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: 811 1-811 5 2003 11 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 I

D y S 7

b. 264000 A2.01 3.513.6 Start D/G for surveillance (1)

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)

e. 223001 A2.07 (4.W4.3)

D,S, Transfer Containment R 6

5 4

9

f. 202001 A2.10 333.9 Respond To A Reactor Recirc Pump Dual Seal Failure IAW ON-164-003 D, S, E/A, L 1

g. 209001 A2.01 3.8/3.7 Perform Manual S/U of Core Spray IAW OP-151-001 Main Steam Line Isolation and Quick Recovery in Accordance with ON-

h. 239001 A4.01 (4.W4.0) 781-007 (2) 2 3

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 I

Bypass RClC Temp or Differential Temperature Isolation signal IAW ES-150-001

• 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 2003 NRC Exam Rev. I Susquehanna Facsimile

ES-301 Control Room/ln-Plant Systems Outline Form ES-30 I

-2 Facility:

Susuuehanna Date of Examination: 8/1 I

-8/15 2003 Exam Level (circle one): SR0-I Operating Test No.:

b. 264000 A2.01 3.513.6 Start D/G for surveillance (I)

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)

RESET Recirc Pump Limiter #2 Runback in accordance with ON-164-002

c. 223001 A2.07 (4.W4.3)

d. 202002 A2.05 (3.814.0)

(2)

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

N, A9 s 0

9 s9 E s9 A System / JPM Title Perform Monthly Surveillance of 4KV Bus Undervoltage Relays

i. 295016 AA1.08 (4.014.0)

Perform manual operation of fhe SRVs Valves from the Remofe Shutdown Panel as required by ON-100-00900.0N.015.103 (3)

Type Code*

0 9

RY HA, 7

A

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

D y S

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

NS

f. 202001 A2.1 0 333.9 Respond To A Reactor Recirc Pump Dual Seal Failure IAW ON-164-003 D, S, E/A, L

g. 209001 A2.01 3.8/3.7 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)

Safety Function 7

6 5

4 9

I 2

h. 262001 K4.04 2.8/3.1

j.

271 001 A4.09 3.6/3.6 I D, E/A, C 1 4

I Bypass RClC Temp or Differential Temperature Isolation signal IAW ES-150-001

• 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 2003 NRC Exam Rev. 1 Susquehanna Facsimile

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:

Susquehanna Date of Examination: 8\\11-8/15 2003 Type Code*

I( Exam Level (circle one): SR0-U Operating Test No.:

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

c. 223601 A2.07 (4.Y4.3)

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)

System / JPM Title 0, s, E 5

e. 272000 AI.01 32/32 Transfer Containment Radiation Monitor Sample Pumps IAW OP-I 79-003 N, s 9

Perform Manual S/U of Core Spray IAW OP-151-001

g. 209001 A201 3.8/3.7 E/A, E

j. 295016 AA1.08 (4.0/4.0)

Perform manual operation of the SRVs Valves from the Remote Shutdown Panel as required by ON-1 00-00900.0N.015.103 (3)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 0, R, ffAY 7

A

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

N'R'A 1

• 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 2003 NRC Exam Rev. 1 Susquehanna Facsimile

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 78.AR.004.103 0

06/17/03 21 5005 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.

Head Date Nuclear Trng. Supv.

Date

~-<

Date of Performance:

JPM Performed By:

Student Name:

15 Allowed Time (Min.)

Time Taken (Min.)

Performance Evaluation:

Evaluator Name:

Last First

(

)

Satisfactory M. I.

0 Employee #/S.S. #

Unsatisfactory 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 I IC651 (Rev. 22)

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

C. OP-158-001 RPS System (Rev. 26) 111. REACTIVITY MAN I PULATIONS 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

Appl. To/JPM No.: S/RO 78.AR.004.103 Candidate locates procedure and refers to Step Obtains procedure AR-103-001 I

appropriate section.

/

\\

PERFORMANCE CHECKLIST and refers to Window A06.

Action EVALUATOR NOTE:

0 0

0 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.

EVALUATOR NOTE:

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

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.

AR-103-A06, AR-103-B06, AR-104-AOI, AR-BOOTH OPERATOR:

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

Student Name:

Standard

• Critical Step I

1. Critical Sequence Eva1 Comments Form STCP-QA-I25A Rev 4, (OYOO)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 78.AR.004.103 Step 2

3 4

5

• 6

(

PERFORMANCE CHECKLIST

(:

Page 4 of 5 Action Determines Probable cause.

Ensures automatic actions occurred.

Determines reactor power reduction is not necessary.

Determines D APRM is affected.

EVALUATOR NOTE:

Candidate may inform Unit Supervisor about the instrument failure before bypassing.

Bypass D APRM.

• Critical Step

1. Critical Sequence Student Name:

Standard 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.

Verifies:

Trip to Reactor Protection System channel B.

0 Rod block to Reactor Manual Control System.

Determines flow bias setpoint has not been exceeded on any of the unaffected channels.

Determine APRM channel causing the trip Verifies:

e D APRM reading 125%.

0 All other APRMs reading 100%.

Places the Division 2 APRM BYPASS joystick to the D position.

Eva1 Comments Form STCP-QA-125A Rev. 4, (05lOO)

Page 1 of 1 2003 NRC Exam Rev. 1

i' i

Appl. To/JPM No.: S/RO 78.AR.004.103 Step

• 7 8

PERFORMANCE CHECKLIST Action EVALUATOR NOTE:

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

Reset RPS trip system.

Observe alarms clear.

EVALUATOR NOTE:

This completes the JPM.

• Critical Step

1. Critical Sequence Student Name:

Page 5 of 5 Standard 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.

Verifies the following alarm is clear 0

RPS CHANNEL 61/62 AUTO SCRAM, AR-104-AOI.

Eva1 Comments 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.

Form S'CCP-QA-12SA Rev. 4, (OYOO)

Page 1 of I 2003 NRC Exam Rev. 1 Page 1 of 2

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

B. You are the PCOM.

INITIATING CUE Respond to alarm conditions.

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

Page I of 1 2003 NRC Exam Rev. 1 Page 2 of 2

1. PCAF NO. 2003--S220 FORM NDAP-QA-0002-8, Rev. 8, Page 1 of 2 (Electronic Form)

2. PAGElOF 4

3. PROC. NO. AR-103-001 REV. 22

S/RO Appl. To Task

Title:

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET

04. SO. 002.251 0

06/15/03 262001 K4.04 2.8/3.1 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

KJA 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 Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

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 I II. REACTIVITY MAN I P U LATlO NS 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

/

i:

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

Step Action EVALUATOR This JPM must be performed in plant.

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

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.

A COPY of SO-204-001.

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.

EVALUATOR Provide the candidate time to review the test procedure.

Obtains stopwatch.

Review precautions.

Standard Verifi a ithorization to commence by Shift Supervision signature with date a time completed.

Stopwatch obtained.

Precautions reviewed.

Eva1 Comments

• Critical Step

1. Critical Sequence STCP-QA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

r:

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

Step 4

5 6

7 8

Action Record plant MODE.

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

Verify Unit 2 ESS buses energized.

Document step completion.

Identify testing restrictions.

Document step completion.

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

1. Critical Sequence Standard Enters I for MODE and initials the confirm line.

Observes white light LIT on OC653 for buses:

2A201 2A203 2A202 2A204 Initials confirm space for each bus.

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

Initials confirm space.

Eva1 Comments STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

I

(

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

Step 9

10

• I 1 12 Action 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.

Inform Shift Supervision to enter TS 3.3.8.1.

Document step completion.

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

Block protection circuit.

Document step completion.

~

Standard Using plant page/radio contacts control room/Unit Supervisor to enter TS 3.3.8.1 for bus 2A201.

Initials confirm space.

Place Degraded Voltage Trip Enable Test Switch HSE-2A20102B to TRIP BLOCKED position.

Initials confirm space.

Eva1 Comments

• Critical Step

1. C ri t i ca I Seq ue n ce STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

(:

PERFORMANCE CHECKLIST

[

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

Step 13 14 15 16 17 18

• Critical Step Action Confirm 4KV BUS 2A(2A201) LO VOLTlPROT CKT TROUBLE ALARM received at panel OC653.

EVALUATOR CUE Inform candidate the alarm was received.

Document step completion.

Perform light test.

EVALUATOR CUE Inform candidate the white lights are LIT.

Document step completion.

Return test switch to normal.

J EVALUATOR CUE Inform candidate the white lights are NOT LIT.

Document step completion.

1. Critical Sequence Standard Using plant page/radio contacts Unit 2 control room to confirm the alarm was received.

Initials confirm space.

Place Degraded Voltage Ckt Test Switch HSE-2A20102A to LIGHT TEST and CONFIRM following Degraded Voltage Ckt Test Light ILLUMINATE:

0 Relay Ckt 2781/2782 0

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

Initials confirm spaces.

Place Test Switch HSE-2A20102A to Normal and CONFIRM following Test lights EXTINGUISH:

0 Relay Ckt 27B1/27B2 Relay Ckt 278312784 Verify white lights are NOT LIT.

Initials confirm spaces.

Eva1 Comments STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. TolJPM No.: S/RO 04.S0.002.251 Step "1 9

• 20 21 22 23 PERFORMANCE CHECKLIST Page 7 of 12 Student Name:

Action Test circuit and time relay drop out.

EVALUATOR CUE Inform candidate the white lights are LIT with the following times:

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

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

EVALUATOR Bus 2A201 acceptance criteria for function 2 is 1.a (65%)

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

Return test switch to normal.

EVALUATOR CUE Inform candidate the white lights are NOT LIT.

Document step completion.

Reset relay targets 27B1 through 27B4.

Document step completion.

• Critical Step

1. Critical Sequence Place Test Switch HSE-2A20102A to CIRCUIT TEST and simultaneously starts the stop watch and CONFIRM following Test lights ILLUMINATE:

Relay Ckt 27B3/27B4 (-3 0

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

Verify white lights are LIT and note times on stopwatch.

Record acceptance criteria as acceptable on the data form by circling yes and initial the confirm space for function 2 and 3.

Place Test Switch HSE-2A20102A to Normal and CONFIRM following Test lights EXTINGUISH:

Relay Ckt 27B1127B2 Relay Ckt 27B312784 Verify white lights are NOT LIT.

Initials confirm space.

Depress the reset button and verify relay target color changes from orange to clear.

Initials confirm space for each relay.

Eva1 Comments STCP-QA-1256 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i; PERFORMANCE CHECKLIST Page 8 of 12 Appl. TolJPM No.: SlRO 04.S0.002.251 Step

• 24 25 26 27 28 29 30 31 Action Enable protection circuit.

Document step completion.

Confirm 4KV BUS 2A(2A201) LO VOLT/PROT CKT TROUBLE ALARM cleared at panel OC653.

EVALUATOR CUE Inform candidate the alarm was clear.

Document step completion.

Inform Shift Supervision to clear TS 3.3.8.1.

Document step completion.

EVALUATOR Candidate will proceed to bus 2A202.

Inform Shift Supervision to enter TS 3.3.8.1.

Document step completion.

Student Name:

Standard Place Degraded Voltage Trip Enable Test Switch HSE-2A20102B to TRIP ENABLED position.

Initials confirm space.

Using plant pagelradio contacts control room to confirm the alarm cleared.

Initials confirm space.

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

Initials confirm space.

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

Initials confirm space.

Eva1 Comments

• Critical Step

1. Critical Sequence STCP-QA-125B 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 04.S0.002.251 Student Name:

Step

• 32 33 34 35 36 37 Actinn CAUTION DEGRADED GRID PROTECTION FOR ESS BUS 2A202 DISABLED DURING PERFORMANCE OF THIS SECTION.

Block protect ion circuit.

Document step completion.

Confirm 4KV BUS 2B(2A202) LO VOLTIPROT CKT TROUBLE ALARM received at panel OC653.

EVALUATOR CUE Inform candidate the alarm was received.

Document step completion.

Perform light test.

EVALUATOR CUE Inform candidate the white lights are LIT.

Document step completion.

• Critical Step

1. Critical Sequence Standard Place Degraded Voltage Trip Enable Test Switch HSE-2A20202B to TRIP BLOCKED position.

Initials confirm space.

Using plant page/radio contacts control room to confirm the alarm was received.

Initials confirm space.

Place Degraded Voltage Ckt Test Switch HSE-2A20202A to LIGHT TEST and CONFIRM following Degraded Voltage Ckt Test Light ILLUMINATE:

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

Initials confirm spaces.

Eva1 Comments STCP-QA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

i,

Appl. To/JPM No.: S/RO 04.S0.002.251 Step 38 39

• Critical Step PERFORMANCE CHECKLIST Page 10 of 12 Return test switch to normal.

EVALUATOR CUE Inform candidate the white lights are NOT LIT.

Document step completion.

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

STCP-QA-1256 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

1. Critical Sequence Student Name:

Standard Place Test Switch HSE-2A20202A to Normal and CONFIRM following Test lights EXTINGUISH:

Relay Ckt 27B1/27B2 Relay Ckt 27B3/27B4 Verify white lights are NOT LIT.

Initials confirm spaces.

Eva1 Comments

Page 11 of 12 i

PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 04.S0.002.251 Step

• 40

• Critical Step Action Test circuit and time relay drop out.

EVALUATOR CUE Inform candidate the white lights are LIT with the following times:

0 Relay Ckt 27B3/27B4 (-6 seconds)

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

EVALUATOR Candidate may inform control room about the acceptance criteria failure.

Bus 2A202 acceptance criteria for function 2 is 1.b (65%)

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

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

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

Page 1 of 1 2003 NRC Exam Rev. 1

1. Critical Sequence Student Name:

Standard Place Test Switch HSE-2A20202A to CIRCUIT TEST and simultaneously starts the stop watch and CONFIRM following Test lights ILLUMINATE:

0 Relay Ckt 27B3127B4 (-3 Relay Ckt 27B1/27B2 (-5 seconds) minutes)

Verify white lights are LIT and note times on stopwatch.

Record acceptance criteria is not acceptable on the data form by circling no and initial the confirm space for function 2.

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

Eva1 Comments

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

Step

• 4 1 42 43 44

• 45 46 47 48 Action Return test switch to normal.

EVALUATOR CUE Inform candidate the white lights are NOT LIT.

Document step completion.

Reset relay targets 27Bl-2A20202 through 27B4-2A20202.

Document step completion.

Enable protection circuit.

Document step completion.

Confirm 4KV BUS ZB(2A202) LO VOLT/PROT CKT TROUBLE ALARM cleared at panel 06653.

EVALUATOR CUE Inform candidate the alarm was clear.

Document step completion.

Standard Place Test Switch HSE-2A20202A to Normal and CONFIRM following Test lights EXTINGUISH:

Relay Ckt 27B1127B2 0

Relay Ckt 27B3/27B4 Verify white lights are NOT LIT.

Initials confirm space.

Depress the reset button and verify relay target color changes from orange to clear.

Initials confirm space for each relay.

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

Initials confirm space.

Using plant page/radio contacts control room to confirm the alarm cleared.

Initials confirm space.

Eva1 Comments

• Critical Step

1. Critical Sequence STCP-CIA-1255 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 04.S0.002.251 Step 49

• Critical Step PERFORMANCE CHECKLIST Page 13 of 12 Action Inform Shift Supervision Bus 2A202 did not meet acceptance criteria.

EVALUATOR This completes the JPM.

1. Critical Sequence Student Name:

Standard Using plant pagehadio contacts Unit 2 control roorn/Unit Supervisor and informs them bus 2A202 did not meet acceptance criteria for relays 27B3/27B4.

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.

.~

2003 NRC Exam Rev. I Page 1 of 2

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.

\\--

2003 NRC Exam Rev. I Page 2 of 2

L-S/RO Appl. To Task

Title:

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 00.ON.015.153 1

06/13/03 295016 AA1.08 4.0/4.0 JPM Number Rev. No.

Date NUREG 11 23 Sys. No.

WA 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 Date of Performance:

JPM Performed By:

25 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance

(

)

Satisfactory

(

)

Unsatisfactory Evaluation:

Evaluator Name:

Sign at u re Typed or Printed Comments:

STCP-QA-125A 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 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 I I. REACTIVITY MAN I P U LATIONS None L-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 00-009 step 4.6.

VI. TASK STANDARD Reactor C/D lowest pressure calculated 1325 psig and at least 1 SRV opened.

2003 NRC Exam Rev. I

Appl. To/JPM No.: S/RO 00.ON.015.153 Step PERFORMANCE CHECKLIST Action 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 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:

SV-12651 INSTR GAS TO CONTN ISO.

SV-12605 INSTR GAS CMP OB SUCT ISO.

EVALUATOR CUE:

Inform candidate, Red OPEN lights LIT and amber CLOSED lights NOT LIT for SV-12651 and SV-I2605 indication.

• Critical Step

1. Critical Sequence Student Name:

Standard 3btains a controlled copy ON-I 00-009, ncluding Attachments A and B.

Checks:

SV-12651 indicating lights Red light LIT.

Amber light NOT LIT.

AND SV-12605 indicating lights Red light LIT.

Amber light NOT LIT.

\\

Page 3 of 7 Eva1

~~

~

Comments STCP-QA-1250 Rev. 2. (9193) As Given Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 00.ON.015.153 Step 3

PERFORMANCE CHECKLIST Page 4 of 7 Action 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.

IF CIG Compressors tripped, Reset as follows at 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.

1 C239 (25-71 9'):

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

1. Critical Sequence STCP-PA-1256 Rev. 2. (9193) As Given Page 1 of 1 2003 NRC Exam Rev. 1 Student Name:

Standard Simulates contacting Reactor building NPO to determine the status of the CIG compressors.

Eva1 Comments

i Appl. To/JPM No.: S/RO 00.ON.015.153 Step

• 4 5

PERFORMANCE CHECKLIST Action 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:

Calculates allowable cooldown value for reactor pressure.

FAULT STATEMENT:

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

Open SRV's A, B, and C as needed.

EVALUATOR CUE:

If asked, indicate RPV pressure is still stable at 875 psig.

• Critical Step

1. Critical Sequence STCP-QA-I25B Rev. 2, (9193) As Given 2003 NRC Exam Rev. 1 Page 1 of 1 Student Name:

Standard Refers to ON-1 00-009, Attachment A to determine current reactor temperature and desired reactor pressure and temperature to achieve a 1 OO°F/hr cooldown AND Determines RPV pressure at 875 psig, reactor temperature is -530°F. Cooldown rate of 1 OO"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.

Places switches for SRVs A, B, or C to OPEN.

AND Checks for change in RPV pressure i

Page 5 of 7 Eva1 Comments

Appl. To/JPM No.: SlRO 00.ON.015.153 Step 6

(

PERFORMANCE CHECKLIST EVALUATOR CUE:

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.

Chooses alternate method of SRV operation.

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

1. Critical Sequence Student Name:

Standard Candidate determines that the valves have not opened and reports this to the SRO.

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

i Page 6 of 7 Eva1 Comments STCP-QA-1258 Rev. 2, (9193) As Given 2003 NRC Exam Rev. 1 Page 1 of 1

Appl. To/JPM No.: S/RO OO.ON.015.153 Step

• 6 7

8

• 9 f

(

i PERFORMANCE CHECKLIST Page 7 of 7 Action 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 Simulate obtaining keys for SRVs from Pink sound powered phone box, labeled JP1207, JP1402, JP2201 I.

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

Simulates establishing communication with the RSDP Room.

Simulates inserting key and rotating switch to the OPEN position.

EVALUATOR CUE:

Inform candidate red light LIT and amber light NOT LIT for each valve place to open.

• Critical Step

1. Critical Sequence Student Name:

Standard Demonstrates the ability to find keys in the pink box labeled JP1207 or JP1402.

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

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

Simulates placing any ADS keylock switch in the OPEN position.

AND Verifies Red light LIT and amber light NOT LIT.

=

Eva1 Comments STCP-QA-1258 Rev. 2, (9193) As Given 2003 NRC Exam Rev. 1 Page 1 of 1

t PERFORMANCE CHECKLIST

~

Step Action Standard Eva1 Comments EVALUATOR CUE:

Acknowledge SRV is OPEN.

OPEN This completes the JPM.

Simulates using sound-powered phone g page.

To inform SRO at the RSDP the valve indicates Appl. To/JPM No.: S/RO 00.ON.015.153 Student Name:

(

Page 8 of 7

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

1. Critical Sequence

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

L' 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.

2003 NRC Exam Rev. I Page 1 of 2

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.

2003 NRC Exam Rev. 1 Page 2 of 2

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 prova I :

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head L-.

Date of Performance:

40 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance

(

)

Satisfactory

(

)

Unsatisfactory Evaluation:

Evaluator Name:

Sign at u re Typed or Printed Comments:

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

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

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 00-1 03, Primary Containment Control.

B. EO-100-1 12, 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

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

(,

PERFORMANCE CHECKLIST Page 3 of 9 Student Name:

Step Action EVALUATOR 0

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.

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.

EVALU AT0 R To begin this JPM, provide the candidate with the Task Conditions and Initiating Cue Sheet.

Review Sections 1.O through 3.0.

Ensure that Shift Supervision has approved performance of Sections 4.6 and 4.2.

Standard Reviews all sections.

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

Notes that Shift Supervision has signed and dated the appropriate signature line.

Eva1 Comments

• Critical Step

1. Critical Sequence STCP-OA-1256 Rev. 2. (9193)

Pagelof1.

2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Page 4 of 9 (r

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

Step 3

4 5

Action Obtain required support materials.

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

Selects correct section.

Place following valve control switches to CLOSE:

STM SUPPLY IB IS0 HV-149-FO07 STM SUPPLY OB IS0 HV-149-FO08 WARM UP LINE IS0 HV-149-F088 EVALUATOR CUE After each switch is placed to CLOSE inform the candidate the amber light is LIT and the red light is NOT LIT.

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.

CAUTIO N 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.

Stand a rd Obtains required support materials from the ES box in the Shift Managers office.

Selects section 4.2.

Insert key and rotate counter clockwise to CLOSE for HV-149-007 and F008.

Place control switch to CLOSE for HV-149-FO88.

Verify amber light LIT and red light NOT LIT.

Eva1

• Critical Step

1. 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 6

7

• 8 9

• I O 11 12 Action Bypass all RClC Div 1 isolations.

EVALUATOR 1 C621 located Upper Relay Room.

Banana Jacks in this JPM have a GREEN stripe.

Locate relay, loosen relay cover screws, and remove cover.

Boot contacts 3/4.

Document step completion.

Boot contacts 9/10.

Document step completion.

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

1. Critical Sequence Standard Locate IC621, RClC RELAY PANEL DIVISION 1.

REMOVE front cover from Relay ISOLATION SIGNAL F008 CONTROL LOGIC.

E51A-KI5, RClC AUTO/MAN Referring to ATT A, INSTALL boot over 314 contact finger of Relay E51A-KI5.

SignsAnitials confirmed space and enters date.

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

Signs/initials confirmed space and enters date.

Locate Terminal Strips - AAA7 and BBB9.

Eva1

~

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

Page 1 of 1 2003 NRC Exam Rev. 1

i' PERFORMANCE CHECKLIST 4,

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

Step

• I 3

14 15 16

• I7 18

• I9 20 21 Action Install jumper.

Document step completion.

Bypass all RClC Div 2 isolations.

EVALUATOR IC618 is located in the Lower Relay Room.

Locate relay, loosen relay cover screws, and remove cover.

Boot contacts 314.

Document step completion.

Boot contacts 7/8.

Document step completion.

Locate Terminal Strip - EEE8.

• Critical Step

1. Critical Sequence Standard INSTALL a jumper between terminal points AAA7-4 and BBB9-7.

Signs/initials confirmed space and enters date.

Locate 1 C618, RHRlRClC RELAY PANEL DIV 2.

REMOVE front cover of Relay TURB EXH DIAPHRAGM HIGH PRESSURE.

E51A-K33, RClC IS0 SIGNAL Referring to ATT B, INSTALL boot over 3/4 contact finger of Relay E51 A-K33.

Signs/initials confirmed space and enters date.

Referring to ATT B, INSTALL boot over 7/8 contact finger of Relay E5 1 A-K33.

Signslinitials confirmed space and enters date.

Locate Terminal Strip - EEE8.

Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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

• 22 23 24

• 25 26

• 1. 27 PERFORMANC'E CHECKLIST Page 7 of 9 Action NOTE: Terminal Strip EEE8 is located right side, 2 feet high in rear of Panel 1C618, third door from right end of panel.

Install jumper.

Document step completion.

Locate Terminal Strips BBBG and 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.

Install jumper Document step completion.

Pressurize RClC steam line.

OPEN STM SUPPLY IB IS0 HV-149-FO07.

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

• Critical Step

1. Critical Sequence Student Name:

Standard INSTALL jumper between Terminal Points EEE8-14 and EEE8-20.

Signs/initials confirmed space and enters date.

Locate Terminal Strip -BBB6 and Terminal Strip - EEE7.

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

Signs/initials confirmed space and enters date.

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

Verify red light LIT and amber light NOT LIT.

Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i, PERFORMANCE CHECKLIST Page 8 of 9

(

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

Step

• 1. 28 29 30 Action THROTTLE OPEN STM SUPPLY OB IS0 HV-149-F008.

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

OBSERVE steam line pressure increasing.

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

THROTTLE OPEN RClC STM SUPPLY OB IS0 HV-149-F008 to pressurize RClC steam line -100 psi/min.

EVALUATOR CUE Inform the candidate that RClC Steam Line is pressurizing at a rate of -80 psi/min.

"Critical Step STCP-QA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

1. Critical Sequence Standard PLACE STM SUPPLY OB IS0 HV-149-F008 keyswitch to OPEN for four seconds.

RETURN STM SUPPLY OB IS0 HV-I 49-FO08 keyswitch to STOP position.

Verify red light and amber light LIT.

Observe STM SUP PRESS TO RClC TURBINE PI-E51-1 R602.

PLACE STM SUPPLY OB IS0 HV-149-F008 keyswitch to OPEN.

RETURN STM SUPPLY OB IS0 HV-149-F008 keyswitch to STOP position while monitoring PI-E51-1 R602 Eva1 Comments

I' Page 9 of 9 i

PERFORMANCE CHECKLIST

(,

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

Step 31 32 Action When RCIC steam line pressure within 50 psig reactor pressure as indicated on STM SUP PRESS TO RClC TURBINE PI-E51-1 R602, FULLY OPEN STM SUPPLY OB IS0 HV-149-FO08.

EVALUATOR CUE Inform candidate that pressures are within 50 psig of each other.

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

Confirms RClC Steam Lines are drained.

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

EVALUATOR This completes the JPM.

Standard Compares any reactor pressure indication to PI-E51-1 R602.

PLACE STM SUPPLY OB IS0 HV-149-F008 keyswitch to OPEN.

Verify red light LIT and amber light is NOT LIT.

Observes Annunciator AR-108-BO4 is CLEAR.

Check STEAM LINE DRN POT BYPS LV-149-FO54 is CLOSED.

Verify amber light LIT and red light NOT LIT.

Eva1 Comments

• Critical Step

1. 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 00-1 03, 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.

2003 NRC Exam Rev. 1 Page 1 of 2

c-TASK CONDITIONS A.

B.

C.

D.

E.

F.

An accident condition exists and Shift Supervision has determined that it is necessary to rapidly depressurize the RPV as required by EO-100-1 03, Primary Containment Control.

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

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.

A steam leak does not exist.

RClC is needed for support of reactor depressurization.

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--

2003 NRC Exam Rev. 1 Page 2 of 2

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 D from Panel OC653 in Accordance With OP-024-001 Completed By:

Reviews:

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

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Head Date Date 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.

1.

SAFETY CONSIDERATIONS i

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.

C. OP-030-002, Control Structure HVAC OP-024-005, Diesel Generator Start Log (SPS 01-024-002)

D. AR-015-001, 13.8/4 KV SWITCHGEAR DISTRIBUTION AND DIESEL GENERATORS A, B, & C LA-0521 -004, DIESEL GENERATOR D OC521 OC653 E.

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

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

A.

B.

C.

D.

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

The Technical Specification Surveillance is not to be performed.

The ESW System is in service.

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

Appl. To/JPM No.: S/RO New DG Surveillance Provide copy of D/G Start Log OP-024-005.

~~

Step

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

PERFORMANCt CHECKLIST Action EVALUATOR NOTE:

Student Name:

Standard 0

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 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.

Candidate is given the procedure as part of turnover and is referred to appropriate section.

Reviews prerequisites.

Given procedure

\\

OP-024-001, Diesel Generator 3.2.

\\

Reviews prerequisites Page 3 of 9 Comments

• Critical Step

1. Critical Sequence 2003 NRC Exam Rev. 1 Form STCP-QA-1ZM Rev. 4, (05/00)

Page 1 of 1

Appl. TolJPM No.: S/RO New DG Surveillance Step 3

(

4 i:

PERFORMANCE CHECKLIST Action 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 Obtains a stop watch.

6iiZGz-r Inform the student that all prerequisites have been met.

I OH NOTE:

All alarms on AR015, Columns IO, 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.

Station an operator at the Diesel to be started.

BOOTH CUE:

Roleplay NPO

• Critical Step

1. Critical Sequence 2003 NRC Exam Rev. 1 Form STCP-QA-125A Rev. 4, (05/00)

Page 1 of 1 Student Name:

Standard Obtains a Control Room timer or another stopwatch.

\\

Follows precautions as applicable.

Dispatches a NPO to the appropriate diesel generator and explains how the timing of the Diesel Generator start will be coordinated..

Eva1 I' ',

Page 4 of 9 Comments

i PERFORMANCE CHECKLIST I

1 Page 5 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Step Action Ensure that the ESW System is in service.

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.

Remove Access Control and Lab Supply System from service.

Ensure that there is no intercooler leakage.

EVALUATOR CUE:

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

Check for proper DG operation mode.

• Critical Step 2003 NRC Exam Rev. 1 Form STCP-QA-125A Rev. 4, (05100)

Page 1 of 1

1. Critical Sequence Student Name:

Standard The student may check the ESW pump running indicator lights on Panel OC653 or refer to the Task Conditions/lnitiating Cue Sheet.

Directs NPO to place air manifold temperature control in automatic.

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

Directs the NPO to verify that intake manifold drains have no discharge.

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 Eva1 Comments

PERFORMANCt CHECKLIST

(<:

Page 6 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Step 10 I 1 12 13 14 15 Action Prelube DG ID Turbocharger. NPO performs turbocharger prelube.

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 prelu be has been completed.

Ensure that the DG is ready to run.

EVALUATOR CUE:

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

Ensure that the NPO performs the appropriate DG checks as the diesel is started.

Start the DG.

Student Name:

Standard Directs the NPO to perform the turbocharger prelube per the appropriate section of OP-024-001.

Checks that the Ready to Run Light is illuminated.

Notifies NPO that the diesel is about to be started and to perform the appropriate steps of OP-024-001 when the diesel begins cranking.

Depresses DG D start HS-00051 D pushbutton.

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

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

Eva1 Comments

• Critical Step

1. Critical Sequence 2003 NRC Exam Rev. 1 Form STCP-QA-12M Rev. 4, (05/00)

Page 1 of 1

Appl. To/JPM No.: S/RO New DG Surveillance Step 16 17 PERFORMANC t CHECKLIST Page 7 of 9 Action Log the DG start time.

EVALUATOR CUE:

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

are just slightly less than the time that he has 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.

DG A PANEL OC521 D LO PRIORITY TROUBLE received (AR-016-C03)

BOOTH OPERATOR Wait one minute and report that local alarm is Standpipe High Level Alarm

• Critical Step 2003 NRC Exam Rev. 1 Form STCP-QA-125A Rev. 4. (05100)

Page 1 of 1

1. Critical Sequence Student Name:

Standard Notes the DG start time Completes the Diesel Generator StaG Log.

AND DISPATCH Operator to perform LA-0521 -004 Diesel Generator D OC521 D 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)

Repeat back high level alarm due to Standpipe high level.

Eva1 3

3e Comments

PERFORMANCE CHECKLIST i

Page 8 of 9 Appl. To/JPM No.: S/RO New DG Surveillance Step 18

• I 9 Action Faulted Step - D DIG svnc switch to ON, G enerator 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 OC521 D LO PRIORITY TROUBLE (C03) Alarm response: &&

01 6-C03 Take manual control of Voltage regulator switch and run it down for a second.

Ramp the Volt meter toward 2700 volts Respond to:

DG D PANEL 0 0 1 D LO PRIORITY TROUBLE (C03) Alarm response: AR-016-C03 Review AR-016-C03 p

Student Name:

Standard DISPATCH Operator to perform LA-0521 -004 Diesel Generator D OC521 D 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)

Eva1 I.

Comments

• Critical Step

1. Critical Sequence 2003 NRC Exam Rev. 1 Form STCP-QA-1ZM Rev. 4, (OYOO)

Page 1 of 1

Appl. To/JPM No.: S/RO New DG Surveillance Step

• 20 21 PERFORMANCE CHECKLIST Action Monitor Voltage DIG meter: OX100035D for change in voltage BOOTH OPERATOR Role play NPO and acknowledge the request.

Depress PB#2 IOR QDISESD STOP (Trips D/G locally)

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

Role play NPO and report D/G tripped.

Verifies DG secured EVALUATOR NOTE:

This completes the JPM.

• Critical Step 2003 NRC Exam Rev. 1 Form STCP-QA-125A Rev. 4, (OSIOO)

Page 1 of 1

1. Critical Sequence Student Name:

Standard Checks:

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

Repeat back D/G tripped.

Verify D/G tripped alarms Verify Voltage indication zero Verify D/G speed decreasing by observing Hz meter.

Contacts NPO to ensure DG is shutdown.

Eva1 i'

Page 9 of 9 Comments

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.

Form STCP-QA-125A Rev. 4, (0300)

Page 1 of 1 2003 NRC Exam Rev. I Page 1 of 2

TASK CONDITIONS The Plant is in Condition 1.

c 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

S/RO Appl. To Task

Title:

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET 73.E0.001.101 2

06/17/03 223001 A2.07 4.2/4.2 JPM Number Rev. No.

Date NUREG 1123 Sys. No.

WA 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 Date of Performance:

JPM Performed By:

20 Allowed Time (Min.)

Time Taken (Min.)

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

S ig nature Typed or Printed Comments:

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

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

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 73.E0.001.IO1 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-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, E. In Step G. SGTS is operating per 4.2, is completed by the US up to and including step 4.2.4.b(1)

Noble Gas samplea-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

Appl. To/JPM No.: S/RO 73.E0.003.101

(<

PERFORMANCE CHECKLIST Action 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.

Notes Shift Manager approval to perform Step 4.2 (page 2 of 23).

Obtain the required equipment.

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

1. C ri t ica I Seq uence Student Name:

Stand a rd Review all sections.

Follows all precautions as applicable.

Observes Shift Manager signature, date, and time in the appropriate location (to perform section 4.2) in Section 4.1 of the procedure.

Obtains two (2) keys.

Eva1 Page 3 of 6 Comments 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 Step

• 4

• 5

• 6 Action 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.

Over-ride 45 minute time delay Div 1.

Over-ride 45 minute time delay Div 2.

EVALUATOR:

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

At Panel IC681 line up vent path.

• Critical Step

1. Critical Sequence Student Name:

Standard 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.

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.

Determines step 4.2.4.d is not applicable.

Open DrwlNVetwell Burp Dmp HD-17508A.

Places Control Switch for HD-I 7508A to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT Eva1 Comments STCP-QA-1258 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

f '~

Appl. To/JPM No.: S/RO 73.E0.003.101 Step

• 7

• 8

• 9 10

=

(

PERFORMANCE CHECKLIST Action At Panel IC681 line up vent path.

At Panel IC601 line up vent path.

At Panel IC601 line up vent path.

Verify vent path complete.

• Critical Step

1. Critical Sequence Student Name:

Standard Open Drwl/Wetwell Burp Dmp HD-175088.

Places Control Switch for HD-17508B to OPEN AND Verifies RED Light LIT, AMBER Light NOT LIT 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 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 MONITOR Suppression Chamber pressure on CONTAINMENT PRESSURE PR-l571OA(B).

Eva1 Page 5 of 6 Comments STCP-QA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(<

PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 73.E0.003.101 Step 11 Action Monitor Radiation release rates.

EVALUATOR:

This completes the JPM.

• Critical Step

1. Critical Sequence Student Name:

Page 6 of 6 Standard 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.

Eva1 Comments STCP-QA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS A.

B.

C.

D.

E.

F.

G.

A small break LOCA has occurred.

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

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

4.2, is completed by the US up to and including step obtained a Suppression Chamber Noble Gas 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)

E. In Step 4.2.1.

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

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

F.

SGTS SPIN T is operable.

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-1 64-002 Completed By:

Reviews:

Russ Halm 06/17/03 Writer Date InstructorNVriter Ap p rova I:

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Head Date Date Date of Performance:

20 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S.

Performance Evaluation:

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

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

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

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)

II I. REACTIVITY MAN I P U LATlO NS 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

Appl. To/JPM No.: S/RO 64.0P.004.153 Step 1

2 3

4 5

PERFORMANCE CHECKLIST

(\\

Page 3 of 13 Action 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.

Obtain a controlled copy of ON-164-002, Loss Of Reactor Recirculation Flow.

Record date and time of event.

Selects the correct section to perform.

Plot position on Power/Flow Map.

Perform appropriate action specified on Power/Flow Map.

• Critical Step

1. Critical Sequence Student Name:

Standard Controlled copy obtained.

Records date and time of event.

Selects section 3.4.

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.

Perform appropriate action specified on Power/Flow Map.

Determines NO action required for current region.

Eva1 Comments STCP-QA-1256 Rev. 2 (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 64.0P.004.153 Step 6

7 PERFORMANCE CHECKLIST Page 4 of 13 Action Placemode switch to SHUTDOWN if operating in any of these power/flow map conditions.

Determine which limiter initiated runback.

• Critical Step

1. Critical Sequence Student Name:

Stand a rd IF Power/Flow Map indicates 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.

Limiter #I (30%) limiting by Green light ILLUMINATED above Rx RECIRC LIMITER #I RUNBK pus hbutton.

RESET HS-B31-I S15A(B)

Verifies:

Green lights NOT LIT.

Limiter #2 (45%) limiting by Green light ILLUMINATED above LOSS 831-1 S12A(B) pushbutton.

OF FW PP RUNBK RESET HS-Verifies:

Green lights LIT.

Eva1

=

Comments STCP-QA-lZSB Rev. 2 (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

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

. 8 9

i' PERFORMANCE CHECKLIST

{

Page 5 of 13 Action Ensure both pumps have run back to value associated with controlling limiter.

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

Monitor neutron instrumentation for indication of core instability.

IF required, Perform ON-1 78-002, Core Flux Oscillations.

• Critical Step

1. Critical Sequence Student Name:

~~~

Standard For RRP A verifies:

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 R621 B is

-45%

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

-45% on XI-140328.

Select a Control Rod and monitors for LPRM/APRM oscillations and determines they are not unstable.

ON-178-002 is NOT required.

Eva1 Comments STCP-QA-125B Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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

Step I O 11 12 Action Power reduction will further reduce amount of feedwater heating which will cause reactor power to increase.

Continue Monitoring position on Power/Flow map.

Monitor changes in radiation levels.

Evaluator:

If questioned about Rad Monitor readings, inform candidate that the radiation level were at their 100% reactor power values and have now lowered and stabilized at the values indicated.

IF Main Steam Line Radiation Monitor or Offgas Pretreatment Log Radiation Monitor increases, Direct Chemistry to sample per CH-ON-003.

• Critical Step Standard Plot position on Power/Flow map for changes in reactor power or core flow.

On 1 C600, Monitor the following:

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

Offgas Pretreatment Log Radiation Monitor, RR-Dl2-I R601.

Determines values are NORMAL for this power level.

Determines Chemistry notification is NOT required.

1. Critical Sequence Eva1 i"

~

~~~

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

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: SIR0 64.0P.004.153 Step 13 14 15

• Critical Step PERFORMANCE CHECKLIST Page 7 of 13 Action Monitors parameters for new power level.

Determine signal that initiated runback.

Evaluator:

CWP I D trip was given in initial conditions.

Ensure recirc speed controllers are in manual.

1. C ri t ica I Seq uence Student Name:

Standard 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.

Determines:

Limiter #2 (45%) runback initiated by Circulating Water Pump 1 D protective trip.

Ensure REACTOR RECIRC PUMP IN MANUAL.

A(B) SPEEDS SY-B31-1 R621A(B)

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

Reactor Recirc Pump A SY-B31-1 R621A Reactor Recirc Pump B SY-B31-1 R621 B Eva1 Comments STCP-QA-1258 Rev. 2 (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 64.0P.004.153 Step PERFORMANCE CHECKLIST Page 8 of 13 Action 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 STCP-QA-1258 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

1. Critical Sequence Student Name:

Standard Eva1 Comments

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

• 16A

• I 7A 18A PERFORMANCE CHECKLIST

(

Page 9 of 13 Action Establish speed control for RRP A.

SIMULATOR OPERATOR:

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

Candidate may observe loop flow to confirm control.

Reset limiter #2 runback for RRP A.

Monitor GEN 1A speed.

• Critical Step

1. Critical Sequence Student Name:

Standard For Limiter #2 runback Perform following for one or both pumps as required:

To prevent pump speed from changing when Limiter #2 reset, Ensure GEN 1A DEMAND adjusted such that GEN I A SPEED decreases when controller DEMAND is decreased.

For RRP A:

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

Depress LOSS OF FW PP RUNBK pushbutton.

RESET HS-B31-1S12A Monitor GEN 1A SPEED SI-14032A.

Determines speed is stable.

Eva1 Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i Appl. To/JPM No.: S/RO 64.0P.004.153 Step 19A 20A

• Critical Step PERFORMANCE CHECKLIST Page 10 of 13 Action If RRP A speed increases rapidly, lock scoop tube.

Verify RRP A limiter #2 is reset by light indication.

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.

1. Critical Sequence Student Name:

Standard speed increases rapidly, Trip scoop tube on affected generator by depressing SCOOP TUBE A TRIP pushbutton.

LOCK OR RESET HS-631-1 S30A Determines speed is not increasing rapidly and locking scoop tube is NOT required.

Observe Green light above LOSS 831-lSl2A pushbutton EXTINGUISHED.

OF FW PP RUNBK RESET HS-Verifies:

Green light NOT LIT.

Eva1

=

Comments STCP-(24-1258 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

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

• 16B

• I 7B 18B Page 11 of 13 i

PERFORMANCE CHECKLIST Action Establish speed control for RRP B.

SIMULATOR OPERATOR:

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

Candidate may observe loop flow to confirm control.

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

Reset limiter #2 runback for RRP B.

Monitor GEN 1 B speed.

• Critical Step

1. Critical Sequence STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1 Student Name:

Standard To prevent pump speed from changing when Limiter #2 reset, Ensure GEN 1B DEMAND adjusted such that GEN 1B SPEED decreases when controller DEMAND is decreased.

For RRP B:

Depresses the DEC pushbutton on Reactor Recirc Pump B SY-B31-I R621 B controller until Gen 1 B Demand XI-14032B and Gen 1 B Speed SI-14032B start to decrease.

Depress LOSS OF FW PP RUNBK pushbutton.

RESET HS-B31-I S12B Monitor GEN 1 B SPEED SI-140328.

Determines RRP B speed is increasing.

Eva1 Comments

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

• 19B 208

• Critical Step PERFORMANCE CHECKLIST Page 12 of 13 Action If RRP B speed increases rapidly, lock scoop tube.

Verify RRP B limiter #2 is reset by light indication.

1. Critical Sequence Student Name:

Stand a rd IF speed increases rapidly, Trip scoop tube on affected generator by depressing SCOOP TUBE B TRIP pushbutton.

LOCK OR RESET HS-B31-1 S03B Depresses the SCOOP TUBE B TRIP pushbutton.

LOCK OR RESET HS-B31-I S03B AND Verifies annunciator AR-I 02-D05, RECIRC MG B SCOOP TUBE DRIVE LOCK is LIT.

Observe Green light above LOSS B31-1 S12B pushbutton EXTl N G U ISH ED.

OF FW PP RUNBK RESET HS-Verifies:

Green light NOT LIT.

Eva1

~

Comments STCP-QA-1256 Rev. 2 (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 64.0P.004.153 Step 21 i'

PERFORMANCE CHECKLIST Action Check annunciator status.

Page 13 of 13

• Critical Step

1. Critical Sequence Student Name:

Standard Check RECIRC A(B) FLOW LIMIT RUNBACK annunciator CLEARED.

Verifies annunciator SLOW FLASH for :

LIMIT RUNBACK.

AR-102-CO1 RECIRC A FLOW AND AR-102-C04 RECIRC B FLOW LIMIT RUNBACK Eva1 Comments 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.

2003 NRC Exam Rev. 1 Page 1 of 2

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 1 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 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

0611 7/03 272000 A I.Ol 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 Date of Performance:

I O Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #lS.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory 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 I P262A2 is running and I P262A1 is in stand by.

\\-

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

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

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

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

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 79.0P.006.101 Step 1

2

• 3 PERFORMANCE CHECKLIST Action 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.

Candidate locates procedure and refers to appropriate section.

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.

Brings up base menu screen.

• Critical Step

1. Critical Sequence Student Name:

~~

Standard Obtains procedure OP-I 79-003 Containment Radiation Monitoring System and refers to section 3.3.

Reviews prerequisites and precautions.

Presses # 0 on CRM A Air Sample Rad Monitor keypad.

Verifies:

screen change Eva1 Page 3 of 4

~~~

Comments Form STCP-QA-12SA Rev. 4, (OYOO) page I of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 79.0P.006.101 Step

• 4

• 5 6

7 8

9 10 i

\\

PERFORMANCE CHECKLIST

~

Action Brings up System controls screen.

Start Containment Radiation Monitor Sample Pump I P262A1.

Observe control status block clear for pump

2.

Observe control status block OFF for pump

2.

Observe control status block LIT for pump 1.

Observe control status block OFF Brings up base menu screen.

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

Page 1 of 1 2003 NRC Exam Rev. 1

1. Critical Sequence Student Name:

~ _ _ _ _ _

Standard Presses # I System Controls on CRM A Air Sample Rad Monitor keypad.

Verifies:

screen change Presses # 3 Pump 1 Control on CRM A Air Sample Rad Monitor keypad.

Verifies small block next to pump 2 is clear.

Verifies control status block OFF is LIT Verifies small block next to pump 1 is LIT.

Verifies control status block OFF.

Presses # 0 Exit on CRM A Air Sample Rad Monitor keypad.

Verifies:

screen change i

Page 4 of 4

~

Com men ts

i Appl. To/JPM No.: S/RO 79.0P.006.101 Step I 1 12 13 PERFORMANCE CHECKLIST Action Brings up Display current data screen.

Brings up System controls screen.

Observe a flowrate of - 1 SCFM.

EVALUATOR NOTE:

This completes the JPM.

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

Page I of 1 2003 NRC Exam Rev. 1 Student Name:

Stand a rd Page 5 of 4 Presses # 3 Display Current Data on CRM A

Air Sample Rad Monitor keypad.

Verifies:

screen change Presses # 3 System on CRM A Air Sample Rad Monitor keypad.

Verifies:

screen change Verifies:

Sample Flowrate - 1 SCFM.

Eva1 I Comments

1. Critical Sequence

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

Page I of 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 1 P262A2 is running and 1 P262A1 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 1 P262A2 to 1 P262Al.

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

Page 1 of I 2003 NRC Exam Rev. 1 Page 2 of 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET S/RO 64.ON.005.101 2

0611 7/03 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-1 64-003 Completed By:

Reviews:

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

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

20 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory 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 A

Reactor Recirculation Pump shutdown and isolated.

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

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 64.0N.005.101 Step

(

PERFORMANCE CHECKLIST Action 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.

Candidate locates procedure and refers to appropriate section.

Has Unit Supervisor record the date and time.

EVALUATOR CUE:

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

"Critical Step

1. Critical Sequence Student Name:

~

Standard Checks RECIRC PP A and B SEAL CAVITY 2 pressure indicators PI-B31-1 R602A and B.

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

Determines that 'A RRP has the dual seal failure.

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

Identifies Shift Supervision must sign to authorize implementation.

Eva1

(

Page 3 of 9 Comments STCP-QA-1258 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 64.0N.005.101 Step Action

(

PERFORMANCE CHECKLIST Page 4 of 9 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.

EVALUATOR CUE:

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

Check drywell pressure rate of increase EVALUATOR CUE:

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.

• Critical Step

1. Critical Sequence Student Name:

Standard Informs supervisor that RCS leak rate check should be performed.

(SO-100-006 attachments E and F)

AND Requests direction for procedure completion.

Checks any drywell pressure indicator and determines drywell pressure is NOT increasing rapidly.

Selects Section 3.4.

Eva1 Comments STCP-QA-12%

Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 64.0N.005.101 Step 7

• 8

• 9 i

PERFORMANCE CHECKLIST Action Checks if power reduction is 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.

Reduce 1A RRP speed to 30%.

Shutdown 1A RRP.

• Critical Step

1. Critical Sequence Student Name:

Standard 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.

Depresses DEC pushbutton on REACTOR B31-1R621A until GEN I A SPEED SI-14032A DECREASES to 30%.

RECIRC PUMP A SPEED CONTROLLER SY-Depresses STOP pushbutton on MG SET A DRV MTR BKR HS-14001A.

Eva1

(

Page 5 of 9 Comments STCP-QA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i Appl. To/JPM No.: S/RO 64.0N.005.101 Step I O I 1 PERFORMANCE CHECKLIST Action Determine actual core flow.

Verify 1A RRP stops.

• Critical Step

1. Critical Sequence Student Name:

~~

Standard Determines position on power to flow map:

0 0

0 0

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

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

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

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

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

Determines position is below the 70% rod line.

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

After -20 seconds GENERATOR 1A FIELD BREAKER Amber light LIT Red light NOT LIT Eva1

(\\

Page 6 of 9

~

Comments STCP-CIA-1256 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 64.0N.005.101 Step 12 13

1. • I4

('

PERFORMANCE CHECKLIST Page 7 of 9 Student Name:

Action Comply with COLR.

EVALUATOR CUE:

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

Comply with Tech Spec LCOs 3.4.1.

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 (60-1 20 seconds).

Close suction valve.

• Critical Step

1. Critical Sequence Standard Candidate informs Unit Supervisor of the need to reference section 8 of the COLR for compliance.

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

Depresses Close pushbutton on RECIRC PUMP A SUCT HV-143-FO23A.

Verifies Amber light LIT Red light NOT LIT Eva1 i:-

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

Page 1 of 1 2003 NRC Exam Rev. 1

i i

PERFORMANCE CHECKLIST Appl. To/JPM No.: S/RO 64.0N.005.101 Step

1. • I 5

1. I 6

1. • I 7

1. • I 8 Action Close RWCU suction from loop A.

Place bypass switch to TEST.

Close discharge valve.

Close discharge bypass.

• Critical Step

1. Critical Sequence STCP-QA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1 Student Name:

Page 8 of 9 Standard Depresses Close pushbutton on RWCU SUCT LOOP A HV-144-F100.

Verifies Amber light LIT Red light NOT LIT 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 Alarm AR-I 02-102 RECIRC LOOP A DISCHARGE VALVES IN TEST actuated VALVES IN TEST - LIT Depresses Close pushbutton on RECIRC PUMP A DSCH HV-143-FO31A.

Verifies Amber light LIT Red light NOT LIT Depresses Close pushbutton on RECIRC PUMP A DSCH BYPS HV-143-FO32A.

Verifies Amber light LIT Red light NOT LIT Eva1 Com men ts

. Appl. TolJPM No.: SlRO 64.0N.005.101 Step 19

• 20 PERFORMANCE CHECKLIST Action After 2 minutes Return bypass switch to NORM.

Close CRD water supply.

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 1 RRP A IS0 143F008A is closed.

EVALUATOR NOTE:

This completes the JPM.

• Critical Step

1. Critical Sequence Student Name:

Standard After 2 minutes Places RECIRC A MOV OL BYPS HV-143-F031A switch to NORM position.

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

Eva1 Page 9 of 9 Comments 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 of 1 2003 NRC Exam Rev. 1

TASK CONDITIONS A. The plant is in Mode I 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 2 of 2 STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

\\

~

C' PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 51.OP.002.152 I

0611 7/03 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 0611 7/03 Writer Date InstructorNVriter Date Approval:

Requesting Supv./C.A.

Date Head Nuclear Trng. Supv.

Date L

20 Date of Performance:

Allowed Time (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Time Taken (Min.)

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)

I I I. 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

Appl. To/JPM No.: S/RO 51.OP.002.152 Step 1

2

• 3 PERFORMANCE CHECKLIST Action 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.

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

0 Locates procedure and refers to appropriate section.

Reviews prerequisites and precautions.

Initiate A Loop of Core Spray.

EVALUATOR The following annunciator alarms, AR-109-A01 (Core Spray Loop A Initiation Switch Armed).

• Critical Step

1. Critical Seq uence FormSTCP-QA-12SA Rev. 4, (OYOO)

Page I of 1 2003 NRC Exam Rev. 1 Student Name:

Standard Obtains procedure OP-151-001 Core Spray System and refers to section 3.3.

Reviews prerequisites and precautions.

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 A Man lnit Switch Armed, annunciator alarms.

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

Verifies CORE SPRAY LOOP A ACTUATED alarm LIT.

Eva1

(

i,,

Page 3 of 8 Comments

i Appl. To/JPM No.: S/RO 51.OP.002.152 Step PERFORMANCE CHECKLIST Adinn EVALUATOR NOTE:

In an effort to initiate both loo~s of core spray as quickly as possible, the candidate may elect to initiate loop B spray by performing steps 7-1 3 of this JPM before completing steps 4-6. This is acceptable.

Observe response of other systems to initiation of core spray.

Observe core spray system response.

Critical Step Form STCP-QA-l2JA Rev. 4, (OYOO)

Page I of I 2003 NRC Exam Rev. I Page 4 of 8 Student Name:

Standard Verifies:

DG A started by observing DG voltage A

DW unit cooler fans running in FAST trip Red high speed fast light-NOT LIT Verifies:

1 P206A and C running.

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

Amber light NOT LIT Red light LIT

1. Critical Sequence Eva1 Comments

Appl. To/JPM No.: S/RO 51.0P.002.152 Step 6

i PERFORMANCE CHECKLIST Action CAUTION AVOID POTENTIAL PUMP/MOTOR DAMAGE, 152F005A(B) MUST BE THROTTLED AS NECESSARY TO PREVENT EXCEEDING MAXIMUM PUMP RUN OUT CURRENT OF 90 AMPS PER PUMP.

CORE SPRAY LOOP A(B) INJ SHUTOFF HV-Verifies injection flowrate.

Student Name:

Page 5 of 8 Standard 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 Observes flowrate on FI-E21-1 R601A.

Eva1 Comments

• Critical Step

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

Page I of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.: S/RO 51.OP.002.152 Step PERFORMANCE CHECKLIST Action FAULT STATEMENT LOOP B CORE SPRAY FAILS TO INITIATE WHEN THE MANUAL PUSHBUTTON IS ARMED AND DEPRESSED.

Initiate B Loop of Core Spray.

EVALU AT0 R The followina annunciator alarms. ARI 13-A01 (Core SprafLoop B Initiation Switch Armed).

EVALUATOR CUE As Unit Supervisor acknowledge notification of division 2 Core Spray initiation failure.

Transitions to appropriate section of the procedure.

EVALUATOR NOTE:

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

Student Name:

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

Notes that AR-113-AOI, Core Spray Loop B 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.

Informs Unit Supervisor division 2 manual initiation has failed.

Notes Manual Startup required for B Loop Core Spray.

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

Eva1

(

Page 6 of 8 Comments

• Critical Step

1. C ri tica I 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 Step

• 9 10

• I 1

• I 2

13 Action Start Core Spray Pumps B and D.

Open or check open OB INJ SHUTOFF HV-152-FO04B.

When Reactor pressure 5436 psig, place LO RX PRESS PERM Switch HS-152-15249B to BYPASS.

THROTTLE OPEN CORE SPRAY LOOP " B IB INJ SHUTOFF HV-152-FO05B to establish loop flow 56,350 gpm for two-pump operation.

Verifies injection flowrate.

EVALUATOR When HS for HV-152-FO05 B taken to OPEN position; red light on.

When CS system flow 2635 gpm F031 B; amber light on.

• Critical Step Page I of 1 2003 NRC Exam Rev. 1 Form STCP-QA-IZSA Rev. 4, (OYOO)

1. Critical Sequence Student Name:

Standard Place the HS for 1 P206B and D to the START position.

Verifies:

Amber lights NOT LIT; Red lights LIT Verifies that HV-I 52-FO04B open.

Amber light NOT LIT Red light LIT When Reactor pressure 2436 psig, removes cover and places HS-15249B to BYPASS.

Throttles open HV-I 52-FO05B Observes flowrate on FI-E21-1 R601 B.

Verifies MIN FLOW HV-152-F031 B closes by Checking Amber light LIT Red light NOT LIT Eva1 Com men ts

Appl. To/JPM No.: S/RO 51.OP.002.152 Step 14 PERFORMANCE CHECKLIST

(

Page 8 of 8 Action Check CS room coolers B/D AUTO starts.

EVALUATOR NOTE:

This completes the JPM.

• Critical Step Page I of 1 2003 NRC Exam Rev. 1 Form STCP-QA-IZSA Rev 4, (05/00)

1. Critical Sequence Student Name:

Standard Check CS Unit Coolers 1V211 B and D AUTO START as indicated on 1 C681.

Verifies:

Red light LIT Amber and white lights NOT LIT Eva1 Comments

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 A. The Core Spray System is aligned for automatic initiation in accordance with L

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-1 84-001 Completed By:

Reviews:

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

Requesting Supv./C.A.

Date Nuclear Trng. Supv.

Head Date Date Date of Performance:

50 Allowed Time (Min.)

Time Taken (Min.)

JPM Performed By:

Student Name:

Last First M.I.

Employee #/S.S. #

Performance Evaluation:

(

)

Satisfactory

(

)

Unsatisfactory Evaluator Name:

Signature Typed or Printed Comments:

L-'

STCP-QA-12%

Rev. 2. (9193)

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

\\-

I.

II.

111.

IV.

V.

REQUIRED TASK INFORMATION JOB PERFORMANCE MEASURE S/RO 84.0N.003.101 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.

REFERENCES A. ON-184-001 MAIN STEAM LINE ISOLATION AND QUICK RECOVERY (Rev. 6 )

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

None 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.

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

Appl. To/JPM No.:

S/RO 84.0N.003.101 Step 1

2

• 3 PERFORMANCE CHECKLIST Action 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.

Obtain a controlled copy of ON-184-001.

RECORD date and time of this event.

PLACE control switches for following to CLOSE:

0 0

0 Mn Stm Line A IB Is0 HV-141-FO22A Mn Stm Line B IB Is0 HV-141-FO22B Mn Stm Line C IB Is0 HV-141-FO22C Mn Stm Line D IB Is0 HV-141-FO22D Mn Stm Line A OB Is0 HV-141-FO28A Mn Stm Line B OB Is0 HV-141-FO28B Mn Stm Line C OB Is0 HV-141-FO28C Mn Stm Line D OB Is0 HV-141-FO28D i

Page 3 of 12 Student Name:

Standard Obtains Control copy of ON-184-001, Places the control switch to CLOSE for the following:

F022A F022B F022C F022D F028A F028B F028C F028D MN STM LINE A IB IS0 HV-141-MN STM LINE B IB IS0 HV-141-MN STM LINE C IB IS0 HV-141-MN STM LINE D IB IS0 HV-141-MN STM LINE A OB IS0 HV-141-MN STM LINE B OB IS0 HV-141-MN STM LINE C OB IS0 HV-141-MN STM LINE D OB IS0 HV-141-Eva1 Comments

• Critical Step

1. 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 4

5 6

7 Action ENSURE Mn Stm Line IB Drain HV-141-F016 CLOSED.

ENSURE Mn Stm Line OB Drain HV-141-F019 CLOSED.

ENSURE Mn Stm Line Drain to Cdsr HV-141-F021 CLOSED.

ENSURE following TRIPPED:

0 Main Turbine Reactor Feed Pump Turbine A 0

Reactor Feed Pump Turbine B Reactor Feed Pump Turbine C

• Critical Step

1. Critical Sequence Standard Checks amber light LIT and red light NOT LIT for:

MN STM LINE IB DRAIN HV-141-F016 Checks amber light LIT and red light NOT LIT for:

MN STM LINE OB DRAIN HV-141-FO19 Checks amber light LIT and red light NOT LIT for:

0 MN STM LINE IB DRAIN TO CDSR HV-1 4 1 -F021 For the 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 Amber light is LIT and red light above the Trip & Reset switch NOT LIT Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

('

PERFORMANCE CHECKLIST Appl. TolJPM No.:

S/RO 84.0N.003.101 i'

\\,

Page 5 of 12 Student Name:

Step 8

9 10 Action If isolation due to EHC System malfunction:

0 DEPRESS standby EHC Hyd Fluid Pump 1 P I 13B(A) STOP push button.

0 DEPRESS operating EHC Hyd Fluid Pump I

P I 13A(B) STOP push button.

0 ENSURE Turbine main stop valves CLOSED.

ENSURE Turbine bypass valves CLOSED.

CLOSE following by depressing Drip Leg Drn HS-I 01 12 AUTO push button:

0 Drip Leg Drn HV-10112A1.

0 Drip Leg Drn HV-I 01 1281.

Drip Leg Drn HV-10112C1.

0 Drip Leg Drn HV-lOll2Dl.

CLOSE BPV Hdr Drip Leg Drn Byps HV-10108A by depressing HS-I 0108A AUTO push button.

• Critical Step

1. Critical Sequence Standard Determines the isolation was not due to an EHC system malfunction.

(Based on initial conditions)

Depresses the AUTO pushbutton on Checks white light LIT and red light NOT LIT.

DRIP LEG DRN HS-10112.

Checks amber light LIT and red light NOT LIT for :

DRIP LEG DRAIN HV-10112A1 DRIP LEG DRAIN HV-10112B1 DRIP LEG DRAIN HV-10112C1 DRIP LEG DRAIN HV-10112D1 Depresses the AUTO pushbutton on HS-10108A to CLOSE HV-1 01 08A.

AND Verifies the white light is LIT and the red light is NOT LIT.

Eva1 Comments STCP-QA-1258 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

i PERFORMANCE CHECKLIST Appl. To/JPM No.:

SIR0 84.0N.003.101 Page 6 of 12 Student Name:

Step 11 12 13 14 15 Action CLOSE MSV Bst Drn HV-10101 A,B,C,D by depressing common CLOSE push button.

CLOSE SSE Mn Stm Sup CV HV-10703.

ENSURE SSE Mn Stm Sup Ln Drn HV-10767 CLOSED.

ENSURE SSE Mn Stm Sup Ln Drn HV-10768 CLOSED.

CLOSE SSE Press Ctlr Is0 HV-10704,

• Critical Step

1. Critical Sequence STCP-QA-1255 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1 Standard Depresses the CLOSE pushbutton for MSV BST DRN HV-IOI~IA,B,C,D.

AND Verifies amber light LIT and red light NOT LIT.

Depress and hold the CLOSE pushbutton for SSE MN STM SUP CV HV-10703.

AND Verifies amber light LIT and red light NOT LIT.

Verifies amber light LIT and red light NOT LIT for SSE MN STM SUP LN DRN HV-10767.

Verifies amber light LIT and red light NOT LIT for SSE MN STM SUP LN DRN HV-10768.

Depresses the CLOSE pushbutton for SSE PRESS CTLR IS0 HV-10704.

AND Verifies amber light LIT and red light NOT LIT.

Eva1 Comments

PERFORMANCE CHECKLIST Page 7 of 12 Appl. TolJPM No.:

S/RO 84.0N.003.101 Student Name:

Step 16 I

I l

l Action Standard Eva1 Comments THROTTLE OPEN SSE Press Ctlr Byps THROTTLE OPEN SSE PRESS CTLR 1 EVALUATOR CUE:

17 I

I AND

• I 8 HV-10705 to establish 0.25 to 0.50 psis on SSE Pressure PI-I 0723.

BYPS HV-10705 to establish 0.25 to 1 0.5 psig on SSE Pressure indication PI-I I

I After HV-10705 is throttled open several times inform the candidate PI-I0723 is reading 0.4 psig CLOSE Mn Stm SJAE Is0 HV-10107.

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.

Mn Stm Line Div 1 Is0 Reset HS-921-1 S32 Reset push button.

Verifies red and amber lights LIT for HV-10705.

Depress the CLOSE pushbutton for MN STM SJAE IS0 HV-10107.

AND Verifies the amber light LIT and red light NOT LIT.

Depresses the RESET pushbutton for:

MN STM LINE DIV 1 IS0 RESET HS-B21-1 S32.

I I

• Critical Step

1. Critical Sequence STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.:

S/RO 84.0N.003.101 Step 19 I

PERFORMANCE CHECKLIST Action Mn Stm Line Div 2 Is0 Reset HS-B21-1 S33 Reset push button.

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:

If asked by the candidate if primary containment is in ieoprardy reply, !I primary containment intearitv is i.!n jeopardy

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

Page 1 of 1 2003 NRC Exam Rev. 1

1. Critical Sequence I

Page 8 of 12 Student Name:

Standard Depresses the RESET pushbutton for:

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.

Candidate asks if Primarv Containment is in Jeopardv. fif Eva1 Comments

Appl. To/JPM No.:

S/RO 84.0N.003.101 Step

• 20

1. 21 PERFORMANCE CHECKLIST Page 9 of 12 Action To OPEN I6 MSIVs PLACE following control switches to AUTO:

Mn Stm Line A I6 Is0 HV-141-FO22A.

Mn Stm Line B IB Is0 HV-141-FO22B.

Mn Stm Line C IB Is0 HV-141-FO22C.

Mn Stm Line D I6 Is0 HV-141-FO22D.

ALIGN for steam line pressurization as follows:

PLACE AC MOV OL BYPS HS-B21-1 S37A to TEST.

PLACE DC MOV OL BYPS HS-B21-1 S37B to TEST.

• Critical Step

1. Critical Sequence Student Name:

Standard Places the control switch to AUTO for:

b MN STM LINE A I6 IS0 HV-141-MN STM LINE B IB IS0 HV-141-MN STM LINE C I6 IS0 HV-141-F022A F022B F022C B MN STM LINE D IB IS0 HV-141-F022D b

b AND Verifies amber light NOT LIT and red light LIT for each valve.

Inserts key and rotates clockwise to place AC MOV OL BYPS HS-B21-1 S37A to TEST.

AND Verifies annunciator AR-111 -H03, AC CONTN IS0 VLVS IN TEST is LIT.

Inserts key and rotates clockwise to place DC MOV OL BYPS HS-B21-lS37B to TEST.

AND Verifies annunciator AR-112-H03, OUTBOARD ISOLATION VLVS IN TEST is LIT.

Eva1 Comments STCP-CIA-1256 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Appl. To/JPM No.:

S/RO 84.0N.003.101 Step Action OPEN Mn Stm Line IB Drain HV-141-F016.

OPEN Mn Stm Line OB Drain HV-141-FO19.

ENSURE Mn Steam Line Warm Up HV-14l-FO20 OPEN.

After 2 minutes, PLACE AC MOV OL Byps HS-B21-1 S37A to NORM.

• Critical Step

1. Critical Sequence Page 10 of 12 Student Name:

Standard Place switch to OPEN for MN STM LINE IB DRAIN HV-141-FO16.

AND Verifies amber light NOT LIT and red light LIT Place switch to OPEN for MN STM LINE OB DRAIN HV-141-F019.

AND Verifies amber light NOT LIT and red light LIT Verifies red light LIT and amber light NOT LIT.

After 2 minutes, place the AC MOV 0 BYPS HS-B21-1 S37A to NORM.

AND Verifies annunciator AR-111-H03, AC CONTN IS0 VLVS IN TEST is NOT LIT Eva1 Comments STCP-QA-125B Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. ToIJPM No.:

SIR0 84.0N.003.101 Step

1. 22 PERFORMANCE CHECKLIST Action After 2 minutes, PLACE DC MOV OL Byps HS-921-1 S37B to NORM.

OBSERVE main steam line pressure 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

1. Critical Sequence

('

Page 11 of 12 Student Name:

Standard After 2 minutes, place the DC MOV OL BYPS HS-B21-1 S37B to NORM.

AND Verifies annunciator AR-112-H03, OUTBOARD ISOLATION VLVS IN TEST is NOT LIT Verifies main steam line pressure INCREASING on Main Stm Press PR-10101 C.

Eva1 Comments STCP-QA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. To/JPM No.:

S/RO 84.0N.003.101 Step

1. 23

(

i" PERFORMANCE CHECKLIST Page 12 of 12 Action When differential pressure across MSlVs is between 53 psid and 200 psid, OPEN OB MSIV's by PLACING following control switches to AUTO:

Mn Stm Line A OB Is0 HV-141-FO28A Mn Stm Line B OB Is0 HV-141-FO28B Mn Stm Line C OB Is0 HV-141-FO28C Mn Stm Line D OB Is0 HV-141-FO28D Eva1 u at or Inform the student the JPM is complete.

• Critical Step

1. Critical Sequence Student Name:

Standard Compares RPV pressure with steam line pressure on PR-I0101 C until the d/p is between 50 and 200 psid AND When outboard MSlV d/p is between 50 and 200 psid, OPENS the outboard MSlVs by placing the control switch to AUTO for:

F028A F028B F028C F028D MN STM LINE A OB IS0 HV-141-MN STM LINE B OB IS0 HV-141-MN STM LINE C OB IS0 HV-141-MN STM LINE D OB IS0 HV-141-AND Verifies amber light NOT LIT and red light LIT for each valve.

Eva1 Comments 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.

2003 NRC Exam Rev. 1 Page 1 of 2

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.

2003 NRC Exam Rev. I Page 2 of 2

PENNSYLVANIA POWER & LIGHT COMPANY JOB PERFORMANCE MEASURE APPROVAL AND ADMINISTRATIVE DATA SHEET SIR0 84.0N.003.101 1

0611 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 InstructorNVriter Date Ap p rova I:

Requesting Supv.1C.A.

Date Nuclear Trng. Supv.

Date Head Date of Performance:

50 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 2003 NRC Exam Rev. 1 File No. A14-58

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 MAN I PU LATl ONS

=-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 Step 1

2

• 3 Action 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.

Obtain a controlled copy of ON-184-001.

RECORD date and time of this event.

PLACE control switches for following to CLOSE:

0 Mn Stm Line A IB Is0 HV-141-FO22A 0

Mn Stm Line B IB Is0 HV-141-FO22B 0

Mn Stm Line C IB Is0 HV-141-FO22C 0

Mn Stm Line D IB Is0 HV-141-FO22D 0

Mn Stm Line A OB Is0 HV-141-FO28A 0

Mn Stm Line B OB Is0 HV-141-FO28B 0

Mn Stm Line C OB Is0 HV-141-FO28C 0

Mn Stm Line D OB Is0 HV-141-FO28D

• Critical Step

1. Critical Sequence Student Name:

Standard Obtains Control copy of ON-184-001.

Places the control switch to CLOSE for the following:

F022A F022B F022C F022D F028A F028B F028C F028D MN STM LINE A IB IS0 HV-141-MN STM LINE B IB IS0 HV-141-MN STM LINE C IB IS0 HV-141-MN STM LINE D IB IS0 HV-141-MN STM LINE A OB IS0 HV-141-MN STM LINE B OB IS0 HV-141-MN STM LINE C OB IS0 HV-141-MN STM LINE D OB IS0 HV-141-Eva1 Comments STCP-QA-1258 Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Appl. To/JPM No.:

S/RO 84.0N.003.101 Step 4

5 6

7 Action ENSURE Mn Stm Line IB Drain HV-141-F016 CLOSED.

ENSURE Mn Stm Line OB Drain HV-141-F019 CLOSED.

ENSURE Mn Stm Line Drain to Cdsr HV-141-F021 CLOSED.

ENSURE following TRIPPED:

0 Main Turbine 0

0 0

Reactor Feed Pump Turbine A Reactor Feed Pump Turbine B Reactor Feed Pump Turbine C

• Critical Step

1. Critical Sequence Page 4 'ot I 2

Student Name:

Standard Checks amber light LIT and red light NOT LIT for:

MN STM LINE IB DRAIN HV-141-F016 Checks amber light LIT and red light NOT LIT for:

MN STM LINE OB DRAIN HV-141-FO19 Checks amber light LIT and red light NOT LIT for:

0 MN STM LINE IB DRAIN TO CDSR HV-1 4 1 -F021 For the 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 Amber light is LIT and red light above the Trip & Reset switch NOT LIT Eva1 Comments STCP-QA-1258 Rev. 2. (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

(:

PERFORMANCE CHECKLIST Page 5 ot 12

(

Appl. To/JPM No.:

S/RO 84.0N.003.101 Student Name:

Step 8

9 10 Action If isolation due to EHC System malfunction:

DEPRESS standby EHC Hyd Fluid Pump 1 P I 13B(A) STOP push button.

DEPRESS operating EHC Hyd Fluid Pump I

P I 13A(B) STOP push button.

0 ENSURE Turbine main stop valves CLOSED.

0 ENSURE Turbine bypass valves CLOSED.

CLOSE following by depressing Drip Leg Drn HS-1 01 12 AUTO push button:

0 Drip Leg Drn HV-10112A1.

Drip Leg Drn HV-10112B1.

0 Drip Leg Drn HV-lOIl2Cl.

Drip Leg Drn HV-10112D1.

CLOSE BPV Hdr Drip Leg Drn Byps HV-10108A by depressing HS-1 01 08A AUTO push button.

• Critical Step

1. Critical Sequence Standard Determines the isolation was an EHC system malfunction.

due to (Based on initial conditions)

Depresses the AUTO pushbutton on Checks white light LIT and red light NOT LIT.

DRIP LEG DRN HS-10112.

Checks amber light LIT and red light NOT LIT for :

DRIP LEG DRAIN HV-10112Al DRIP LEG DRAIN HV-10112B1 DRIP LEG DRAIN HV-10112Cl 0 DRIP LEG DRAIN HV-10112D1 Depresses the AUTO pushbutton on HS-10108A to CLOSE HV-10108A.

AND Verifies the white light is LIT and the red light is NOT LIT.

Eva1 Comments STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

Appl. TolJPM No.:

S/RO 84.0N.003.101 Step 11 12 13 14 15 PERFORMANCE CHECKLIST

~~

Action CLOSE MSV Bst Drn HV-10101 A,B,C,D by depressing common CLOSE push button.

CLOSE SSE Mn Stm Sup CV HV-10703.

ENSURE SSE Mn Stm Sup Ln Drn HV-10767 CLOSED.

ENSURE SSE Mn Stm Sup Ln Drn HV-10768 CLOSED.

CLOSE SSE Press Ctlr Is0 HV-10704,

• Critical Step

1. Critical Sequence Page 6 ot 12 Student Name:

Standard Depresses the CLOSE pushbutton for MSV BST DRN HV-IOIOIA,B,C,D.

AND Verifies amber light LIT and red light NOT LIT.

Depress and hold the CLOSE pushbutton for SSE MN STM SUP CV HV-10703.

AND Verifies amber light LIT and red light NOT LIT.

Verifies amber light LIT and red light NOT LIT for SSE MN STM SUP LN DRN HV-10767.

Verifies amber light LIT and red light NOT LIT for SSE MN STM SUP LN DRN HV-I 0768.

Depresses the CLOSE pushbutton for SSE PRESS CTLR IS0 HV-10704.

AND Verifies amber light LIT and red light NOT LIT.

Eva1 Comments STCP-QA-1250 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMAN& CHECKLIST Appl. TolJPM No.:

S/RO 84.0N.003.101 Step 16 17 18 Action THROTTLE OPEN SSE Press Ctlr Byps HV-10705 to establish 0.25 to 0.50 psig on SSE Pressure PI-I 0723.

EVALUATOR After HV-10705 is throttled open several times inform the candidate PI-I0723 is reading 0.4 psig CLOSE Mn Stm SJAE Is0 HV-10107 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 resettinn the NSSSS Main Steam Line Isolation.

Mn Stm Line Div 1 Is0 Reset HS-621-1 S32 Reset push button.

• Critical Step

1. Critical Sequence Page 7 ot 12 Student Name:

Standard THROTTLE OPEN SSE PRESS CTLR BYPS HV-I0705 to establish 0.25 to 0.5 psig on SSE Pressure indication PI-10723.

AND Verifies red and amber lights LIT for HV-10705.

Depress the CLOSE pushbutton for MN STM SJAE IS0 HV-10107.

AND Verifies the amber light LIT and red light NOT LIT.

Depresses the RESET pushbutton for:

0 MN STM LINE DIV 1 IS0 RESET HS-B21-I S32.

Eva1 Comments STCP-QA-125B Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCE CHECKLIST Appl. To/JPM No.:

SIR0 84.0N.003.101 Page 8 ot 12 Student Name:

Step 19

• 20 Action Mn Stm Line Div 2 Is0 Reset HS-B21-1 S33 Reset push button.

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.

To OPEN IB MSIVs PLACE following control switches to AUTO:

Mn Stm Line A IB Is0 HV-141-FO22A.

Mn Stm Line B IB Is0 HV-141-FO22B.

Mn Stm Line C IB Is0 HV-141-FO22C.

Mn Stm Line D IB Is0 HV-141-FO22D.

• Critical Step

1. Critical Sequence Standard Depresses the RESET pushbutton for:

MN STM LINE DIV 2 IS0 RESET HS-B21-1 S33.

AND Verifies that all 4 white status lights are LIT for the MSlV trip logic.

Places the control switch to AUTO for:

MN STM LINE A IB IS0 HV-141-MN STM LINE B IB IS0 HV-141-MN STM LINE C IB IS0 HV-141-MN STM LINE D IB IS0 HV-141-F022A F022B F022C F022D AND Verifies amber light NOT LIT and red light LIT for each valve.

Eva1 Comments STCP-QA-125B Rev. 2, (9193)

Page 1 of 1 2003 NRC Exam Rev. 1

i:

Appl. To/JPM No.:

S/RO 84.0N.003.101 Step

1. 21 PERFORMANCE CHECKLIST Action 4LIGN for steam line pressurization as follows:

PLACE AC MOV OL BYPS HS-B21-1 S37A to TEST.

PLACE DC 1 TEST.

OV OL Byps HS-B21-1 S37B to OPEN Mn Stm Line IB Drain HV-141-FO16.

OPEN Mn Stm Line OB Drain HV-141-F019.

• Critical Step

1. Critical Sequence

(

Page 9 or 12 Student Name:

Standard Inserts key and rotates clockwise to place AC MOV OL BYPS HS-B21-1 S37A to TEST.

AND Verifies annunciator AR-111 -H03, AC CONTN IS0 VLVS IN TEST is LIT.

Inserts key and rotates clockwise to place DC MOV OL BYPS HS-B21-1S37B to TEST.

AND Verifies annunciator AR-I 12-H03, OUTBOARD ISOLATION VLVS IN TEST is LIT.

Place switch to OPEN for MN STM LINE IB DRAIN HV-141-F016.

AND Verifies amber light NOT LIT and red light LIT Place switch to OPEN for MN STM LINE OB DRAIN HV-141-F019.

AND Verifies amber light NOT LIT and red light LIT Eva1 Comments STCP-QA-1256 Rev. 2. (9/93)

Page I of 1 2003 NRC Exam Rev. 1

(:

PERFORMANCE CHECKLIST Appl. To/JPM No.:

S/RO 84.0N.003.101 Step

1. 22 Action ENSURE Mn Steam Line Warm Up HV-141-F020 OPEN.

After 2 minutes, PLACE AC MOV OL Byps HS-B21-1 S37A to NORM.

After 2 minutes, PLACE DC MOV OL Byps HS-B21-1S37B to NORM.

OBSERVE main steam line pressure INCREASING on Main Stm Press PR-I 01 01 C.

CAUTION OPENING MSIV'S WITH LARGE DIFFERENTIAL PRESSURE WILL CAUSE RPV PRESSURE TO DROP RAPIDLY AND RPV LEVEL TO SWELL.

• Critical Step

1. Critical Sequence

(

Page I o 'ot I 2

Student Name:

Standard Verifies red light LIT and amber light NOT LIT.

After 2 minutes, place the AC MOV OL BYPS HS-B21-1 S37A to NORM.

AND Verifies annunciator AR-I I I-H03, AC CONTN IS0 VLVS IN TEST is NOT LIT After 2 minutes, place the DC MOV OL BYPS HS-B21-1S37B to NORM.

AND Verifies annunciator AR-I 12-H03, OUTBOARD ISOLATION VLVS IN TEST is NOT LIT Verifies main steam line pressure INCREASING on Main Stm Press PR-I0101 C.

Eva1 Comments STCP-QA-1256 Rev. 2, (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

PERFORMANCk CHECKLIST Page 11 OT 12 Appl. To/JPM No.:

S/RO 84.0N.003.101 Step

1. 23 Action When differential pressure across MSlVs is between 50 psid and 200 psid, OPEN OB MSIVs by PLACING following control switches to AUTO:

Mn Stm Line A OB Is0 HV-141-FO28A Mn Stm Line B OB Is0 HV-141-FO28B Mn Stm Line C OB Is0 HV-141 -F028C Mn Stm Line D OB Is0 HV-141 -F028D Evaluator Inform the student the JPM is complete.

• Critical Step STCP-CIA-1258 Rev. 2. (9/93)

Page 1 of 1 2003 NRC Exam Rev. 1

1. C ri tica I Sequence Student Name:

Standard Compares RPV pressure with steam line pressure on PR-10101C until the dlp is between 50 and 200 psid AND When outboard MSlV d/p is between 50 and 200 psid, OPENS the outboard MSIVs by placing the control switch to AUTO for:

F028A F028B F028C F028D MN STM LINE A OB IS0 HV-141-MN STM LINE B OB IS0 HV-141-MN STM LINE C OB IS0 HV-141-MN STM LINE D OB IS0 HV-141-AND Verifies amber light NOT LIT and red light LIT for each valve.

Comments

w-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.

2003 NRC Exam Rev. 1 Page 1 of 2

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.

2003 NRC Exam Rev. 1 Page 2 of 2