO54 is CLOSED.

light is NOT LIT.

Verify amber light LIT and red light NOT LIT.

EVALUATOR This completes the JPM.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS

---

A. An accident condition exists and Shift Supervision has determined that it is necessary to rapidly depressurize the RPV as required by EO-I 00-103, Primary Containment Control.

B. EO-100-1 12, Rapid Depressurization, is being executed, and only two SRVs can be opened.

C. A RCIC initiation signal is sealed in and RCIC started, but tripped and isolated, due to a loss of RB HVAC with a subsequent pipe routing area high temperature.

D. A steam leak does not exist.

E. RClC is needed for support of reactor depressurization.

F. ES-150-001 Section 4.6 is complete, bypassing and resetting the RClC initiation signal.

INITIATING CUE Bypass all of the RClC isolation signals in accordance with ES-150-001, Section 4.2.

Page 1 of 2 2003 NRC Exam Rev. 1

TASK CONDITIONS c-A. An accident condition exists and Shift Supervision has determined that it is necessary to rapidly depressurize the RPV as required by EO-100-103, Primary Containment Control.

B. EO-100-112, Rapid Depressurization, is being executed, and only two SRVs can be opened.

C. A RClC initiation signal is sealed in and RClC started, but tripped and isolated, due to a loss of RB HVAC with a subsequent pipe routing area high temperature.

D. A steam leak does not exist.

E. RClC is needed for support of reactor depressurization.

F. ES-150-001 Section 4.6 is complete, bypassing and resetting the RClC initiation signal.

INITIATING CUE Bypass all of the RClC isolation signals in accordance with ES-150-001, Section 4.2.

i--

Page 2 of 2 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO New D/G 0 06/18/03 264000 A2.01 3.513.6 Surveillance Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Perform a Manual Start of Diesel Generator Dfrom Panel OC653 in Accordance With OP-024-001 Completed By: Reviews:

R. Halm 06/18/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head V

30 Min Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1 File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 24.0P.

i

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. OP-024-001, Diesel Generators B. OP-024-005, Diesel Generator Start Log (SPS 01-024-002)

C. OP-030-002, Control Structure HVAC D. AR-015-001, 13.8/4 KV SWITCHGEAR DISTRIBUTION AND DIESEL GENERATORS A, B, & C OC653 E. LA-0521-004, DIESEL GENERATOR D OC521 Ill. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS The Plant is in Condition 1.

A. A diesel is to be started and loaded so that cylinder pressures and temperatures can be recorded as per Vendor request.

B. The Technical Specification Surveillance is not to be performed.

C. The ESW System is in service.

D. The diesel is to be timed from the moment the start button is depressed until frequency reaches 60 Hz per second.

V. INITIATING CUE Manually start Diesel Generator D from Panel OC653 in preparation to load.

VI. TASK STANDARD Start the D D/G, prepare to Sync with grid, identify Generator Voltage decay, shutdown D/G based on Generator terminal voltage decay and alarm response direction Form STCP-QA-125A Rev. 4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCt CHECKLIST Page 3 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Student Name:

~~

Step Action Standard Comments EVALUATOR NOTE:

This JPM must be performed in the simulator.

0 Establish task conditions as directed on attached setup instructions.

The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

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

Evaluator Typically there are there people timing each DG start. There are two in the Control Room; one timing voltage to 4,160 VAC and one timing frequency to 60 Hz. The third person is the NPO at the Diesel timing speed to 600 rpm.

You should act as both the second person in the Control Room and the NPO. The longest time found is the one that is recorded in the Diesel Generator Start Log.

Provide copy of D/G Start Log OP-024-005.

Candidate is given the procedure as part of

,-+---------~

Given procedure \

turnover and is referred to appropriate OP-024-001, Diesel Generator 3.2.

section. \

Reviews prerequisites. Reviews prerequisites

• Critical Step #Critical Sequence Form STCP-QA-1ZM Rev.4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 1

i: I,

PERFORMANCE CHECKLIST Page 4 of 9 Appl. TolJPM No.: S/RO New DG Surveillance Student Name:

Step Action Standard Eva1 Comments EVALUATOR NOTE:

Normally 2 people time the DG starting, roleplay as necessary that you will provide the second timing as appropriate. The second timing is handled in a later cue at step 16 of this JPM 3 Obtains a stop watch. Obtains a Control Room timer or another stopwatch.

6iiZGz- r \

( Inform the student that all prerequisites have been met.

I OH NOTE:

All alarms on AR015, Columns I O , 13, 16, Rows A through G will be extinguished.

All alarms on AR016, Column 3, Rows A through G will be extinguished.

Diesels A, B, C and D will be in Standby with each diesel's associated instruments and indications reading as follows: DG D Watts XI-00032D - Downscale Amps -

Downscale Freq - 60 to 61 Hz Volts -

Downscale Ready to Run Light illuminated Voltage Regulator Auto light illuminated Synchroscope XS-00037 will be OFF.

Diesel Gen Bus Diff Voltmeter XI-00036 will be reading zero.

The Diesel Generator output breakers for each generator will be open.

Review the precautions. Follows precautions as applicable.

4 Station an operator at the Diesel to be started. Dispatches a NPO to the appropriate diesel generator and explains how the timing of the BOOTH CUE: Diesel Generator start will be coordinated..

Roleplay NPO

• Critical Step #Critical Sequence Form STCP-QA-125A Rev. 4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 1

i I1 PERFORMANCE CHECKLIST Page 5 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Student Name:

Step Action Standard Eva1 Comments Ensure that the ESW System is in service. The student may check the ESW pump running indicator lights on Panel OC653 or refer to the Task Conditions/lnitiatingCue Sheet.

EVALUATOR CUE:

If necessary Inform the student that the ESW System is in operation as required by OP-024-001 and OP-054-001.

Control air manifold temperature as directed. Directs NPO to place air manifold temperature control in automatic.

Remove Access Control and Lab Supply Direct NPO to remove Access Control and Lab System from service. Area Supply System from service IAW OP-030-002.

Ensure that there is no intercooler leakage. Directs the NPO to verify that intake manifold drains have no discharge.

EVALUATOR CUE:

Inform the student that there is no discharge from the intake manifold drains.

Check for proper DG operation mode. Ensures that the following control switches are in the indicated position:

0 DG ID Gov Mode Sel HS-00055D -

DROOP 0 DG D Volt Reg Mode Sel HS-00056D - AUTO

• Critical Step #Critical Sequence Form STCP-QA-125A Rev.4, (05100)

Page 1 of 1 2003 NRC Exam Rev. 1

(<:

PERFORMANCt CHECKLIST Page 6 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Student Name:

Step Action Standard Eva1 Comments 10 Prelube DG ID Turbocharger.- NPO performs Directs the NPO to perform the turbocharger turbocharger prelube. prelube per the appropriate section of OP-024-001.

EVALUATOR NOTE:

0 During prelube operation, the DG Trip and DG Panel Hi Priority Trouble Annunciators will alarm OC653.

0 The Ready to Run Light will extinguish, then illuminate.

Inform the student that the turbocharger prelube has been completed.

I1 Checks that the Ready to Run Light is Ensure that the DG is ready to run. illuminated.

EVALUATOR CUE:

Inform the student that all local checks were performed and were satisfactory.

12 Ensure that the NPO performs the appropriate Notifies NPO that the diesel is about to be DG checks as the diesel is started. started and to perform the appropriate steps of OP-024-001when the diesel begins cranking.

13 Depresses DG D start HS-00051D Start the DG. pushbutton.

14 Starts the stop watch (timer) when the Start pushbutton is depressed.

15 Stops the stop watch (timer) when DG frequency indicates 60 Hz.

• Critical Step #Critical Sequence Form STCP-QA-12M Rev. 4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCt CHECKLIST Page 7 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Student Name:

Step Action Standard Eva1 Comments 16 Log the DG start time. Notes the DG start time AND EVALUATOR CUE: Completes the Diesel Generator StaG Log.

Provide the student with start times (from the other Control Room person and the NPO) that - 3 , >

are just slightly less than the time that he has 3e noted.

You may have the student complete filling out the Log or have him/her explain what he/she would do.

Evaluator DIG will run for a few minutes and a Low Priority alarm will re received. The alarm is from the Standpipe High Level alarm at the local panel.

17 DG A PANEL OC521D LO PRIORITY DISPATCH Operator to perform LA-0521-004 TROUBLE received (AR-016-C03) Diesel Generator D OC521D Review AR-016-C03 COMPLY with TS 3.8.1 and 3.8.3.

OBSERVE Generator Voltage; If 2600V(,+2OOV):

DO NOT adjust Voltage Regulator, AND PROMPTLY SHUTDOWN Diesel Generator.

(See reference 4.5)

BOOTH OPERATOR Repeat back high level alarm due to Standpipe Wait one minute and report that local alarm is high level.

Standpipe High Level Alarm

• Critical Step #Critical Sequence Form STCP-QA-125A Rev. 4. (05100)

Page 1 of 1 2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 8 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Student Name:

Step Action Standard Eva1 Comments Faulted Step - D DIG svnc switch to ON, Generator Terminal voltaae decays.

BOOTH OPERATOR Monitor candidate actions for preparations to sync the generator to the bus. When candidate takes sync switch to the on position the batch file DG.VOLTREGFAlL is initiated, if batch file not initiated depress PB#I.

The file will cause:

DG D PANEL OC521D LO PRIORITY TROUBLE (C03) Alarm response: &&

016-C03 Take manual control of Voltage regulator switch and run it down for a second.

Ramp the Volt meter toward 2700 volts 18 Respond to: DISPATCH Operator to perform LA-0521-004 p Diesel Generator D OC521D I DG D PANEL 0 0 1D LO PRIORITY TROUBLE (C03) Alarm response: AR-016-C03

• I9 Review AR-016-C03 Review AR-016-C03 COMPLY with TS 3.8.1 and 3.8.3.

OBSERVE Generator Voltage; If 2600V(+ 200V):

DO NOT adjust Voltage Regulator, AND PROMPTLY SHUTDOWN Diesel Generator.

(See reference 4.5)

• Critical Step #Critical Sequence Form STCP-QA-1ZM Rev. 4, (OYOO)

Page 1 of 1 2003 NRC Exam Rev. 1

i' PERFORMANCE CHECKLIST Page 9 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Student Name:

Step Action Standard Eva1 Comments

• 20 Monitor Voltage DIG meter: OX100035D for Checks:

change in voltage voltage decreasing, as voltage approaches 2800V Contacts NPO on radio or plant page, and direct the local operator to trip the D/G.

BOOTH OPERATOR Repeat back D/G tripped.

Role play NPO and acknowledge the request. Verify D/G tripped alarms Verify Voltage indication zero Depress PB#2 IOR QDISESD STOP (Trips Verify D/G speed decreasing by observing Hz D/G locally) meter.

Depress PB#3 IOR ZAOXI 00035D (Ramps D/G volt meter to zero)

Role play NPO and report D/G tripped.

21 Verifies DG secured Contacts NPO to ensure DG is shutdown.

EVALUATOR NOTE:

This completes the JPM.

• Critical Step #Critical Sequence Form STCP-QA-125A Rev. 4, (OSIOO)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS

--. The Plant is in Condition 1.

A. A diesel is to be started and loaded so that cylinder pressures and temperatures can be recorded as per Vendor request.

B. The Technical Specification Surveillance is not to be performed.

C. The ESW System is in service.

D. The diesel is to be timed from the moment the start button is depressed until frequency reaches 60 Hz per second.

INITIATING CUE Manually start Diesel Generator D from Panel OC653 in preparation to load.

Page 1 of 2 Form STCP-QA-125A Rev. 4, (0300)

Page 1 of 1 2003 NRC Exam Rev. I

TASK CONDITIONS c The Plant is in Condition 1.

A. A diesel is to be started and loaded so that cylinder pressures and temperatures can be recorded as per Vendor request.

B. The Technical Specification Surveillance is not to be performed.

C. The ESW System is in service.

D. The diesel is to be timed from the moment the start button is depressed until frequency reaches 60 Hz per second.

INITIATING CUE Manually start Diesel Generator D from Panel OC653 in preparation to load.

Page 2 of 2 Form STCP-QA-125A Rev. 4, (05/00)

Page 1 of 1 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 73.E0.001.101 2 06/17/03 223001 A2.07 4.2/4.2 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Venting Suppression Chamber Within Offsite Release Limits - ES-173-001, Section 4.2 Vent Suppression Chamber Using Two Inch Vent Bypass to SGTS Completed By: Reviews:

Russ Halm 06/17/03 06/20/01 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date L- Head 20 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

STCP-QA-125A Rev. 2.(9193)

Page 1 of 1 File No. A14-SB 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE L

S/RO 73.E0.001 . I O 1

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. ES-173-001 Venting Suppression Chamber Within Offsite Release Limits (Rev. 4) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. A small break LOCA has occurred.

B. The Reactor is shut down with all control rods full in.

C. The TSC has determined it is necessary to vent the Suppression Chamber restricted to TS release limits.

D. ES-173-001, 4.2, is completed by the US up to and including step 4.2.4.b(1)

E. In Step Noble Gas samplea-G. SGTS is operating per V. INITIATING CUE Vent the Suppression Chamber (restricted to TS Release Limits) per ES-173-001, Section 4.2, beginning at step 4.2.4.c VI. TASK STANDARD Suppression Chamber vent path established.

2003 NRC Exam Rev. 1

(<

PERFORMANCE CHECKLIST Page 3 of 6 Appl. To/JPM No.: S/RO 73.E0.003.101 Student Name:

.Action

.- -. - . . Standard Eva1 Comments EVALUATOR:

Prior to performing this JPM, obtain a copy of the latest revision of ES-173-001 and mark it as if it was actually to be performed. For step 4.1 indicate (initial) that section 4.2 be performed and N/A section 4.3. Complete the signature, date, and time. Indicate steps 42.1 I 4 2 2 , 4 2 3 , and 4.2.4 are complete. Provide it to the student along with the Task Conditionsllnitiating Cue Sheet.

0 If this JPM is performed in the simulator establish task conditions as directed on attached setup instructions.

When student is ready to begin JPM, place the Simulator in RUN.

Review Sections 1.O through 3.0. Review all sections.

Follows all precautions as applicable.

Notes Shift Manager approval to perform Step Observes Shift Manager signature, date, and 4.2 (page 2 of 23). time in the appropriate location (to perform section 4.2) in Section 4.1 of the procedure.

Obtain the required equipment. Obtains two (2) keys.

NOTE:

If a containment isolation signal nc, present, then steps 4.2.4.c(1) & (2) are not required and should not be performed. Mark signoffs NA.

• Critical Step #C rit icaI Sequence STCP-QA-1PBB Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

I i: (

PERFORMANCE CHECKLIST Page 4 of 6 Appl. TolJPM No.: S/RO 73.E0.003.101 Student Name:

Step .- - .- ..

.Action Standard Eva1 Comments EVALUATOR NOTE:

Placing the key switches to the SC position in the following steps will cause AR127(8)-D-7 to alarm.

Acknowledging these alarms is not critical.

• 4 Over-ride 45 minute time delay Div 1. PLACE keylock switch for DrwVSupp Chmbr Dmp HD-17508A Is0 Signal Byps (HD17508A HV-15703) in SC position.

Inserts key and rotates clockwise to place keylock switch HD-17508A in SC position.

• 5 Over-ride 45 minute time delay Div 2. PLACE keylock switch for DrwllSupp Chmbr Dmp HD-I 75088 Is0 Signal Byps (HDI 7508B, HV-15705) in SC position.

Inserts key and rotates clockwise to place keylock switch HD-I 75088 in SC position.

EVALUATOR: Determines step 4.2.4.d is not applicable.

If asked, inform the student that venting is restricted to TS release limits; N/A step 4.2.4.d.

• 6 At Panel IC681 line up vent path. Open DrwlNVetwell Burp Dmp HD-17508A.

Places Control Switch for HD-I 7508A to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

f (

'~

PERFORMANCE CHECKLIST Page 5 of 6 Appl. To/JPM No.: S/RO 73.E0.003.101 Student Name:

Step Action Standard Eva1 Comments

• 7 At Panel IC681 line up vent path. Open Drwl/Wetwell Burp Dmp HD-175088.

Places Control Switch for HD-17508B to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT

• 8 At Panel IC601 line up vent path. Open SUPP CHMBR VENT IB IS0 HV-15703.

Places Control Switch for HV-15703 to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT

• 9 At Panel IC601 line up vent path. Open SUPP CHMBR VENT OB IS0 HV-15705.

Places Control Switch for HV-I 5705 to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT 10 Verify vent path complete. MONITOR Suppression Chamber pressure on CONTAINMENT PRESSURE PR-l571OA(B).

=

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(<

PERFORMANCE CHECKLIST Page 6 of 6 Appl. To/JPM No.: S/RO 73.E0.003.101 Student Name:

Step Action Standard Eva1 Comments 11 Monitor Radiation release rates. MONITOR SBGT SPING release rates.

Using any of the following:

PlCSY (yellow-no alarms)

SPING Terminal.

AND Determine SGTS SPING release rates remain stable and NO alarms are present.

EVALUATOR:

This completes the JPM.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS A. A small break LOCA has occurred.

B. The Reactor is shut down with all control rods full in.

C. The TSC has determined it is necessary to vent the Suppression Chamber restricted to TS release limits.

D. 4.2, is completed by the US up to and including step E. obtained a Suppression Chamber Noble Gas F.

G.

INITIATING CUE 3\

Vent the Suppression Chamber (restricted to TS Release Limits) per ES-173-001, Section 4.2, beginning at step 4.2.4.c.

Page 1 of 2 2003 NRC Exam Rev. 1

TASK CONDITIONS

._ A. A small break LOCA has occurred.

8. The Reactor is shut down with all control rods full in.

C. The TSC has determined it is necessary to vent the Suppression Chamber restricted to TS release limits.

D. ES-173-001, Section 4.2, is completed by the US up to and including step 4.2.4.b(1)

T E. In Step 4.2.1. Chemistry obtained a Suppression Chamber Noble Gas sample per Sample resul is 3E-7ucVcc.

F. SGTS SPIN is operable.

G. SGTS is operating per OP-070-001.

INITIATING CUE Vent the Suppression Chamber (restricted to TS Release Limits) per ES-173-001, Section 4.2, beginning at step 4.2.4.c.

Page 2 of 2 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 64.0P.004.153 0 06/17/03 202002 142.05 3.814.0 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. KIA Task

Title:

Reset Recirculation Pump Limiter #2 Runback IAW ON-164-002 Completed By: Reviews:

Russ Halm 06/17/03 Writer Date InstructorNVriter Date Ap provaI:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 20 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

STCP-QA-125A Rev. 2, (9/93)

Page 1 of 1 File No. A14-56 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION

- JOB PERFORMANCE MEASURE S/RO 64.0P.004.153

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES ON-I 64-002, Loss Of Reactor Recirculation Flow (Rev. 20)

III. REACTIVITY MANIPULATlONS

. . This JPM satisfies the requirements of Operational Activity(s):

36 Reset recirc pump runback IV. TASK CONDITIONS A. The plant is in Mode 1.

B. Rods 18-23, 18-39, 42-23, and 42-39, are fully inserted to support HCU maintenance on Rod 18-23.

C. A trip of CWP I D has caused a Reactor Recirculation runback to occur D. NO Operator actions have been taken.

V. INITIATING CUE Respond to a loss of reactor recirculation flow and reset recirculation pump runback in accordance with appropriate Off Normal procedure.

VI. TASK STANDARD

- Recirc pump limiter #2 reset and scoop tube locked for B recirc pump 2003 NRC Exam Rev. 1

(\

PERFORMANCE CHECKLIST Page 3 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

Step Action Standard Eva1 Comments Evaluator:

This JPM must be performed in the simulator.

Establish task conditions as directed on attached setup instructions.

The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

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

1 Obtain a controlled copy of ON-164-002, Loss Of Controlled copy obtained.

Reactor Recirculation Flow.

2 Record date and time of event. Records date and time of event.

3 Selects the correct section to perform. Selects section 3.4.

4 Plot position on Power/Flow Map. In the event of Reactor Recirculation Pump runback:

Plot position on Power/Flow h,dp, Form NDAP-QA-0338-10 (Rev-5).

Determines NOT to be in Region 1 or 2.

5 Perform appropriate action specified on Perform appropriate action Power/Flow Map. specified on Power/Flow Map.

Determines NO action required for current region.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2 (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 4 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

Step Action Standard Eva1 Comments 6 Placemode switch to SHUTDOWN if operating in -IF Power/Flow Map indicates any of these power/flow map conditions. operation in Region 1 or Core Flow is < Natural Recirculation Line operation in any region not bounded by Power/Flow map, Place MODE SWITCH to SHUTDOWN.

Determines NO action required.

7 Determine which limiter initiated runback. Limiter # I (30%) limiting by Green light ILLUMINATED above Rx RECIRC LIMITER #RUNBK I RESET HS-B31-I S15A(B) pushbutton.

Verifies:

Green lights NOT LIT.

Limiter #2 (45%) limiting by Green light ILLUMINATED above LOSS OF FW PP RUNBK RESET HS-831-1S12A(B) pushbutton.

Verifies:

Green lights LIT.

=

• Critical Step #Critical Sequence STCP-QA-lZSB Rev. 2 (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

i' PERFORMANCE CHECKLIST Page 5 of 13

{

Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

~~~

Step Action Standard Eva1 Comments

. 8 Ensure both pumps have run back to value For RRP A verifies:

associated with controlling limiter. Input meter SY-B31-lR621A is

-45%

OR Gen 1A Speed is -45 % on SI-14032A and Gen 1A Demand is

-45% on XI-14032A.

AND For RRP B verifies:

Input meter SY-B31-I R621B is

-45%

OR Gen 1B Speed is -45% on SI-140328 and Gen IB Demand is

-45% on XI-140328.

CAUTION As core flow decreases, core flux instabilities are more likely to occur.

9 Monitor neutron instrumentation for indication of Select a Control Rod and monitors core instability. for LPRM/APRM oscillations and determines they are not unstable.

IF required, Perform ON-178-002, Core Flux ON-178-002 is NOT required.

Oscillations.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i" PERFORMANCE CHECKLIST Page 6 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

~ ~~~

Step Action Standard Eva1 Comments Power reduction will further reduce amount of feedwater heating which will cause reactor power to increase.

IO Continue Monitoring position on Power/Flow map. Plot position on Power/Flow map for changes in reactor power or core flow.

11 Monitor changes in radiation levels. On 1C600, Monitor the following:

Main Steam Line Radiation Evaluator: Monitor, RR-D12-I R603.

If questioned about Rad Monitor readings, inform candidate that the radiation level were at their Offgas Pretreatment Log Radiation 100% reactor power values and have now lowered Monitor, RR-Dl2-I R601.

and stabilized at the values indicated.

Determines values are NORMAL for this power level.

12 IF Main Steam Line Radiation Monitor or Offgas Determines Chemistry notification Pretreatment Log Radiation Monitor increases, is NOT required.

Direct Chemistry to sample per CH-ON-003.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 7 of 13 Appl. To/JPM No.: SIR0 64.0P.004.153 Student Name:

Step Action Standard Eva1 Comments 13 Monitors parameters for new power level. Observe following plant parameters WITHIN LIMITS corresponding to new power level:

a. Power to flow limits

b. Condenser vacuum

c. Feedwater flow/steam flow

d. RPV water level Determines WITHIN LIMITS for the new power level.

14 Determine signal that initiated runback. Determines:

Limiter #2 (45%) runback initiated Evaluator: by Circulating Water Pump 1D CWP I D trip was given in initial conditions. protective trip.

15 Ensure recirc speed controllers are in manual. Ensure REACTOR RECIRC PUMP A(B) SPEEDS SY-B31-1R621A(B)

IN MANUAL.

Verifies amber M (manual) light LIT on the following:

Reactor Recirc Pump A SY-B31-1R621A Reactor Recirc Pump B SY-B31-1R621B

• Critical Step #C rit icaI Sequence STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 8 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

Step Action Standard Eva1 Comments CAUTION When establishing control with the recirc pump speed controllers, minimize lowering core flow to avoid inadvertent entry into Regions I or II of the powerlflow map.

Evaluator If minor speed oscillations occur for RRP A, acknowledge candidate concerns and direct candidate to continue with FW PP Runback Resets. Speed oscillations will be addressed subsequent to the reset.

SIMULATOR OPERATOR:

If necessary provide candidate with INITIAL recirc pump RPM select MPS (Monitored Parameter Summary) to view speed values.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

(

PERFORMANCECHECKLIST Page 9 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

Step Action Standard Eva1 Comments

• 16A Establish speed control for RRP A. For Limiter #2 runback Perform following for one or both pumps as SIMULATOR OPERATOR: required:

If necessary provide candidate with recirc pump To prevent pump speed from RPM select MPS (Monitored Parameter Summary) changing when Limiter #2 reset, to view speed values. Ensure GEN 1A DEMAND adjusted such that GEN I A SPEED decreases when controller Candidate may observe loop flow to confirm DEMAND is decreased.

control.

For RRP A:

Depresses the DEC pushbutton on Reactor Recirc Pump A SY-B31-1R621A controller until Gen 1A Demand XI-14032A and Gen I A Speed SI-14032A start to decrease.

• I 7A Reset limiter #2 runback for RRP A. Depress LOSS OF FW PP RUNBK RESET HS-B31-1S12A pushbutton.

18A Monitor GEN 1A speed. Monitor GEN 1A SPEED SI-14032A.

Determines speed is stable.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 10 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

Step Action Standard Eva1 Comments 19A If RRP A speed increases rapidly, lock scoop tube. speed increases rapidly, Trip scoop tube on affected generator by depressing SCOOP TUBE A LOCK OR RESET HS-631-1S30A TRIP pushbutton.

Determines speed is not increasing rapidly and locking scoop tube is NOT required.

20A Verify RRP A limiter #2 is reset by light indication. Observe Green light above LOSS OF FW PP RUNBK RESET HS-831-lSl2A pushbutton EXTINGUISHED.

Verifies:

Green light NOT LIT.

Evaluator If minor speed oscillations occur for RRP B, acknowledge candidate concerns and direct candidate to continue with FW PP Runback Resets. Speed oscillations will be addressed subsequent to the reset.

=

• Critical Step #Critical Sequence STCP-(24-1258 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 11 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

Step Action Standard Eva1 Comments

• 16B Establish speed control for RRP B. To prevent pump speed from changing when Limiter #2 reset, Ensure GEN 1B DEMAND SIMULATOR OPERATOR: adjusted such that GEN 1B If necessary provide candidate with recirc pump SPEED decreases when controller RPM select MPS (Monitored Parameter Summary) DEMAND is decreased.

to view speed values.

For RRP B:

Depresses the DEC pushbutton on Candidate may observe loop flow to confirm Reactor Recirc Pump B control. SY-B31-I R621B controller until Gen 1B Demand XI-14032B and Gen 1B Speed SI-14032B start to decrease.

FAULT STATEMENT: RRP B WILL EXPERIENCE AN UNCONTROLLED SPEED INCREASE AFTER THE CANDIDATE HAS RESET THE RUNBACK.

• I 7B Reset limiter #2 runback for RRP B. Depress LOSS OF FW PP RUNBK RESET HS-B31-I S12B pushbutton.

18B Monitor GEN 1B speed. Monitor GEN 1B SPEED SI-140328.

Determines RRP B speed is increasing.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 12 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

~ _ _ _ _

Step Action Standard Eva1 Comments

• 19B If RRP B speed increases rapidly, lock scoop tube. -

IF speed increases rapidly, Trip scoop tube on affected generator by depressing SCOOP TUBE B LOCK OR RESET HS-B31-1S03B TRIP pushbutton.

Depresses the SCOOP TUBE B LOCK OR RESET HS-B31-I S03B TRIP pushbutton.

AND Verifies annunciator AR-I 02-D05, RECIRC MG B SCOOP TUBE DRIVE LOCK is LIT.

208 Verify RRP B limiter #2 is reset by light indication. Observe Green light above LOSS OF FW PP RUNBK RESET HS-B31-1S12B pushbutton EXTlNGUISHED.

Verifies:

Green light NOT LIT.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i' PERFORMANCE CHECKLIST Page 13 of 13 Appl. To/JPM No.: S/RO 64.0P.004.153 Student Name:

Step Action Standard Eva1 Comments 21 Check annunciator status. Check RECIRC A(B) FLOW LIMIT RUNBACK annunciator CLEARED.

Verifies annunciator SLOW FLASH for :

AR-102-CO1 RECIRC A FLOW LIMIT RUNBACK.

AND AR-102-C04 RECIRC B FLOW LIMIT RUNBACK

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS:

A. The plant is in Mode I 6 . Rods 18-23, 18-39,42-23, and 42-39, are fully inserted to support HCU maintenance on Rod 18-23.

C. A trip of CWP I D has caused a Reactor Recirculation runback to occur D. NO Operator actions have been taken.

INITIATING CUE:

Respond to a loss of reactor recirculation flow and reset recirculation pump runback in accordance with appropriate Off Normal procedure.

Page 1 of 2 2003 NRC Exam Rev. 1

TASK CONDITIONS:

L A. The plant is in Mode 1.

B. Rods 18-23, 18-39, 42-23, and 42-39, are fully inserted to support HCU maintenance on Rod 18-23.

C. A trip of CWP 1D has caused a Reactor Recirculation runback to occur.

D. NO Operator actions have been taken.

INITIATING CUE:

Respond to a loss of reactor recirculation flow and reset recirculation pump runback in accordance with appropriate Off Normal procedure.

Page 2 of 2 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 79.0P.006.101 0 06117/03 272000 A I . O l 3.213.2 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. KIA Task

Title:

Transfer Containment Radiation Monitor Pumps Completed By: Reviews:

Russ Halm 06/17/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head

--.-- IO Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #lS.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-125A Rev.4, (OVOO)

Page 1 of 1 2003 NRC Exam Rev. 1 File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 79.0P.006.101

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

I . Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. OP-179-003 Containment Radiation Monitoring (Rev. 4) 111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None

\-

IV. TASK CONDITIONS A. A Containment Radiation Monitor Sample Pump IP262A2 is running and IP262A1 is in stand by.

B. Chemistry recommends transferring AContainment Radiation Monitor Sample Pumps.

V. INITIATING CUE From the control room, transfer the operating A Containment Radiation Monitor Sample Pump from 1P262A2 to 1P262A1.

VI. TASK STANDARD 1P262A1 is in operation, and 1P262A2 is shutdown and isolated.

Form STCP-QA-12SA Rev 4, (0900)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 3 of 4 Appl. To/JPM No.: S/RO 79.0P.006.101 Student Name:

~~ ~~~

Step Action Standard Eva1 Comments EVALUATOR NOTE:

This JPM must be performed in the simulator.

Establish task conditions as directed on attached setup instructions.

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

1 Candidate locates procedure and refers to Obtains procedure appropriate section. OP-I 79-003 Containment Radiation Monitoring System and refers to section 3.3.

2 Reviews prerequisites and precautions. Reviews prerequisites and precautions.

EVALUATOR NOTE:

The only way to transfer pumps from this keypad is to get to the correct menu. If candidate depresses wrong key and doesnt immediately get to the correct screen, it is acceptable for the candidate to retry getting to the correct screen.

• 3 Brings up base menu screen. Presses # 0 on CRM AAir Sample Rad Monitor keypad.

Verifies:

screen change

• Critical Step #Critical Sequence Form STCP-QA-12SA Rev. 4, (OYOO) page I of 1 2003 NRC Exam Rev. 1

i\ i PERFORMANCE CHECKLIST Page 4 of 4 Appl. To/JPM No.:S/RO 79.0P.006.101 Student Name:

~ ~_____ ~

Step Action Standard Comments

• 4 Brings up System controls screen. Presses # ISystem Controls on CRM A Air Sample Rad Monitor keypad.

Verifies:

screen change

• 5 Start Containment Radiation Monitor Sample Presses # 3 Pump 1 Control on CRM A Air Pump IP262A1. Sample Rad Monitor keypad.

6 Observe control status block clear for pump Verifies small block next to pump 2 is clear.

2.

7 Observe control status block OFF for pump Verifies control status block OFF is LIT 2.

8 Observe control status block LIT for pump 1. Verifies small block next to pump 1 is LIT.

9 Observe control status block OFF Verifies control status block OFF.

10 Brings up base menu screen. Presses # 0 Exit on CRM AAir Sample Rad Monitor keypad.

Verifies:

screen change

• Critical Step #Critical Sequence Form STCP-QA-IZSA Rev. 4, (OSIOO)

Page 1 of 1 2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 5 of 4 Appl. To/JPM No.: S/RO 79.0P.006.101 Student Name:

Step Action Standard Eva1 I Comments I1 Brings up Display current data screen. Presses # 3 Display Current Data on CRM AAir Sample Rad Monitor keypad.

Verifies:

screen change 12 Brings up System controls screen. Presses # 3 System on CRM AAir Sample Rad Monitor keypad.

Verifies:

screen change 13 Observe a flowrate of - 1 SCFM. Verifies:

Sample Flowrate - 1 SCFM.

EVALUATOR NOTE:

This completes the JPM.

• Critical Step #Critical Sequence Form STCP-QA-lZ5A Rev. 4, (05/00)

Page I of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS L- A. AContainment Radiation Monitor Sample Pump 1P262A2 is running and 1P262A1 is in stand by.

B. Chemistry recommends transferring A Containment Radiation Monitor Sample Pumps.

INITIATING CUE From the control room, transfer the operating A Containment Radiation Monitor Sample Pump from 1P262A2 to 1P262A1.

Page Iof 2 Form STCP-QA-125A Rev. 4,(05/00)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS L- A. A Containment Radiation Monitor Sample Pump 1P262A2 is running and 1P262A1 is in standby.

B. Chemistry recommends transferring A Containment Radiation Monitor Sample Pumps.

INITIATING CUE From the control room, transfer the operating A Containment Radiation Monitor Sample Pump from 1P262A2 to 1P262Al.

Page 2 of 2 Form STCP-QA-125A Rev. 4, (OS/OO)

Page 1 of I 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 64.ON.005.101 2 06117/03 202001 A2.10 3.513.9 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. KIA Task

Title:

Respond To A Reactor Recirculation Pump Dual Seal Failure IAW ON-164-003 Completed By: Reviews:

Russ Halm 06/17/03 Writer Date InstructoriWriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head

-...-- 20 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1 File No. A14-5B

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 64.0N.005.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

I.Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C: If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. ON-164-003, Reactor Recirculation Pump Dual Seal Failure (Rev. 15)

B. AR-102-GO1, RECIRC PUMP A SEAL LEAKAGE HI FLOW (Rev.21)

C. AR-102-GO2, RECIRC PUMP A SEAL STAGE HI-LO FLOW (Rev.21) 111. REACTIVITY MANIPULATIONS

--.--- This JPM satisfies the requirements of Operational Activity@):

A. 28 Reactor Recirc Pump Dual Seal Failure B. 33 10 Percent Power Change (RoddRecirc)

IV. TASK CONDITIONS A. The plant is in Mode 1 at approximately 44 percent reactor power.

B. A Reactor Recirculation Pump Dual Seal Failure is about to occur C. You are the PCOM and will operate all controls for this event.

V. INITIATING CUE Using the appropriate Off-Normal procedure, Perform all required operator actions to mitigate the consequences of the event.

VI. TASK STANDARD AReactor Recirculation Pump shutdown and isolated.

STCP-QA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

( (

PERFORMANCE CHECKLIST Page 3 of 9 Appl. To/JPM No.: S/RO 64.0N.005.101 Student Name:

~

Step Action Standard Eva1 Comments EVALUATOR NOTE:

This JPM must be performed in the simulator.

Establish task conditions as directed on attached setup instructions.

When candidate is ready to begin JPM, place the simulator in RUN and Depress P-I .

Ac.;nowledge and respond to alarms. Checks RECIRC PP A and B SEAL CAVITY 2 pressure indicators PI-B31-1R602A and B.

Refers to AR-I 02-GO1 and AR-102-G02.

Determines that 'ARRP has the dual seal failure.

Candidate locates procedure and refers to Obtains procedure appropriate section. ON-I 64-003, Reactor Recirculation Pump Dual Seal Failure and refers to section 3.1.

Has Unit Supervisor record the date and Identifies Shift Supervision must sign to time. authorize implementation.

EVALUATOR CUE:

Inform the candidate the Unit Supervisor has signed and dated the procedure.

"Critical Step #Critical Sequence STCP-QA-1258 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(

PERFORMANCE CHECKLIST Page 4 of 9 Appl. To/JPM No.: S/RO 64.0N.005.101 Student Name:

Step Action Standard Eva1 Comments EVALUATOR NOTE:

Step 3.2 of the procedure directs the PCO to either determine the leak rate or obtain Shift Supervision approval to continue the procedure. If necessary instruct the student to continue with procedure.

Check if procedure should be continued. Informs supervisor that RCS leak rate check should be performed.

(SO-100-006 attachments E and F)

AND Requests direction for procedure completion.

EVALUATOR CUE:

Role play the SRO instruct the candidate to continue with procedure.

Check drywell pressure rate of increase Checks any drywell pressure indicator and determines drywell pressure is NOT increasing EVALUATOR CUE: rapidly.

IF necessary, Role play the SRO instruct the candidate for the purposes of this JPM, drywell pressure is NOT increasing rapidly.

Selects the correct procedure section. Selects Section 3.4.

• Critical Step #Critical Sequence STCP-QA-12%

Rev. 2.(9193)

Page 1 of 1 2003 NRC Exam Rev. 1

i (

PERFORMANCE CHECKLIST Page 5 of 9 Appl. To/JPM No.: S/RO 64.0N.005.101 Student Name:

Step Action Standard Eva1 Comments 7 Checks if power reduction is required. Checks APRMs and core flow indications.

Plots position on the Power/Flow Map to ensure power is below the 70 percent Rod Line.

Determines power reduction is not required.

CAUTION WHEN REDUCING RECIRC PUMP SPEED TO 30% RATED, PUMP SPEED SHOULD BE MAINTAINED AT APPROXIMATELY 500 RPM. SPEED OSCILLATIONS ARE POSSIBLE WHEN THE PUMP IS OPERATED 460 - 485 RPM.

• 8 Reduce 1A RRP speed to 30%. Depresses DEC pushbutton on REACTOR RECIRC PUMP A SPEED CONTROLLER SY-B31-1R621A until GEN I A SPEED SI-14032A DECREASES to 30%.

• 9 Shutdown 1A RRP. Depresses STOP pushbutton on MG SET A DRV MTR BKR HS-14001A.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i (\

PERFORMANCE CHECKLIST Page 6 of 9 Appl. To/JPM No.: S/RO 64.0N.005.101 Student Name:

~

~~

Step Action Standard Eva1 Comments IO Determine actual core flow. Determines position on power to flow map:

0 Determines B RRP speed is <75% using GEN 1B Speed SI-140-328.

0 Uses PlCSY display to obtain computer point NJP51-Core PI Press.

0 Plots core plate dlp on form GO-100-009-2, Core Flow vs Core Pressure Drop.

0 Determines core flow value is 42-43,000 Ibm/hr.

0 Plots position on Power to Flow Map using above value and current power.

Determines position is below the 70% rod line.

I1 Verify 1A RRP stops. Checks MG SET A DRV MTR BKR HS-14001A Amber light LIT Red light NOT LIT GEN 1A SPEED SI-14032A DECREASES to 20 (Bottom scale)

After -20 seconds GENERATOR 1A FIELD BREAKER Amber light LIT Red light NOT LIT

• Critical Step #Critical Sequence STCP-CIA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

('

PERFORMANCE CHECKLIST i:-

Page 7 of 9 Appl. To/JPM No.: S/RO 64.0N.005.101 Student Name:

Step Action Standard Eva1 Comments 12 Comply with COLR. Candidate informs Unit Supervisor of the need to reference section 8 of the COLR for compliance.

EVALUATOR CUE:

Role play the SRO and instruct candidate that you will reference section 8 of the COLR for compliance.

13 Comply with Tech Spec LCOs 3.4.1. Candidate informs Unit Supervisor of the need to reference Tech Spec LCOs 3.4.1 for compliance.

EVALUATOR CUE:

Role play the SRO and instruct candidate that you will reference Tech Spec LCOs 3.4.1 for compliance.

EVALUATOR NOTE:

The following steps will isolate the leaking seals and they must be completed in the order listed.

Valves HV-143-F023A, HV-144-FI OO, HV-143-F031A, and HV-143-FO32A have long stroke times (60-120 seconds).

1. • I4 Close suction valve. Depresses Close pushbutton on RECIRC PUMP A SUCT HV-143-FO23A.

Verifies Amber light LIT Red light NOT LIT

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

i i PERFORMANCE CHECKLIST Page 8 of 9 Appl. To/JPM No.: S/RO 64.0N.005.101 Student Name:

Step Action Standard Eva1 Comments

1. • I 5 Close RWCU suction from loop A. Depresses Close pushbutton on RWCU SUCT LOOP A HV-144-F100.

Verifies Amber light LIT Red light NOT LIT

1. I6 Place bypass switch to TEST. Locates and inserts key in RECIRC A MOV OL BYPS HV-143-FO31A and places to TEST position.

Verifies:

Status light RECIRC SYS A DISCHARGE VALVES IN TEST - LIT Alarm AR-I 02-102 RECIRC LOOP A DISCHARGE VALVES IN TEST actuated

1. • I7 Close discharge valve. Depresses Close pushbutton on RECIRC PUMP A DSCH HV-143-FO31A.

Verifies Amber light LIT Red light NOT LIT

1. • I8 Close discharge bypass. Depresses Close pushbutton on RECIRC PUMP A DSCH BYPS HV-143-FO32A.

Verifies Amber light LIT Red light NOT LIT

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2.(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 9 of 9

. Appl. TolJPM No.: SlRO 64.0N.005.101 Student Name:

Step Action Standard Eva1 Comments 19 After 2 minutes Return bypass switch to After 2 minutes NORM. Places RECIRC A MOV OL BYPS HV-143-F031A switch to NORM position.

• 20 Close CRD water supply. Contacts NPO on radio or plant page, and requests CRD Water Supply to Unit 1 RRP A IS0 143F008A closed.

BOOTH CUE:

Acknowledge request to close CRD Water Supply to RRP A IS0 143F008A.

Wait 2 minutes and Depress P-2 Then Contact CR and report CRD Water Supply to Unit 1RRP A IS0 143F008A is closed.

EVALUATOR NOTE:

This completes the JPM.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

c TASK CONDITIONS A. The plant is in Mode 1 at approximately 44 percent reactor power.

B. A Reactor Recirculation Pump Dual Seal Failure is about to occur.

C. You are the PCOM and will operate all controls for this event.

INITIATING CUE Using the appropriate Off-Normal procedure, Perform all required operator actions to mitigate the consequences of the event.

Page 1 of 2 STCP-W-1255 Rev. 2, (9/93)

Page 1 of1 2003 NRC Exam Rev. 1

TASK CONDITIONS A. The plant is in Mode Iat approximately 44 percent reactor power.

B. A Reactor Recirculation Pump Dual Seal Failure is about to occur.

C. You are the PCOM and will operate all controls for this event.

INITIATING CUE Using the appropriate Off-Normal procedure, Perform all required operator actions to mitigate the consequences of the event.

Page 2 of 2 STCP-QA-1258 Rev. 2,(9193)

Page 1 of 1 2003 NRC Exam Rev. 1

~

\

PENNSYLVANIA POWER & LIGHT COMPANY C'

JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 51.OP.002.152 I 06117/03 209001 A2.01 3.813.7 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. KIA Task

Title:

Perform Manual Startup Component by Component of Core Spray System in Accordance With OP-I 51-001 Completed By: Reviews:

Russ Halm 06117/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head L 20 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

Form STCP-QA-IZSA Rev. 4, (OSIOO)

Page 1 of 1 2003 NRC Exam Rev. 1 File No. A14-5B /'

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE SlRO 51.OP.002.152

'v'

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. OP-I 51-001 Core Spray System (Revision 24)

III. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None

-- IV. TASK CONDITIONS A. The Core Spray System is aligned for automatic initiation in accordance with OP-151-001.

B. A LOCA has occurred.

C. Generator lockouts have been reset.

D. CS System failed to auto initiate.

V. INITIATING CUE Manually initiate both loops of core spray.

VI. TASK STANDARD Both loops of core spray injecting into the RPV.

\---

Form STCP-QA- 125A Rev. 4, (OS/OO)

Page I of 1 2003 NRC Exam Rev. 1

(

i,,

PERFORMANCE CHECKLIST Page 3 of 8 Appl. To/JPM No.: S/RO 51.OP.002.152 Student Name:

Step Action Standard Eva1 Comments EVALUATOR This JPM must be performed in the simulator.

0 Establish task conditions as directed on attached setup instructions.

0 The FAULTED step in this JPM is preceded by a fault statement in BOLD TYPE WITH ALL CAPITAL LETTERS.

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

1 Locates procedure and refers to appropriate Obtains procedure section. OP-151-001 Core Spray System and refers to section 3.3.

2 Reviews prerequisites and precautions. Reviews prerequisites and precautions.

• 3 Initiate A Loop of Core Spray. Rotates the collar on Core Spray Loop A MAN INlT HS-E21-1SIGA pushbutton to the ARMED position.

Verifies that AR-109-AOI . Core Spray Loop EVALUATOR A Man lnit Switch Armed, annunciator The following annunciator alarms, AR-109-A01 alarms.

(Core Spray Loop A Initiation Switch Armed).

Depress Core Spray Loop A MAN INlT HS-E21-1Sl6A pushbutton.

Verifies CORE SPRAY LOOP A ACTUATED alarm LIT.

• Critical Step #Critical Sequence FormSTCP-QA-12SA Rev. 4, (OYOO)

Page I of 1 2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 4 of 8 Appl. To/JPM No.: S/RO 51.OP.002.152 Student Name:

Step .- -.- ..

.Adinn Standard Eva1 Comments EVALUATOR NOTE:

In an effort to initiate both l o o ~ of s core spray as quickly as possible, the candidate may elect to initiate loop B spray by performing steps 7-13 of this JPM before completing steps 4-6. This is acceptable.

Observe response of other systems to initiation of Verifies:

core spray. DG Astarted by observing DG voltage A DW unit cooler fans running in FAST trip Red high speed fast light-NOT LIT Observe core spray system response. Verifies:

1P206A and C running.

Amber light NOT LIT Red light LIT CORE SPRAY LOOP A INlT SIG RESET HS-E21-1S I 7A Green light LIT CORE SPRAY LOOP A IB INJ SHUTOFF HV-152-F005A open.

Amber light NOT LIT Red light LIT Critical Step #Critical Sequence Form STCP-QA-l2JA Rev. 4, (OYOO)

Page I of I 2003 NRC Exam Rev. I

i PERFORMANCE CHECKLIST Page 5 of 8 Appl. To/JPM No.: S/RO 51.0P.002.152 Student Name:

Step Action Standard Eva1 Comments CAUTION AVOID POTENTIAL PUMP/MOTOR DAMAGE, CORE SPRAY LOOP A(B) INJ SHUTOFF HV-152F005A(B) MUST BE THROTTLED AS NECESSARY TO PREVENT EXCEEDING MAXIMUM PUMP RUN OUT CURRENT OF 90 AMPS PER PUMP.

CORE SPRAY LOOP A OB INJ SHUTOFF HV-152-FO04A open.

Amber light NOT LIT Red light LIT CORE SPRAY LOOP A TEST TO SUPP POOL HV-I 52-FO15A closed.

Amber light LIT Red light NOT LIT CORE SPRAY LOOP A MIN FLOW HV-152-F031A closed.

Amber light LIT Red light NOT LIT CS Unit Coolers lV211A and C as indicated on IC681 running.

Red light LIT Amber and white lights NOT LIT 6 Verifies injection flowrate. Observes flowrate on FI-E21-1R601A.

• Critical Step #Critical Sequence Form STCP-QA-I25A Rev. 4, (05/00)

Page I of 1 2003 NRC Exam Rev. 1

(

PERFORMANCE CHECKLIST Page 6 of 8 Appl. To/JPM No.: S/RO 51.OP.002.152 Student Name:

Step Action Standard Eva1 Comments FAULT STATEMENT LOOP B CORE SPRAY FAILS TO INITIATE WHEN THE MANUAL PUSHBUTTON IS ARMED AND DEPRESSED.

Initiate B Loop of Core Spray. Rotates the collar on Core Spray Loop B MAN INlT HS-E21-1SIGB pushbutton to the ARMED position.

EVALUAT0 R The followina annunciator alarms. ARI 13-A01 Notes that AR-113-AOI , Core Spray Loop B (Core SprafLoop B Initiation Switch Armed). Man Init Switch Armed, annunciator alarms.

Depress Core Spray Loop B MAN INlT HS -

E21-1S16B pushbutton.

Notes that Core Spray Loop B failed to initiate.

EVALUATOR CUE Informs Unit Supervisor division 2 manual As Unit Supervisor acknowledge notification of initiation has failed.

division 2 Core Spray initiation failure.

Notes Manual Startup required for B Loop Core Spray.

Transitions to appropriate section of the Moves to section 3.3.4 of procedure OP-I 51-procedure. 001 Core Spray System.

EVALUATOR NOTE:

Manual startup component by component of B Loop of CS System will be accomplished in the following steps.

• Critical Step #CriticaI Sequence FormSTCP-QA-12JA Rev 4, (OS/aO)

Page 1 of 1 2003 NRC Exam Rev. 1

(,"  !,'

PERFORMANCE CHECKLIST Page 7 of 8 Appl. To/JPM No.: S/RO 51.OP.002.152 Student Name:

Step Action Standard Eva1 Comments

• 9 Start Core Spray Pumps B and D. Place the HS for 1P206B and D to the START position.

Verifies:

Amber lights NOT LIT; Red lights LIT 10 Open or check open OB INJ SHUTOFF Verifies that HV-I 52-FO04B open.

HV-152-FO04B. Amber light NOT LIT Red light LIT

• I 1 When Reactor pressure 5436 psig, place LO RX When Reactor pressure 2436 psig, PRESS PERM Switch HS-152-15249B to removes cover and places HS-15249B to BYPASS. BYPASS.

• I 2 THROTTLE OPEN CORE SPRAY LOOP " B IB Throttles open HV-I 52-FO05B INJ SHUTOFF HV-152-FO05B to establish loop flow 56,350 gpm for two-pump operation.

13 Verifies injection flowrate. Observes flowrate on FI-E21-1R601B.

EVALUATOR Verifies MIN FLOW HV-152-F031B closes by When HS for HV-152-FO05 B taken to OPEN Checking position; red light on. Amber light LIT When CS system flow 2635 gpm F031B; Red light NOT LIT amber light on.

• Critical Step #Critical Sequence Form STCP-QA-IZSA Rev. 4, (OYOO)

Page I of 1 2003 NRC Exam Rev. 1

(

PERFORMANCE CHECKLIST Page 8 of 8 Appl. To/JPM No.: S/RO 51.OP.002.152 Student Name:

Step Action Standard Eva1 Comments 14 Check CS room coolers B/D AUTO starts. Check CS Unit Coolers 1V211B and D AUTO START as indicated on 1C681.

Verifies:

Red light LIT Amber and white lights NOT LIT EVALUATOR NOTE:

This completes the JPM.

• Critical Step #Critical Sequence Form STCP-QA-IZSA Rev 4, (05/00)

Page I of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS A. The Core Spray System is aligned for automatic initiation in accordance with OP-I 51-001.

B. A LOCA has occurred.

C. Generator lockouts have been reset.

D. CS System failed to auto initiate.

INITIATING CUE Manually initiate both loops of core spray.

Page 1 of 2 Form STCP-QA-125A Rev. 4, (OYOO)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS L

A. The Core Spray System is aligned for automatic initiation in accordance with OP-I 51-001.

B. A LOCA has occurred.

C. Generator lockouts have been reset.

D. CS System failed to auto initiate.

INITIATING CUE Manually initiate both loops of core spray.

Page 2 of 2 Form STCP-QA-IZSA Rev. 4, (OYOO)

Page I of I 2003 NRC Exam Rev. 1

PENNSYLVANIA POWER & LIGHT COMPANY

---

JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 84.0N.003.101 1 OW1 7/03 239001 A4.01 4.214.0 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Main Steam Line Isolation and Quick Recovery in Accordance With ON-184-001 Completed By: Reviews:

Russ Halm 06/17/03 Writer Date Instructor/Writer Date Approval:

Requesting Supv./C.A. Date Nuclear Trng. Supv. Date Head 50 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

L-' STCP-QA-12%

Rev. 2. (9193)

Page 1 of 1 File No. A14-5B 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE

\-

S/RO 84.0N.003.101 I. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required andlor posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. ON-184-001 MAIN STEAM LINE ISOLATION AND QUICK RECOVERY (Rev. 6 )

111. REACTIVITY MANIPULATIONS This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. An MSIV isolation and reactor scram occurred from 100% reactor power.

B. The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.

C. HPCl and/or RClC injection is controlling reactor water level.

D. Reactor pressure is controlled by manual SRV actuation.

E. Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.

V. INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.

VI. TASK STANDARD MSlVs OPEN 2003 NRC Exam Rev. 1

VI. TASK SIGNIFICANCE Inability to reopen the MSlVs would eliminate a heat sink reuuirinq additional enemy to be added to the Primary Containment.

2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 3 of 12 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments Evaluator 0 This JPM should be performed in the Simulator.

Establish task conditions as directed on attached setup instructions.

0 When student is ready to begin JPM, place the Simulator in RUN.

1 Obtain a controlled copy of ON-184-001. Obtains Control copy of ON-184-001, 2 RECORD date and time of this event.

• 3 PLACE control switches for following to CLOSE: Places the control switch to CLOSE for the following:

0 Mn Stm Line A IB Is0 HV-141-FO22A MN STM LINE A IB IS0 HV-141-F022A Mn Stm Line B IB Is0 HV-141-FO22B MN STM LINE B IB IS0 HV-141-F022B Mn Stm Line C IB Is0 HV-141-FO22C MN STM LINE C IB IS0 HV-141-F022C MN STM LINE D IB IS0 HV-141-Mn Stm Line D IB Is0 HV-141-FO22D F022D MN STM LINE A OB IS0 HV-141-0 Mn Stm Line A OB Is0 HV-141-FO28A F028A MN STM LINE B OB IS0 HV-141-Mn Stm Line B OB Is0 HV-141-FO28B F028B MN STM LINE C OB IS0 HV-141-Mn Stm Line C OB Is0 HV-141-FO28C F028C MN STM LINE D OB IS0 HV-141-0 Mn Stm Line D OB Is0 HV-141-FO28D F028D

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments 4 ENSURE Mn Stm Line IB Drain HV-141-F016 Checks amber light LIT and red light CLOSED. NOT LIT for:

MN STM LINE IB DRAIN HV-141-F016 5 ENSURE Mn Stm Line OB Drain HV-141-F019 Checks amber light LIT and red light CLOSED. NOT LIT for:

MN STM LINE OB DRAIN HV-141-FO19 6 ENSURE Mn Stm Line Drain to Cdsr HV-141-F021 Checks amber light LIT and red light CLOSED. NOT LIT for:

0 MN STM LINE IB DRAIN TO CDSR HV-14 1-F021 7 ENSURE following TRIPPED: For the Main Turbine:

0 Main Turbine 0 Checks Main Turbine trip annunciation ON 0 Red Main Turbine Trip status light is LIT and the green Reset status light is NOT LIT.

For each RFP:

0 Checks RFP Trip annunciation LIT Reactor Feed Pump Turbine A Amber light is LIT and red light 0 Reactor Feed Pump Turbine B above the Trip & Reset switch NOT LIT Reactor Feed Pump Turbine C

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

(' i'

\,

PERFORMANCE CHECKLIST Page 5 of 12 Appl. TolJPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments 8 If isolation due to EHC System malfunction: Determines the isolation was not due to 0 DEPRESS standby EHC Hyd Fluid Pump an EHC system malfunction.

1P I 13B(A) STOP push button.

(Based on initial conditions) 0 DEPRESS operating EHC Hyd Fluid Pump IP I 13A(B) STOP push button.

0 ENSURE Turbine main stop valves CLOSED.

ENSURE Turbine bypass valves CLOSED.

9 CLOSE following by depressing Drip Leg Drn Depresses the AUTO pushbutton on HS-I 0112 AUTO push button: DRIP LEG DRN HS-10112.

Checks white light LIT and red light 0 Drip Leg Drn HV-10112A1. NOT LIT.

0 Drip Leg Drn HV-I 011281.

Checks amber light LIT and red light Drip Leg Drn HV-10112C1. NOT LIT for :

DRIP LEG DRAIN HV-10112A1 0 Drip Leg Drn HV-lOll2Dl.

DRIP LEG DRAIN HV-10112B1 DRIP LEG DRAIN HV-10112C1 DRIP LEG DRAIN HV-10112D1 10 CLOSE BPV Hdr Drip Leg Drn Byps HV-10108A Depresses the AUTO pushbutton on by depressing HS-I 0108A AUTO push button. HS-10108A to CLOSE HV-10108A.

AND Verifies the white light is LIT and the red light is NOT LIT.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2,(9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Page 6 of 12 Appl. To/JPM No.: SIR0 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments 11 CLOSE MSV Bst Drn HV-10101 A,B,C,D by Depresses the CLOSE pushbutton for depressing common CLOSE push button. MSV BST DRN HV-IOI~IA,B,C,D.

AND Verifies amber light LIT and red light NOT LIT.

12 CLOSE SSE Mn Stm Sup CV HV-10703. Depress and hold the CLOSE pushbutton for SSE MN STM SUP CV HV-10703.

AND Verifies amber light LIT and red light NOT LIT.

13 ENSURE SSE Mn Stm Sup Ln Drn HV-10767 Verifies amber light LIT and red light CLOSED. NOT LIT for SSE MN STM SUP LN DRN HV-10767.

14 ENSURE SSE Mn Stm Sup Ln Drn HV-10768 Verifies amber light LIT and red light CLOSED. NOT LIT for SSE MN STM SUP LN DRN HV-10768.

15 CLOSE SSE Press Ctlr Is0 HV-10704, Depresses the CLOSE pushbutton for SSE PRESS CTLR IS0 HV-10704.

AND Verifies amber light LIT and red light NOT LIT.

• Critical Step #Critical Sequence STCP-QA-1255 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 7 of 12 Appl. TolJPM No.: S/RO 84.0N.003.101 Student Name:

I I Step 16 Action THROTTLE OPEN SSE Press Ctlr Byps Standard THROTTLE OPEN SSE PRESS CTLR Eva1 Comments l l HV-10705 to establish 0.25 to 0.50 psis on SSE Pressure PI-I 0723. 1 BYPS HV-10705 to establish 0.25 to 0.5 psig on SSE Pressure indication PI-1 I I I EVALUATOR CUE:

After HV-10705 is throttled open several times AND Verifies red and amber lights LIT for I I inform the candidate PI-I0723 is reading 0.4 psig HV-10705.

17 CLOSE Mn Stm SJAE Is0 HV-10107. Depress the CLOSE pushbutton for MN STM SJAE IS0 HV-10107.

AND Verifies the amber light LIT and red light NOT LIT.

When directed by Shift Supervision AND initiating event is determined and cleared, RESET NSSSS Main Steam Line Isolation by depressing:

Evaluator As the Unit Supervisor direct resetting the NSSSS Main Steam Line Isolation.

I

-*I8 Mn Stm Line Div 1 Is0 Reset HS-921-1S32 Reset Depresses the RESET pushbutton for: I push button.

MN STM LINE DIV 1 IS0 RESET HS-B21-1S32.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

I I PERFORMANCE CHECKLIST Page 8 of 12 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments 19 Mn Stm Line Div 2 Is0 Reset HS-B21-1S33 Reset Depresses the RESET pushbutton for:

push button.

MN STM LINE DIV 2 IS0 RESET HS-B21-I S33.

AND Verifies that all 4 white status lights are LIT for the MSlV trip logic.

NOTE:

If primary containment integrity in jeopardy, it is acceptable to open MSIVs (IB first) with AP > 200 PSID. This action will not damage MSIVs. If conditions permit, equalizing around MSIVs is preferred.

EVALUATOR CUE: Candidate asks if Primarv Containment is in Jeopardv. fif If asked by the candidate if primary containment is in ieoprardy reply, primary containment intearitv

!I is i.!n jeopardy

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 9 of 12 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments

• 20 To OPEN I6 MSIVs PLACE following - control Places the control switch to AUTO for:

switches to AUTO: b MN STM LINE A I6 IS0 HV-141-Mn Stm Line A I6 Is0 HV-141-FO22A. F022A Mn Stm Line B IB Is0 HV-141-FO22B. b MN STM LINE B IB IS0 HV-141-Mn Stm Line C IB Is0 HV-141-FO22C. F022B Mn Stm Line D I6 Is0 HV-141-FO22D. b MN STM LINE C I6 IS0 HV-141-F022C B MN STM LINE D IB IS0 HV-141-F022D AND Verifies amber light NOT LIT and red light LIT for each valve.

1. 21 ALIGN for steam line pressurization as follows: Inserts key and rotates clockwise to place AC MOV OL BYPS HS-B21-PLACE AC MOV OL BYPSHS-B21-1S37A to 1S37A to TEST.

TEST.

AND Verifies annunciator AR-111-H03, AC CONTN IS0 VLVS IN TEST is LIT.

PLACE DC MOV OL BYPSHS-B21-1S37B to Inserts key and rotates clockwise to TEST. place DC MOV OL BYPS HS-B21-lS37B to TEST.

AND Verifies annunciator AR-112-H03, OUTBOARD ISOLATION VLVS IN TEST is LIT.

• Critical Step #Critical Sequence STCP-CIA-1256 Rev. 2.(9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 10 of 12 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments OPEN Mn Stm Line IB Drain HV-141-F016. Place switch to OPEN for MN STM LINE IB DRAIN HV-141-FO16.

AND Verifies amber light NOT LIT and red light LIT OPEN Mn Stm Line OB Drain HV-141-FO19. Place switch to OPEN for MN STM LINE OB DRAIN HV-141-F019.

AND Verifies amber light NOT LIT and red light LIT ENSURE Mn Steam Line Warm Up HV-14l-FO20 Verifies red light LIT and amber light OPEN. NOT LIT.

After 2 minutes, PLACE AC MOV OL Byps After 2 minutes, place the AC MOV 0 HS-B21-1S37A to NORM. BYPS HS-B21-1S37A to NORM.

AND Verifies annunciator AR-111-H03, AC CONTN IS0 VLVS IN TEST is NOT LIT

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 11 of 12 Appl. ToIJPM No.: SIR0 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments After 2 minutes, PLACE DC MOV OL Byps After 2 minutes, place the DC MOV OL HS-921-1S37B to NORM. BYPS HS-B21-1S37B to NORM.

AND Verifies annunciator AR-112-H03, OUTBOARD ISOLATION VLVS IN TEST is NOT LIT

1. 22 OBSERVE main steam line pressure Verifies main steam line pressure INCREASING on Main Stm Press PR-10101C. INCREASING on Main Stm Press PR-10101C.

CAUTION OPENING MSIV'S WITH LARGE DIFFERENTIAL PRESSURE WILL CAUSE RPV PRESSURE TO DROP RAPIDLY AND RPV LEVEL TO SWELL.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

( i" PERFORMANCE CHECKLIST Page 12 of 12 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments

1. 23 When differential pressure across MSlVs is Compares RPV pressure with steam between 53 psid and 200 psid, OPEN OB MSIV's line pressure on PR-I0101C until the by PLACING following control switches to AUTO: d/p is between 50 and 200 psid Mn Stm Line A OB Is0 HV-141-FO28A AND Mn Stm Line B OB Is0 HV-141-FO28B When outboard MSlV d/p is between 50 and 200 psid, OPENS the outboard Mn Stm Line C OB Is0 HV-141-FO28C MSlVs by placing the control switch to AUTO for:

Mn Stm Line D OB Is0 HV-141-FO28D MN STM LINE A OB IS0 HV-141-F028A MN STM LINE B OB IS0 HV-141-F028B MN STM LINE C OB IS0 HV-141-F028C MN STM LINE D OB IS0 HV-141-F028D AND Verifies amber light NOT LIT and red light LIT for each valve.

Eva1uator Inform the student the JPM is complete.

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS A. An MSlV isolation and reactor scram occurred from 100% reactor power.

B. The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.

C. HPCl and/or RClC injection is controlling reactor water level.

D. Reactor pressure is controlled by manual SRV actuation.

E. Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.

INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.

Page 1 of 2 2003 NRC Exam Rev. 1

TASK CONDITIONS A. An MSlV isolation and reactor scram occurred from 100% reactor power.

B. The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.

C. HPCl and/or RClC injection is controlling reactor water level.

D. Reactor pressure is controlled by manual SRV actuation.

E. Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.

INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.

Page 2 of 2 2003 NRC Exam Rev. I

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 84.0N.003.101 1 06117/03 239001 A4.01 4.214.0 Appl. To JPM Number Rev. No. Date NUREG 1123 Sys. No. WA Task

Title:

Main Steam Line Isolation and Quick Recovery in Accordance With ON-184-001 Completed By: Reviews:

Russ Halm 06/17/03 Writer Date InstructorNVriter Date ApprovaI:

Requesting Supv.1C.A. Date Nuclear Trng. Supv. Date Head 50 Date of Performance: Allowed Time (Min.) Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I. Employee #/S.S. #

Performance ( ) Satisfactory ( ) Unsatisfactory Evaluation:

Evaluator Name:

Signature Typed or Printed Comments:

STCP-QA-125A Rev. 2,(9/93)

Page 1 of 1 File No. A14-58 2003 NRC Exam Rev. 1

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE

-._-- S/RO 84.0N.003.101

1. SAFETY CONSIDERATIONS A. All Operations personnel are responsible for maintaining their radiation exposure As Low As Reasonably Achievable in accordance with OP-AD-002, Standards for Shift Operations.

B. All applicable safety precautions shall be taken in accordance with established PPL safety policies and the Safety Rule Book, for example:

1. Whenever any electrical panel is opened for inspection during JPM performance.

2. Whenever entering any plant area where specific safety equipment; such as hearing or eye protection, safety shoes, hardhats, etc; is required and/or posted as being necessary.

C. If in the judgement of the evaluator any safety issue occurs during the performance of a JPM, the JPM will be terminated until the issue is resolved.

II. REFERENCES A. ON-184-001, MAIN STEAM LINE ISOLATION AND QUICK RECOVERY (Rev. 6)

II I. REACTIVITY MANIPULATlONS

=-J This JPM satisfies the requirements of Operational Activity(s):

None IV. TASK CONDITIONS A. An MSlV isolation and reactor scram occurred from 100% reactor power.

B. The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.

C. HPCl and/or RClC injection is controlling reactor water level.

D. Reactor pressure is controlled by manual SRV actuation.

E. Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.

V. INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.

VI. TASK STANDARD MSlVs OPEN 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Appl. To/JPM No.: SIR0 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments Evaluator 0 This JPM should be performed in the Simulator.

Establish task conditions as directed on attached setup instructions.

0 When student is ready to begin JPM, place the Simulator in RUN.

1 Obtain a controlled copy of ON-184-001. Obtains Control copy of ON-184-001.

2 RECORD date and time of this event.

• 3 PLACE control switches for following to CLOSE: Places the control switch to CLOSE for the following:

0 Mn Stm Line A IB Is0 HV-141-FO22A MN STM LINE A IB IS0 HV-141-F022A 0 Mn Stm Line B IB Is0 HV-141-FO22B MN STM LINE B IB IS0 HV-141-F022B 0 Mn Stm Line C IB Is0 HV-141-FO22C MN STM LINE C IB IS0 HV-141-F022C MN STM LINE D IB I S 0 HV-141-0 Mn Stm Line D IB Is0 HV-141-FO22D F022D MN STM LINE A OB IS0 HV-141-0 Mn Stm Line A OB Is0 HV-141-FO28A F028A MN STM LINE B OB IS0 HV-141-0 Mn Stm Line B OB Is0 HV-141-FO28B F028B MN STM LINE C OB IS0 HV-141-0 Mn Stm Line C OB Is0 HV-141-FO28C F028C MN STM LINE D OB IS0 HV-141-0 Mn Stm Line D OB Is0 HV-141-FO28D F028D

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 4 'ot I2 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step ____

Action Standard Eva1 Comments 4 ENSURE Mn Stm Line IB Drain HV-141-F016 Checks amber light LIT and red light CLOSED. NOT LIT for:

MN STM LINE IB DRAIN HV-141-F016 5 ENSURE Mn Stm Line OB Drain HV-141-F019 Checks amber light LIT and red light CLOSED. NOT LIT for:

MN STM LINE OB DRAIN HV-141-FO19 6 ENSURE Mn Stm Line Drain to Cdsr HV-141-F021 Checks amber light LIT and red light CLOSED. NOT LIT for:

0 MN STM LINE IB DRAIN TO CDSR HV-14 1-F021 7 ENSURE following TRIPPED: For the Main Turbine:

0 Main Turbine Checks Main Turbine trip annunciation ON 0 Red Main Turbine Trip status light is LIT and the green Reset status light is NOT LIT.

For each RFP:

Checks RFP Trip annunciation LIT 0 Reactor Feed Pump Turbine A 0 Amber light is LIT and red light 0 Reactor Feed Pump Turbine B above the Trip & Reset switch NOT LIT 0 Reactor Feed Pump Turbine C

• Critical Step #Critical Sequence STCP-QA-1258 Rev. 2.(9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page 5 ot 12 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments 8 If isolation due to EHC System malfunction: Determines the isolation was due to DEPRESS standby EHC Hyd Fluid Pump an EHC system malfunction.

1P I 13B(A) STOP push button.

(Based on initial conditions)

DEPRESS operating EHC Hyd Fluid Pump IP I 13A(B) STOP push button.

0 ENSURE Turbine main stop valves CLOSED.

0 ENSURE Turbine bypass valves CLOSED.

9 CLOSE following by depressing Drip Leg Drn Depresses the AUTO pushbutton on HS-10112 AUTO push button: DRIP LEG DRN HS-10112.

Checks white light LIT and red light 0 Drip Leg Drn HV-10112A1. NOT LIT.

Drip Leg Drn HV-10112B1.

Checks amber light LIT and red light 0 Drip Leg Drn HV-lOIl2Cl. NOT LIT for :

DRIP LEG DRAIN HV-10112Al Drip Leg Drn HV-10112D1.

DRIP LEG DRAIN HV-10112B1 DRIP LEG DRAIN HV-10112Cl 0 DRIP LEG DRAIN HV-10112D1 10 CLOSE BPV Hdr Drip Leg Drn Byps HV-10108A Depresses the AUTO pushbutton on by depressing HS-10108A AUTO push button. HS-10108A to CLOSE HV-10108A.

AND Verifies the white light is LIT and the red light is NOT LIT.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 6 ot 12 Appl. TolJPM No.: S/RO 84.0N.003.101 Student Name:

~~

Step Action Standard Eva1 Comments 11 CLOSE MSV Bst Drn HV-10101 A,B,C,D by Depresses the CLOSE pushbutton for depressing common CLOSE push button. MSV BST DRN HV-IOIOIA,B,C,D.

AND Verifies amber light LIT and red light NOT LIT.

12 CLOSE SSE Mn Stm Sup CV HV-10703. Depress and hold the CLOSE pushbutton for SSE MN STM SUP CV HV-10703.

AND Verifies amber light LIT and red light NOT LIT.

13 ENSURE SSE Mn Stm Sup Ln Drn HV-10767 Verifies amber light LIT and red light CLOSED. NOT LIT for SSE MN STM SUP LN DRN HV-10767.

14 ENSURE SSE Mn Stm Sup Ln Drn HV-10768 Verifies amber light LIT and red light CLOSED. NOT LIT for SSE MN STM SUP LN DRN HV-I 0768.

15 CLOSE SSE Press Ctlr Is0 HV-10704, Depresses the CLOSE pushbutton for SSE PRESS CTLR IS0 HV-10704.

AND Verifies amber light LIT and red light NOT LIT.

• Critical Step #Critical Sequence STCP-QA-1250 Rev. 2, (9/93)

Page 1 of1 2003 NRC Exam Rev. 1

PERFORMAN& CHECKLIST Page 7 ot 12 Appl. TolJPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments 16 THROTTLE OPEN SSE Press Ctlr Byps THROTTLE OPEN SSE PRESS CTLR HV-10705 to establish 0.25 to 0.50 psig on SSE BYPS HV-I0705 to establish 0.25 to Pressure PI-I 0723. 0.5 psig on SSE Pressure indication PI-10723.

EVALUATOR AND After HV-10705 is throttled open several times Verifies red and amber lights LIT for inform the candidate PI-I0723 is reading 0.4 psig HV-10705.

17 CLOSE Mn Stm SJAE Is0 HV-10107 Depress the CLOSE pushbutton for MN STM SJAE IS0 HV-10107.

AND Verifies the amber light LIT and red light NOT LIT.

When directed by Shift Supervision AND initiating event is determined and cleared, RESET NSSSS Main Steam Line Isolation by depressing:

Evaluator

- the NSSSS As the Unit Supervisor direct resettinn Main Steam Line Isolation.

18 Mn Stm Line Div 1 Is0 Reset HS-621-1S32 Reset Depresses the RESET pushbutton for:

push button.

0 MN STM LINE DIV 1 IS0 RESET HS-B21-IS32.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 8 ot 12 Appl. To/JPM No.: SIR0 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments 19 Mn Stm Line Div 2 Is0 Reset HS-B21-1S33 Reset Depresses the RESET pushbutton for:

push button.

MN STM LINE DIV 2 IS0 RESET HS-B21-1S33.

AND Verifies that all 4 white status lights are LIT for the MSlV trip logic.

NOTE:

If primary containment integrity in jeopardy, it is acceptable to open MSIVs (IB first) with AP > 200 PSID. This action will not damage MSIVs. If conditions permit, equalizing around MSIVs is preferred.

• 20 To OPEN IB MSIVs PLACE following control Places the control switch to AUTO for:

switches to AUTO: MN STM LINE A IB IS0 HV-141-Mn Stm Line A IB Is0 HV-141-FO22A. F022A Mn Stm Line B IB Is0 HV-141-FO22B. MN STM LINE B IB IS0 HV-141-Mn Stm Line C IB Is0 HV-141-FO22C. F022B Mn Stm Line D IB Is0 HV-141-FO22D. MN STM LINE C IB IS0 HV-141-F022C MN STM LINE D IB IS0 HV-141-F022D AND Verifies amber light NOT LIT and red light LIT for each valve.

• Critical Step #Critical Sequence STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

i: PERFORMANCE CHECKLIST

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Page 9 or 12 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments

1. 21 4LIGN for steam line pressurization as follows: Inserts key and rotates clockwise to place AC MOV OL BYPS HS-B21-PLACE AC MOV OL BYPSHS-B21-1S37A to 1S37A to TEST.

TEST.

AND Verifies annunciator AR-111-H03, AC CONTN IS0 VLVS IN TEST is LIT.

PLACE DC 1 OV OL Byps HS-B21-1S37B to Inserts key and rotates clockwise to TEST. place DC MOV OL BYPS HS-B21-1S37B to TEST.

AND Verifies annunciator AR-I 12-H03, OUTBOARD ISOLATION VLVS IN TEST is LIT.

OPEN Mn Stm Line IB Drain HV-141-FO16. Place switch to OPEN for MN STM LINE IB DRAIN HV-141-F016.

AND Verifies amber light NOT LIT and red light LIT OPEN Mn Stm Line OB Drain HV-141-F019. Place switch to OPEN for MN STM LINE OB DRAIN HV-141-F019.

AND Verifies amber light NOT LIT and red light LIT

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2.(9/93)

Page Iof 1 2003 NRC Exam Rev. 1

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PERFORMANCE CHECKLIST Page Io 'ot I2 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Eva1 Comments ENSURE Mn Steam Line Warm Up HV-141-F020 Verifies red light LIT and amber light OPEN. NOT LIT.

After 2 minutes, PLACE AC MOV OL Byps After 2 minutes, place the AC MOV OL HS-B21-1S37A to NORM. BYPS HS-B21-1S37A to NORM.

AND Verifies annunciator AR-I II-H03, AC CONTN IS0 VLVS IN TEST is NOT LIT After 2 minutes, PLACE DC MOV OL Byps After 2 minutes, place the DC MOV OL HS-B21-1S37B to NORM. BYPS HS-B21-1S37B to NORM.

AND Verifies annunciator AR-I 12-H03, OUTBOARD ISOLATION VLVS IN TEST is NOT LIT

1. 22 OBSERVE main steam line pressure Verifies main steam line pressure INCREASING on Main Stm Press PR-I 0101C. INCREASING on Main Stm Press PR-I0101C.

CAUTION OPENING MSIV'S WITH LARGE DIFFERENTIAL PRESSURE WILL CAUSE RPV PRESSURE TO DROP RAPIDLY AND RPV LEVEL TO SWELL.

• Critical Step #Critical Sequence STCP-QA-1256 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCk CHECKLIST Page 11OT 12 Appl. To/JPM No.: S/RO 84.0N.003.101 Student Name:

Step Action Standard Comments

1. 23 When differential pressure across MSlVs is Compares RPV pressure with steam between 50 psid and 200 psid, OPEN OB MSIVs line pressure on PR-10101C until the by PLACING following control switches to AUTO: dlp is between 50 and 200 psid Mn Stm Line A OB Is0 HV-141-FO28A AND Mn Stm Line B OB Is0 HV-141-FO28B When outboard MSlV d/p is between 50 and 200 psid, OPENS the outboard Mn Stm Line C OB Is0 HV-141-F028C MSIVs by placing the control switch to AUTO for:

Mn Stm Line D OB Is0 HV-141-F028D MN STM LINE A OB IS0 HV-141-F028A MN STM LINE B OB IS0 HV-141-F028B MN STM LINE C OB IS0 HV-141-F028C MN STM LINE D OB IS0 HV-141-F028D AND Verifies amber light NOT LIT and red light LIT for each valve.

Evaluator Inform the student the JPM is complete.

• Critical Step #C riticaI Sequence STCP-CIA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS

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A. An MSlV isolation and reactor scram occurred from 100% reactor power.

B. The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.

C. HPCl and/or RClC injection is controlling reactor water level.

D. Reactor pressure is controlled by manual SRV actuation.

E. Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.

INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.

Page 1 of 2 2003 NRC Exam Rev. 1

TASK CONDITIONS A. An MSlV isolation and reactor scram occurred from 100% reactor power.

B. The cause of the MSlV isolation was a faulty isolation logic surveillance test procedure.

C. HPCl and/or RClC injection is controlling reactor water level.

D. Reactor pressure is controlled by manual SRV actuation.

E. Restoration of normal steam loads and turbine bypass system is required for a reactor cooldown.

INITIATING CUE Perform a quick recovery from a Main Steam Line Isolation and reopen the MSIVs.

Page 2 of 2 2003 NRC Exam Rev. 1