Text

05-2004 Draft Operating Examination
	ML042080207
Person / Time
Site:	Wolf Creek
Issue date:	05/13/2004
From:	Gody A; Operations Branch IV
To:	Muench R; Wolf Creek
References
	50-482/04-301 50-482/04-301
	Download: ML042080207 (351)
	v • d • e

Control Room C-1 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 601-C K/A NO: 055 EA1.07 COMPLETION TIME: 20 Minutes K/A RATING: 4.3/4.5 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: EMG C-0 , Loss of All AC, Align Alternate Power to Safeguards Bus using the OFN DUTY: Station Blackout ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM X SIMULATOR/LAB PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 601-C C-1 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has experienced a complete loss of AC electrical power. to the switchyard.

Emergency Diesel Generator B (NE02) is tagged out for 12 more hours. Bus NB01 has experienced a bus lockout and Electrical Maintenance estimates it will take three hours to clear it.

Initiating Cues: System Operations has informed the Control Room that they will be able to re energize the Athens 69KV line in about 30 minutes. The Control Room Supervisor has directed you to go to OFN NB-30, Loss Of AC Emergency Bus NB01 (NB02),

and mark up the steps that will need to be performed in order to restore power to an NB Bus.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the Candidate with a current copy of OFN NB-030.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have provided a marked up copy of the procedure which indicates the steps of the procedure which will need to be performed to energize NB-02 from the Athens 69KV line.

START TIME:

STOP TIME:

PAGE 1 of 9

JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Check AC Buses - AT Check NB EI-1 and NB LEAST ONE EI-2 and determine both Comments:

ENERGIZED buses have zero voltage STEP 1 When candidate checks NOTE: Candidate may NB EI-1 and NB EI-2 decide from the Initial state that no voltage is conditions that neither indicated bus is energized.

S U Note that NB01 is locked

2. *If entering this out and go to Attachment Comments:

procedure from EMG B step B12 for NB02 C-0 then go to desired attachment STEP 1 RNO S U

3. Check NB02 bus Note Annunciator 21A, lockout relays - RESET Bus Lockout - CLEAR Comments:

Annunciator 21A not lit STEP B12

CRITICAL STEP PAGE 2 of 9

JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Note that NE02 is tagged

4. *Check EDG NE02 - out in the initial Comments:

RUNNING conditions and perform the RNO STEP B13 S U

5. If CRS directs that NB02 Should realize that this be energized from a was directed in the initial Comments:

source other than the conditions of this JPM.

diesel, then go to:

B16 for normal offsite or

B18 for alternate Note that NB02 is the offsite only bus available and go to B18 STEP B13 RNO S U

6. *Verify alternate offsite Comments:

power supply -

AVAILABLE Check annunciator 19A

Check annunciator 19A, XNB01 XFMR Annunciator 19A -

Lociout - CLEAR CLEAR

Check XNB01 - Note that no power is ENERGIZED BY currently available to OFFSITE POWER XNB01 and perform the RNO STEP B18

CRITICAL STEP PAGE 3 of 9

JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. *Perform the following Comments:

Transition to Attachment

Energize XNB01 C using Attachment C STEP B18 RNO b.

S U

8. Verify Annunciator 12E - Check Annunciator 12E CLEAR Comments:

Annunciator 12E is STEP C1 CLEAR

9. Verify Power Supply to Contact the Site Operator

4 Transformer Load and verify Tap Changer - ON NOTE: Candidate may STEP C2 Verify that the power indicated that they would supply to the load tap do this later when changer is ON actually performing the procedure.

CRITICAL STEP PAGE 4 of 9

JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. Verify Power Supply to Contact the Site Operator

5 Transformer Load and verify Comments:

Tap Changer - ON NOTE: Candidate may STEP C3 Verify that the power indicated that they would supply to the load tap do this later when changer is ON actually performing the procedure S U

11. Ensure load tap changers Contact the Site Operator on #4 transformer - and verify Comments:

AUTO Verify they are in AUTO NOTE: Candidate may STEP C4 indicated that they would do this later when actually performing the procedure S U

12. Ensure load tap Contact the Site Operator changers on #5 and verify Comments:

transformer - AUTO Verify they are in AUTO NOTE: Candidate may STEP C5 indicated that they would do this later when actually performing the procedure

CRITICAL STEP PAGE 5 of 9

JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. Ensure breaker 13-8 is Contact Site Operator and open and racked in verify Comments:

Verify it is open and STEP C6 racked in NOTE: Candidate may indicated that they would do this later when actually performing the procedure S U

14. Ensure Disconnect 13- Contact Site Operator and 21 is closed verify Comments:

Verify it is closed STEP C7 NOTE: Candidate may indicated that they would do this later when actually performing the procedure S U Place handswitch 13-48

15. *Place breaker 13-48 in in PTL Comments:

PTL STEP C8

CRITICAL STEP PAGE 6 of 9

JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Rotate 1HS-SY0018 to

16. *Close breaker 13-8 the right and note the red Comments:

lite only is lit.

STEP C9 Return to step B18 RNO

b. 2)

S U Go to B19

17. *Perform the following Comments:

If XNB01 can be energized then go to step B19 STEP B18 RNO b S U

18. Check NB01 normal Check NB HIS-2 -OPEN supply breaker - OPEN. Comments:

NB HIS-2 indicates STEP B19 green lite only

CRITICAL STEP PAGE 7 of 9

JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

19. *Reenergize NB02 from Comments:

alternate offsite power supply Rotate NB HS-9 to ON

Place alternate sync transfer switch to ON

Close NB02 alternate Rotate NB HIS-5 to the supply breaker right and note red lite only lit

Place alternate supply sync transfer Rotate NB HS-9 to OFF switch to OFF

Check NB02 - Check XXX for voltage ENERGIZED THE JPM IS COMPLETE RECORD STOP TIME STEP B20 ON PAGE 1

CRITICAL STEP PAGE 8 of 9

JPM NO: 601-C C-1 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has experienced a complete loss of AC electrical power. to the switchyard.

Emergency Diesel Generator B (NE02) is tagged out for 12 more hours. Bus NB01 has experienced a bus lockout and Electrical Maintenance estimates it will take three hours to clear it.

Initiating Cues: System Operations has informed the Control Room that they will be able to re energize the Athens 69KV line in about 30 minutes. The Control Room Supervisor has directed you to go to OFN NB-30, Loss Of AC Emergency Bus NB01 (NB02),

and mark up the steps that will need to be performed in order to restore power to an NB Bus.

PAGE 9 of 9

In Plant P-1 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 302-P K/A NO: 006 A2.02 COMPLETION TIME: 10 Minutes K/A RATING:3.9/4.3 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Locally Unisolate the BIT DUTY: Emergency Core Cooling System The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

EMG FR-C1, Response to Inadequate Core Cooling TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 302-P P-1 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has experienced a reactor trip and safety injection. The crew has entered EMG FR-C1, Response to Inadequate Core Cooling.

Initiating Cues: The Control Room Supervisor directs you to ensure one of the following trains of valves is open to align the NCP to the BIT.

BG-V8483A AND EM HV8803A OR BG V8483C AND EM HV8803B DO NOT OPERATE ANY EQUIPMENT IN THE PLANT ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have aligned the NCP discharge to the Boron Injection Tank.

START TIME:

STOP TIME:

PAGE 1 of 5

JPM NO: 302-P P-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 1 Ensure BG-V8483A is Locate BG-V8483A on open the 1974 level of the Comments:

Aux Bldg, in the A CCP room and check the position by turning the valve clockwise and/or looking at the position indicator Valve operator will turn in the clockwise

OR direction. Valve indicator indicates open. OR Locate BG-V8483C on Ensure BG-V8483C is the 1974 level of the open Aux Bldg, in the B CCP room and check the position by turning the valve clockwise and/or looking at the position indicator Valve operator will turn in the clockwise direction. Valve indicator indicates open STEP A16 RNO

CRITICAL STEP PAGE 2 of 5

JPM NO: 302-P P-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

2. Ensure EMG HV-8803A If BG-V8483A was is open checked open in element Comments:

1 than locate EM HV-8803A in the BIT room..

Check the valve open by turning the handwheel in the clockwise direction to see if it will turn or check Valve operator will not the position indicator.

turn in the clockwise direction. Position indicator is down.

Turn the valve operator in counterclockwise direction and check Valve opeator is turning position indicator in the counterclockwise direction. Position indicator is moving up.

Position indicator is all the way up.

OR OR If BG-V8483C was checked open in element Ensure EM HV-8803B is 1 than locate EM HV-open 8803B in the BIT room.

Check the valve open by turning the handwheel in the clockwise direction to Valve operator will not see if it will turn or check turn in the clockwise the position indicator.

direction. Position indicator is down.

Turn the valve operator in counterclockwise Valve opeator is turning direction and check in the counterclockwise position indicator direction. Position indicator is moving up.

Position indicator is all the way up STEP A16 RNO

CRITICAL STEP PAGE 3 of 5

JPM NO: 302-P P-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

3. Report task complete Simulate calling the Control Room and Comments:

STEP A16 RNO reporting task complete.

Acknowledge report THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 5

JPM NO: 302-P P-1 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has experienced a reactor trip and safety injection. The crew has entered EMG FR-C1, Response to Inadequate Core Cooling.

Initiating Cues: The Control Room Supervisor directs you to ensure one of the following trains of valves is open to align the NCP to the BIT.

BG-V8483A AND EM HV8803A OR BG V8483C AND EM HV8803B DO NOT OPERATE ANY EQUIPMENT IN THE PLANT PAGE 5 of 5

In Plant P-2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 602-P K/A NO: 057 AA1.01 COMPLETION TIME: 20 Minutes K/A RATING: 3.7/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Align 120 vac Vital Bus to SOLA Xfmr DUTY: Loss of Vital AC Instrument Bus ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

OFN NN-021 TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 602-P P-2 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 3 with all items for entering Mode 2 complete. Annunciator 25A, NN01 Bus UV and 25B, NN11 Inv UV, have gone into alarm. The Reactor Operator has verified from OFN NN-021, Loss of 120 VAC Instrument Bus, that Bus NN01 is de energized..

Initiating Cues: The Control Room Supervisor directs you to locally restore power to BUS NN01 using OFN NN-021, Step A4.

DO NOT OPERATE ANY COMPONENTS IN THE PLANT ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the candidate with an information only copy of OFN NN-21, Attachment A.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have placed the NN01 Bus on the power supply from the SOLA Transformer.

START TIME:

STOP TIME:

PAGE 1 of 5

JPM NO: 602-P P-2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Locally Restore power to Bus NN01 Comments:

Check NN Bus - NO APPARENT At NN01, 2016 level of DAMAGE the Control Building, check for indication physical damage No damage is evident and no odor of smoke or heat exists.

Look at inverter output

*Check inverter voltmeter on NN11 NN11 output voltage

- NORMAL Meter indicates 0 voltage Realize that voltage is not normal and perform the RNO to go to Step A5 STEP A4

CRITICAL STEP PAGE 2 of 5

JPM NO: 602-P P-2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE

2. Align Backup Power to Bus NN01

*Close backup Locate NG01ACR3, transformer XNN05 2000 level of Control power supply Breaker operator is Building, and rotate the breaker pointing to the closed operator to the right position

Verify backup power Look at white light on available white light White lite is illuminated NN11

- LIT Install the interlock key into the lock mechanism

*Open normal and turn. Move the NN0101 breaker operator feeder breaker to the left until it indicates off.

Breaker operator is pointing at the open position Move the slide bar to the left and move NN0102 breaker operator to the

*Close alternate left until it indicates feeder breaker closed Breaker operator is pointing at the closed position Call the Control Room and report NN01 is powered from the SOLA transformer. Note that TS

3. Refer to applicable 3.8.7 and 3.8.8 must be Technical Specifications referred to.

STEP A5

CRITICAL STEP PAGE 3 of 5

JPM NO: 602-P P-2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE Acknowledge report.

Balance of crew will refer to Technical Specifications.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 5

JPM NO: 602-P P-2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 3 with all items for entering Mode 2 complete. Annunciator 25A, NN01 Bus UV and 25B, NN11 Inv UV, have gone into alarm. The Reactor Operator has verified from OFN NN-021, Loss of 120 VAC Instrument Bus, that Bus NN01 is de energized..

Initiating Cues: The Control Room Supervisor directs you to locally restore power to BUS NN01 using OFN NN-021, Step A4.

DO NOT OPERATE ANY COMPONENTS IN THE PLANT PAGE 5 of 5

In Plant P-3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 202-P K/A NO: 002 A2.01 COMPLETION TIME: 10 Minutes K/A RATING: 4.3/4.4 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: EMG C-0, Loss of All AC, Isolate RCP Seal Leak Off DUTY: Reactor Coolant System The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

EMG C-0, Loss Of All AC Power TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 202-P P-3 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has experienced a total loss of AC power. EMG C-0 is being performed.

Initiating Cues: The Control Room Supervisor has directed you to perform step 15 of EMG C-0 to isolate the RCP seals.

DO NOT OPERATE ANY EQUIPMENT IN THE PLANT ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the Candidiate with a copy of EMG C-0, Step 15.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have isolated the valves from the RCP seals.

START TIME:

STOP TIME:

PAGE 1 of 4

JPM NO: 202-P P-3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Dispatch personnel to locally close valves to Comments:

isolate RCP seals Go to BG HV-8100 at

*Seal Water Return Aux Building , 2000 Containment Isolation level, South Penetration Valve Room. Push down on the declutch lever and operate the valve in the clockwise direction.

Note the stem indication.

Valve is turning in the clockwise direction.

Valve will not turn any more. Stem is totally inserted.

Go to BG V101 at Aux

*Seal Water Building, 2000 level, Injection Filters Inlet RX Coolant Filter/Seal Isolations Injection Filter A Valve Room. Rotate the valve operator in the clockwise direction and note the Valve is turning in the position of the stem.

clockwise direction.

Valve will not turn any more. Stem is totally inserted. Go to BG V105 at Aux Building, 2000 level, RX Coolant Filter/Seal Injection Filter B Valve Room. Rotate the valve operator in the clockwise direction and not the position of the stem Valve is turning in the clockwise direction.

Valve will not turn any more. Stem is totally inserted

CRITICAL STEP PAGE 2 of 4

JPM NO: 202-P P-3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE Go to the EG HV-61 at the Aux Building, 2000, North Penetration Room.

*CCW Return From Push down on the RCS Isolation Valve declutch lever and operate the valve in the clockwise direction.

Note the stem indication.

STEP 15 Call Control Room and Acknowledge report report step 15 complete.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 3 of 4

JPM NO: 202-P P-3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has experienced a total loss of AC power. EMG C-0 is being performed.

Initiating Cues: The Control Room Supervisor has directed you to perform step 15 of EMG C-0 to isolate the RCP seals.

DO NOT OPERATE ANY EQUIPMENT IN THE PLANT PAGE 4 of 4

Administrative RO A1a WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 001-A K/A NO: 2.1.33 COMPLETION TIME: K/A RATING: 3.4 JOB TITLE: RO REVISION: 0 TASK TITLE: Perform Surveillance Test for AFD DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

MAY BE PERFORMED IN ANY LOCATION WHERE PROPER REFERENCE MATERIAL IS AVAILABLE.

METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

STS SF-002, CORE AXIAL FLUX DIFFERENCE CORE OPERATING LIMITS REPORT TECHNICAL SPECIFICATION 3.2.3 TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 001-A RO A1a Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has been stable at 100%. The AFD Monitor Alarm is inoperable.

Initiating Cues: The Control Room Supervisor has directed you to perform STS SF-002 and Determine T/S compliance.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the candidate with an information only copy of STS SF-002.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

THE FOLLOWING DATA IS PROVIDED ON THE CUE SHEET N41 N42 N43 N44

% Power 100 100 100 100

% Flux Difference -13 -16 -16 -14 Task Standard: Upon completion of this JPM, the operator will have determined that the Plant is in Technical Specification 3.2.3, Action A.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 001-A RO A1a Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Record data as required Go to Attachment A and on Attachment A enter the data provide on Comments:

the cue sheet

*Compare % flux Determine that N41 and for each channel to N44 are in the acceptable COLR limits region, determine that N42 and N43 are in the unacceptable region, and annotate the attachment accordingly Determine that the Plant

*If the indicated is in TS 3.2.3 and report FLUX DIFF is to the Control Room outside the Supervisor.

acceptable limits of COLR on two or more operable PR channels, then perform the actions required by Tech Specs THE JPM IS COMPLETE RECORD STOP TIME STEP 8.1 ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 001-A RO A1a Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has been stable at 100%. The AFD Monitor Alarm is inoperable.

Initiating Cues: The Control Room Supervisor has directed you to perform STS SF-002 and Determine T/S compliance.

THE FOLLOWING DATA IS PRESENT ON PLANT INSTRUMENTATION N41 N42 N43 N44

% Power 100 100 100 100

% Flux Difference -13 -16 -16 -14 PAGE 3 of 3

CORRECTED COPY 07-03-2002 STS SF-002 CORE AXIAL FLUX DIFFERENCE Responsible Manager Manager Operations

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³ Revision Number ³ 7 ³

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³ Use Category ³ Continuous

³

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³ Administrative Controls Procedure ³ No ³

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³ Infrequently Performed Procedure ³ No ³

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³ Program Number ³ 21D ³

DC22 12/18/1999

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 1 of 6 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 2 3.1 References 2 3.2 Commitments 2 4.0 PRECAUTIONS/LIMITATIONS 2 5.0 TEST EQUIPMENT 2 6.0 ACCEPTANCE CRITERIA 2 7.0 PREREQUISITES 2 8.0 PROCEDURE 4 9.0 RESTORATION 4 10.0 RECORDS 5 ATTACHMENT A AXIAL FLUX DIFFERENCE LOG 6

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 2 of 6 1.0 PURPOSE 1.1 The purpose of this procedure is to monitor and log Axial Flux Difference (AFD) at least once per hour when the AFD Monitor Alarm (NPIS Computer) is inoperable.

2.0 SCOPE 2.1 This procedure satisfies the requirements of Technical

³ Requirements Manual TR 3.3.17 and Technical Specification

³ SR 3.2.3.1 if/when the NPIS Computer is inoperable for

³ more than 7 days.

³

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3.1.1 WCGS Technical Specifications 3.1.2 COLR, Core Operating Limits Report 3.1.3 WCGS Technical Requirements Manual

³ 3.2 Commitments 3.2.1 None

³ 4.0 PRECAUTIONS/LIMITATIONS 4.1 Report any irregularities or component malfunctions to the

³ Shift Manager immediately, and reference Technical

³ Specification LCO 3.2.3.

³ 4.2 The Control Rods should not be moved when the AFD is being monitored.

4.3 The AFD Monitor Alarm is an NPIS Computer generated alarm.

It is considered operable by the performance of STN RJ-001, VERIFICATION OF OPERABILITY OF COMPUTER PROCESSES, whenever the NPIS Computer is operable, and is inoperable whenever the NPIS Computer is down.

5.0 TEST EQUIPMENT 5.1 None 6.0 ACCEPTANCE CRITERIA

6.1 AFD is monitored to be within the limits specified in the COLR.

6.2 The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 3 of 6 7.0 PREREQUISITES INIT/DATE 7.1 The plant is in Mode 1 with thermal power greater

³ than or equal to 50% rated thermal power. /

³ 7.2 The AFD Monitor Alarm is inoperable. /

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 4 of 6 INIT/DATE 8.0 PROCEDURE

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³ NOTE ³

³ ³

³ The recorded values of indicated FLUX DIFF shall be assumed to ³

³ exist during the interval preceding each logging. ³

³ ³

8.1 At RL004, record data as required on ATTACHMENT A, at least once per hour for each operable power range channel. (Mark inoperable channel(s) N/A) 8.1.1 Compare the % FLUX DIFF from each operable power range channel to the limits of COLR, Figure 2.5.

1. Designate whether the indicated % FLUX DIFF is within the acceptable operation range of COLR, Figure 2.5 for each operable channel by placing a check mark in yes (Y) or no (N) column.

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¿

³ NOTE ³

³ ³

³ The AFD shall be considered outside the limits when two or more ³

³ operable excore channels indicate AFD to be outside the limits. ³

³ ³

8.1.2 IF the indicated FLUX DIFF is outside the acceptable limits of COLR, Figure 2.5 on two or more operable power range channels, THEN perform the actions required by Technical Specification 3.2.3.

8.2 IF additional copies of ATTACHMENT A are needed, THEN attach copies as necessary and sequentially number each sheet in the space provided.

9.0 RESTORATION 9.1 None

9.2 Comments

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 5 of 6 10.0 RECORDS 10.1 The following QA records are generated by this procedure:

10.1.1 Sections 7, 8 and 9 10.1.2 ATTACHMENT A

-END-

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 6 of 6 ATTACHMENT A (Page 1 of 1)

AXIAL FLUX DIFFERENCE LOG (Step 8.2) Sheet of

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³ ³ Step 8.1 (RL004) ³Step 8.1.1.1 ³ ³

³ ÃÂ'In COLR Fig.2.5³ ³

³ ³ % POWER ³ % FLUX DIFF ³Acceptable Rg. ³ ³

³ TIME

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³

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-END-

FORM APF 29B-003-01 REV 04 SURVEILLANCE TEST ROUTING SHEET (STRS)

DOCUMENT NUMBER: STS SF-002 **TEST FREQ. Contingent

- DUE DATE/TIME: N/A DOCUMENT TITLE: **LATE DATE/TIME: N/A CORE AXIAL FLUX DIFFERENCE **T/S REQUIRED MODE: 1

- REQUIRED PLANT MODE: 1

- INITIATING DOCUMENT #(S):

- SUPPORTING CLEARANCE ORDER(s) [Commitment Step 3.2.29]

- RESPONSIBLE GROUP: OPS

- SUPPORT GROUP(S):

- PRE-TEST COMMENTS:

1) PROCEDURE VERIFIED TO BE CORRECT REVISION WITH ALL _______/_______

TEMPORARY CHANGES ATTACHED AND INCORPORATED. INIT/DATE TEST PERFORMERS:

PRINT NAME INIT/DATE PRINT NAME INIT/DATE

/ / / /

2) PRE-TEST REVIEWS: SIGNATURE DATE TIME

/ /

SM/CRS/DESIGNEE AUTH/NOTIF/NI / /

(CIRCLE AS APPLICABLE) / /

3) *TEST DEFICIENCY DESCRIPTION:

/

4) *T/S OR TRM FAILURE? TP INIT / DATE

¨ YES ¨ NO /

SM/CRS/DESIGNEE SIGNATURE DATE IF NO - JUSTIFICATION:

5) *ACTION TAKEN:

EOL # WR/WO#

TEST SUSPENDED ¨ YES ¨ NO /

SM/CRS/DESIGNEE SIGNATURE DATE

SECTIONS 3, 4, AND 5 ARE COMPLETED IF A TEST DEFICIENCY OCCURS. OTHERWISE MARK N/A.

6) POST TEST REVIEWS: (GROUP SUP. CHECK ONE) ¨ COMPLETE ¨ PARTIAL ¨ N/A TOTAL MAN HOURS:

SIGNATURE DATE TIME

/ /

TEST PERFORMER

/ /

SM/CRS/DESIGNEE REVIEW/NOTIF:

GROUP SUPERVISOR:

SC/SURV. TECHNICIAN

7) ADDITIONAL COMMENTS**:

- OPTIONAL INFORMATION NOT REQUIRED TO BE FILLED IN GEN 00-003 HOT STANDBY TO MINIMUM LOAD Responsible Manager Manager Operations

Ú

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³ Revision Number ³ 62 ³

Ã

Å'

³ Use Category ³ Continuous

³

Ã

Å'

³ Administrative Controls Procedure ³ No ³

Ã

Å'

³ Infrequently Performed Procedure ³ Yes ³

Ã

Å'

³ Program Number ³ 21D ³

DC12 11/25/2003

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 1 of 61 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 3 3.1 References 3 3.2 Commitments 4 4.0 PRECAUTIONS/LIMITATIONS 6 5.0 PREREQUISITES 13 6.0 PROCEDURE 20 7.0 FINAL CONDITIONS 57 8.0 RECORDS 57 ATTACHMENT A TECHNICAL SPECIFICATIONS WHICH BECOME APPLICABLE IN MODE 2 58 ATTACHMENT B TECHNICAL SPECIFICATIONS WHICH BECOME APPLICABLE IN MODE 1 60 FIGURE 1 1/M PLOT 61

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 2 of 61 1.0 PURPOSE 1.1 This procedure provides instructions for taking the plant from Hot Standby at no-load conditions to greater than or equal to 30% of full power.

2.0 SCOPE 2.1 Provide sequential steps to place equipment in service to support plant startup.

2.2 Provide verification of system and equipment status during startup to meet Technical Specification operability requirements.

2.3 Provide administrative requirements to ensure operators are cognizant of Mode dependent Technical Specification applicability.

2.4 Provide management verification that procedural and administrative requirements have been satisfied to proceed with the next Mode change.

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 3 of 61

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3.1.1 EER 90-MA-03 Disposition Revision 1, PMR 4203 3.1.2 PMR 3669 and 2946, Feedwater Preheating 3.1.3 PMR 3388, Reflash of Source Range Flux Doubling When Blocked 3.1.4 LER 86-042, Low-Low S/G Level Caused Reactor Trip 3.1.5 LER 85-042, Reactor Trip and ESFA - Shrink and Swell 3.1.6 SAP 89-138, RCCA Driveline Wear Recommendations 3.1.7 NRC GENERIC LETTER 93-04, Rod Control System Failure, ET 93-0094 (RCMS #93-175) 3.1.8 EER 89-BB-07, Pressurizer and RCS Operational Limits 3.1.9 PIR 96-1221, Extraction Valves Found Closed 3.1.10 T/S Amendment 148, Decalibration Effects Of Calorimetric On NIS High Power Reactor Trip At Reduced Power Levels. ESBU TB-92-14-R1, WESTINGHOUSE TECHNICAL BULLETIN 3.1.11 PIR 96-2860, NIS Scaler/Timer Nixie Tube Burn Out 3.1.12 ANSI/ANS - 19.6.1 - 1997, Reload Startup Physics Tests for Pressurized Water Reactors.

3.1.13 Westinghouse letter NF-SAP-02-10, WCNOC 02-00088, Revised Limits and Conditions for Ramp Rate Limits MFRD-01-222 Rev. 1. Fuel Preconditioning Limits Raised From 20 % to 40% Power.

3.1.14 EER 88-SE-02/PMR 3459, Source Range High Voltage NOT Interlocked to P-6 Bistable 3.1.15 UFSAR SECTION 3.9.(N).1.1 MECHANICAL SYSTEMS AND COMPONENTS 3.1.16 CCP 09953, Reactor Vessel Simplified Head Assembly 3.1.17 ITIP 01654, Conduct of Infrequently Performed Tests or Evolution 3.1.18 ITIP 68, Potential Malfunction of Permissive P-10 3.1.19 ITIP 4313, OE 9822 "Administrative Limit (difference) Between Pressurizer and Reactor Coolant System Boron Concentration Exceeded"

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 4 of 61 3.1.20 PIR 2001-0107, Westinghouse NSAL 00-016: Rod Withdrawal From Subcritical Protection In Lower Modes 3.1.21 CCP 011178, RVLIS Scaling

³ 3.2 Commitments 3.2.1 Tech Spec Amendment No. 29, AFP ESFAS BLOC 3.2.2 EER 86-AF-04, Water Hammer Prevention 3.2.3 ITIP 00922/SER 06-89, Dropped Rods at Low Power 3.2.4 LER 89-5, Late Performance of Unit Vent Sample 3.2.5 LER 87-018/LER 86-008, Personnel Error While Placing AFAS Switch in Permit, WM 87-0143 (RCMS #87-312 &

86-042) 3.2.6 ITIP 1088 and ITIP 1420, SOER 90-03 R1.a, Miscalibration of Excore Nuclear Detectors 3.2.7 ITIP 00719, SOER 88-2 R6, Premature Criticality Events During Reactor Startup 3.2.8 LER 85-064, Reactor Trip and ESFA - Lack of Preheat, KMLNRC 85-223 (RCMS #85-428) 3.2.9 EER 92-GN-01, Rev. 1, CTMT Coolers & Hydrogen Mixing Fan Operations 3.2.10 LER 93-10, Mode Change With MDAFW Pumps in "Pull-To-Lock", ET 93-0087, WO 93-0114 (RCMS #93-180

& 93-188) 3.2.11 Letter WM 94-0068, Revision in Commitments for Operations Management Review Items Prior to Plant Mode Changes 3.2.12 PIR 96-3093, ITIP 03550, SOER 96-02 R4, Design and Operating Considerations for Reactor Cores 3.2.13 ET 88-0130, NOV 482/8821-04, Corrective Action Ineffective in Preventing Recurrence of ESFAS Actuation (RCMS # 88-278) 3.2.14 LER 85-072, Reactor Trip and ESFA - S/G Level Control (RCMS # 85-434) 3.2.15 LER 85-042, Reactor Trip and ESFA - Shrink and Swell (RCMS # 85-421) 3.2.16 PIR 2002-1180, Reactor Trip due to Failure of MFRV Manual Control

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 5 of 61 3.2.17 PIR 2002-1293, Difficulties During Turbine Warming 3.2.18 PIR 2002-1104, Sequencing Turbine Testing and EHC Venting

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 6 of 61 4.0 PRECAUTIONS/LIMITATIONS 4.1 Criticality must be anticipated whenever shutdown or control rods are being withdrawn or boron dilution operations are in progress.

4.2 Criticality shall not be achieved by boron dilution with the exception of initial criticality after refueling.

4.3 If at any point during the boron dilution, an unexpected increase in the count rate by a factor of two occurs, all operations involving positive reactivity must be terminated pending an evaluation.

4.4 A stable startup rate of 1 decade per minute (DPM) or a transient startup rate of 1.5 DPM shall not be exceeded.

4.5 When the reactor is subcritical, minimize addition of positive reactivity by more than one controlled method at a time.

4.6 Maintain RCS operating loop average temperature greater than or equal to 551°F when in Mode 1 or in Mode 2 with Keff ³1.

TS 3.4.2.

4.7 If a dropped rod event occurs during the performance of this procedure which causes the reactor to go subcritical, all control banks shall be re-inserted and the startup re-performed. [3.2.3]

4.8 Maintain shutdown margin greater than or equal to 1.3% Dk/k as required by TS 3.1.1.

4.9 Prior to withdrawing shutdown banks, shutdown margin shall be calculated for shutdown banks withdrawn.

4.10 When changing Reactor Coolant System boron concentration, maintain differential boron concentration between the pressurizer and RCS loops less than or equal to 50 ppm by having both groups of pressurizer backup heaters energized and leaving pressurizer spray control in automatic. (3.1.19) 4.11 When auxiliary spray is being used, the following criteria applies:

4.11.1 Auxiliary spray DT (pressurizer temperature minus CVCS temperature) shall be plotted using STS BB-011, REACTOR COOLANT SYSTEM AND PRESSURIZER HEATUP/COOLDOWN SURVEILLANCE.

4.11.2 Auxiliary spray DT shall be maintained less than or equal to 583°F to satisfy TR 3.4.3.

4.11.3 If auxiliary spray DT exceeds 320°F, logging of this transient cycle should be made with reference to AP 23I-001, FATIGUE MANAGEMENT and TS 5.5.5.

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 7 of 61 4.12 If the reactor is subcritical below P-6 setpoint, the following applies: (3.1.14)

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¿

³ NOTE ³

³ ³

³ Alarm 00-057A, SR FLUX DOUBLED, cannot be reinstated until both ³

³ intermediate range channels are less than P-6 setpoint and P-6 ³

³ light is out. ³

³ ³

4.12.1 If P-6 is NOT reset, THEN perform the following:

1. Manually reenergize source range channels as follows:

Reset source range channels using SE HS-5 and SE HS-10 OR

Place high voltage manual control switch in HV ON position 4.12.2 If only one source range channel is operable, refer to TS 3.3.1, Table 3.3.1-1, Function 5.

4.12.3 If both source range channels are inoperable, perform the following as required by TS 3.3.1, Table 3.3.1-1, Function 5 and ACTIONS A, I and J, refer also to ACTION K and TR 3.3.15:

1. Open reactor trip breakers.

2. Suspend all operations involving positive reactivity changes.

3. Verify shutdown margin is greater than or equal to 1.3% D k/k within one hour and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

4. Use gammametrics source range channels SE NI-60 and SE NI-61 to monitor neutron flux levels in the reactor.

5. Make all reasonable attempts to regain source range instrumentation as quickly as possible.

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 8 of 61

Ú

¿

³ NOTES ³

³ ³

³ o Placing the P-10 bistable in a non-tripped condition below 10% ³

³ power is not possible with power range control power fuses ³

³ removed. The following actions are adequate to ensure the ³

³ margin for safety defined in Technical Specifications. ³

³ ³

³ o Technical Specification allowable value for the P-10 interlock ³

³ is from 6.7% RTP to 13.3% RTP. ³

³ ³

4.13 If in Mode 1 or Mode 2 and P-10 is not in the required state for current plant conditions, perform the following:

(3.1.18) 4.13.1 Stabilize the plant at the current power level.

4.13.2 Contact I&C to initiate trouble shooting and refer to OFN SB-008, INSTRUMENT MALFUNCTIONS.

4.13.3 Reference TS 3.3.1, Table 3.3.1-1, Function 18e; restore P-10 and verify the interlock is in the required state for existing plant conditions within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR be in Mode 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

4.13.4 If power is less than 6.7% and the Power Range Low Power and the Intermediate Range Trips are blocked, then reference TS 3.3.1, Table 3.3.1-1, Functions 2b, 4 and 18e; immediately suspend operations involving positive reactivity additions and reduce Thermal Power to less than P-6 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reference LCO 3.0.3. (3.1.14) 4.13.5 If the P-6 setpoint is reached and source range indication is not restored, then refer to Step 4.12.

(3.1.14) 4.14 Startups (except startup following core reload) will require all four power range channels to be operable independent of Technical Specification requirements until reactor power is greater than 10%.

4.15 If a nuclear instrumentation power range channel is in test, it should be re-instated prior to any planned power reduction to below the P-10 setpoint of 10%.

4.16 In Modes 1 and 2, all reactor coolant loops shall be in operation to satisfy TS 3.4.4.

4.17 Reactor Coolant System pressure shall not exceed 2735 psig as required by TS 2.1.2.

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 9 of 61 4.18 When the reactor is critical above the point of adding heat, loop DTs should be monitored as well as nuclear instrumentation to determine reactor power output. [3.2.6]

4.19 Due to potential feed flow and steam flow measurement inaccuracies, RCS DT should be monitored and compared to nuclear instrumentation indication during power increases.

[3.2.6]

4.20 There are no fuel conditioning restrictions below 40% power.

(3.1.13)

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¿

³ NOTE ³

³ ³

³ Limitations in step 4.21 are mechanical limitations of the ³

³ Reactor Coolant System (RCS). (3.1.15) ³

³ ³

4.21 The rate of power increase shall be limited to the following:

4.21.1 Unit loading between 0 and 15 percent power shall be limited to 0.5% (rated) per minute.

4.21.2 Unit loading between 15 and 40 percent power shall be limited to:

5% (rated) per minute OR

A maximum step increase of 10% (rated) power.

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 10 of 61 4.22 If any steam generator is isolated (MSIV and MFIV closed),

the following applies:

4.22.1 No steam generator should be isolated in Mode 1.

4.22.2 Operation in Mode 2 with steam generator(s) isolated is permissible.

4.22.3 If operation with isolated steam generator(s) is anticipated for longer than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , Plant Manager (or designee's) approval is required.

4.22.4 Operation with isolated steam generator(s) for a prolonged period of time increases the concern for the following:

1. Higher corrosion rates in the steam generators and feedwater train

2. Uneven core power distribution

3. Feedline cracking

4. Nozzle thermal transient/fatigue stresses

5. Increased feedwater cycling (slug flow) 4.22.5 If all four steam generators are isolated, heat removal should be performed by feeding one steam generator from the Auxiliary Feedwater System while steaming the same steam generator through its atmospheric relief valve.

4.22.6 While steaming an isolated steam generator, a small continuous feed flow should be provided to accommodate stable level control and prevent feedline cracking. Intermittent feed should be provided to non-steaming steam generators as required to maintain levels.

4.22.7 If it is desired to maintain water chemistry parameters in the power operation band, blowdown should be in operation on isolated steam generator(s). If it is not desired to maintain water chemistry in the power operation band, blowdown may be initiated to maintain heat-up chemistry parameters.

4.22.8 Chemistry samples of non-steaming isolated steam generators are not representative since little mixing occurs. Chemical additions to adjust chemistry without mixing is also not effective.

4.22.9 Prior to returning an isolated steam generator to normal operation, assure steamline draining and heating is provided.

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 11 of 61 4.23 An isotopic analysis of reactor coolant for iodine must be performed between 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a thermal power change exceeding 15% of rated thermal power within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period to satisfy SR 3.4.16.2.

4.24 Primary to Secondary Leakage Detection radiation monitors are not operable unless they can directly correlate activity to gpd leakage, and can detect leak rates greater than 30 gpd at existing RCS activity levels. Chemistry grab samples must be taken until sufficient RCS activity exists to provide adequate indication of tube leakage. Refer to TR 3.3.18 and BASES.

4.25 A grab sample and analysis of the unit vent is required following reactor shutdown, reactor startup, or thermal power change exceeding 15% of rated thermal power within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period. Refer to AP 07B-003, OFFSITE DOSE CALCULATION MANUAL, Table 3-1 and AP 02-007, CHEMISTRY TURNOVER AND ABNORMAL CONDITIONS GUIDELINES. [3.2.4]

4.26 If a containment purge is in progress, a grab sample and analysis of containment is required following reactor shutdown, reactor startup, or a thermal power change exceeding 15% of rated thermal power within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

Refer to AP 07B-003, OFFSITE DOSE CALCULATION MANUAL, Table 3-1 and AP 02-007, CHEMISTRY TURNOVER AND ABNORMAL CONDITIONS GUIDELINES. [3.2.4]

4.27 Control rod drive mechanism (CRDM) cooling fans shall be operated as follows: (3.1.16) 4.27.1 When RCS temperature is greater than 350°F, the following applies:

1. At least two CRDM fans must be running.

2. If only one CRDM fan is running, the following restrictions apply:

a. Nuclear Plant Information System (NPIS) points GNT0045 and GNT0046 shall be monitored and logged at least once per shift. If GNT0045 and GNT0046 are not available, local temperature monitoring can be performed.

b. Nuclear Plant Information System (NPIS) points GNT0045 and GNT0046 or local temperature monitoring shall not exceed 165°F.

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 12 of 61 4.28 The minimum requirements for hydrogen mixing fan and containment cooler operation in Mode 1, Mode 2 and Mode 3 at normal operating pressure and temperature are as follows:

[3.2.9]

4.28.1 If containment temperature is greater than or equal to 95°F, all eight fans (four hydrogen mixing fans and four containment coolers) should be running in fast speed.

4.28.2 If containment temperature is less than 95°F, seven of the eight fans (four hydrogen mixing fans and four containment coolers) should be running in fast speed or slow speed.

4.28.3 If the minimum requirements for operating fans can NOT be met, a work request must be expedited to System Engineering within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for evaluation.

4.29 When the main turbine shaft is rotating, the Generator Seal Oil System shall be in operation.

4.30 One condenser vacuum pump is normally in service. If either of the following conditions are satisfied, a second condenser vacuum pump should be started:

4.30.1 Circulating water temperature is greater than 80°F.

4.30.2 Condenser in-leakage is greater than 35 scfm.

4.31 As service water cooling requirements change, monitor and maintain backpressure using SYS EA-120, SERVICE WATER SYSTEM STARTUP.

4.32 Operation of feedwater preheating through AB PCV-359 and AB PCV-360 is for use between 0% to 25% thermal power only.

Valves AB-V353 through AB-V358 and AB PCV-359 and AB PCV-360 shall remain closed above 25% thermal power.

4.33 If Reactor Engineering provides recommendations that affect reactivity, then the Shift Manager shall approve the recommendations. Exceptions to this guidance are evolutions performed using an approved procedure, such as low-power physics testing. The Shift Manager is responsible for controlling the reactor core. [3.2.12]

4.34 The Shift Manager shall ensure clear communication of advice from Reactor Engineering to the Control Room Operators.

[3.2.12]

4.35 The Shift Manager shall ensure sufficient Reactor Engineering support during selected evolutions, such as reactor startups, power ascensions or other unexpected core behaviors.

[3.2.12]

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 13 of 61 INIT/DATE 5.0 PREREQUISITES 5.1 At least one Senior and one Reactor Operator are present in the Control Room as required by Technical Specifications Administrative Controls 5.1.2 and 5.2.2 and TR 5.2.1. /

5.2 The plant is in one of the following conditions:

Mode 3 with Tavg and RCS pressure at no-load values. /

OR

Mode 2 /

OR

Mode 1 with power level less than or equal to 30% /

5.3 IF containment has been opened, THEN containment final inspection has been completed using STN EJ-002, CONTAINMENT INSPECTION. /

5.4 Both source range channel High Voltage Manual Control Switches are in the Normal position:

o SE NI NORMAL /

5.5 Nuclear instrumentation is available as follows:

5.5.1 NR-45 recorder is in service. /

5.5.2 All indicators associated with the nuclear instrumentation system are in service. /

5.5.3 Both source range channels are operable.

o SE NI OPERABLE /

5.5.4 Both intermediate range channels are operable.

o SE NI OPERABLE /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 14 of 61 INIT/DATE 5.5.5 All power range channels are operable. (One channel may be marked N/A if used for Physics Testing). (3.1.20) o SE NI OPERABLE /

o SE NI OPERABLE /

5.5.6 IF this is the first startup after refueling OR power range NI gains have been adjusted down as a result of a part power calorimetric performed at less than 45%

RTP, THEN ensure power range high flux level reactor trip setpoints have been reduced to £80% per STS IC-932, POWER RANGE NEUTRON HIGH FLUX TRIP SETPOINT ADJUSTMENT.

(3.1.10) /

5.6 Performance of STS RE-004, SHUTDOWN MARGIN DETERMINATION, shows the following:

5.6.1 Shutdown margin is greater than 1.3%. /

5.6.2 Shutdown rods may be withdrawn without reaching criticality. /

É

º CAUTION º

º º

º If this is the initial startup after refueling, do not withdraw º

º shutdown banks until directed by Reactor Engineering. Refer to º

º RXE 01-002, RELOAD LOW POWER PHYSICS TESTING. º

º º 1/4 5.7 IF shutdown rods have NOT been withdrawn, THEN perform the following:

5.7.1 Prior to closing the reactor trip breakers, ensure the following are current:

1. STS IC-211A, ACTUATION LOGIC TEST TRAIN A SOLID STATE PROTECTION SYSTEM. /

2. STS IC-211B, ACTUATION LOGIC TEST TRAIN B SOLID STATE PROTECTION SYSTEM. /

3. STS IC-215, TRIP ACTUATING DEVICE OPERATIONAL TEST OF MANUAL REACTOR TRIP, TRIP AND BYPASS BREAKER UV/SHUNT TRIP, TURBINE TRIP ON REACTOR TRIP AND

P4. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 15 of 61 INIT/DATE

4. Ensure the RCS loop operability and operation requirements are met.

TS 3.4.5. /

5. Ensure one of the following conditions is met: (3.1.20)

All power range nuclear instrument channels are operable, OR three channels are operable with one being used for Physics Testing. /

OR

RCS boron concentration is adequate to maintain the reactor shutdown under all rods out conditions. /

6. IF this is the first startup after refueling OR power range NI gains have been adjusted down as a result of a part power calorimetric performed at less than 45% RTP, THEN ensure power range high flux level reactor trip setpoints have been reduced to £80% per STS IC-932, POWER RANGE NEUTRON HIGH FLUX TRIP SETPOINT ADJUSTMENT.

(3.1.10, 3.1.20) /

7. Verify DRPI subsystem indicates all rods are on the bottom prior to making the Rod Control System capable of rod withdrawal. TR 3.1.7. /

5.7.2 Ensure shutdown margin is calculated for shutdown banks withdrawn using STS RE-004, SHUTDOWN MARGIN DETERMINATION. /

5.7.3 While withdrawing shutdown rods, ensure the following: (3.1.7)

1. The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System are operable and individual rod position shall be within 12 steps of their group step counter demand position (except in the traveling region). TS 3.1.4 and TS 3.1.7. and TR 3.1.7. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 16 of 61 INIT/DATE

É

º CAUTION º

º º

º Criticality must be anticipated anytime shutdown or control rods º

º are being withdrawn. º

º º 1/4 5.7.4 Place Rod Control System in operation using SYS SF-120, ROD CONTROL SYSTEM OPERATION. /

5.7.5 (r) Withdraw shutdown banks using SYS SF-120, ROD CONTROL SYSTEM OPERATION. /

5.8 Control rods are fully inserted and the shutdown rods are fully withdrawn /

5.9 Moveable incore detection system is operable as required by Reactor Engineering. /

5.10 IF it is desired to transfer loads to the unit auxiliary transformer, THEN align by performing CKL MA-132, UNIT AUXILIARY TRANSFORMER XMA02 LINEUP FOR OPERATION. /

5.11 The main transformers are aligned in accordance with CKL MA-131, MAIN TRANSFORMER XMA01A/B/C LINEUP OPERATION. /

5.12 Generator is properly aligned to switchyard as follows:

5.12.1 Generator output breakers are open.

o 345 OPEN /

5.12.2 Locally ensure main generator switchyard air break disconnects are closed.

o 345-51 - CLOSED /

o 345-53 - CLOSED /

o 345-61 - CLOSED /

o 345-63 - CLOSED /

5.12.3 Generator air break switch is closed.

o 345 CLOSED /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 17 of 61 INIT/DATE 5.12.4 Generator transformer primary and secondary 94 differential lockout relays in switchyard are reset (amber lamp lit).

o GEN S/U XFMR PRIMARY DIFF MTR (Main Trip Relay) - RESET /

o GEN S/U SECONDARY DIFF MTR (Main Trip Relay) - RESET /

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¿

³ NOTE ³

³ ³

³ Steam line drain valves automatically open and remain open on ³

³ high condensate level in the main steam low point drains. Normal ³

³ RCS temperature can be maintained by manually reclosing these ³

³ valves. ³

³ ³

5.13 Maintain the following steam line drain valves closed:

o AB LV-50, MAIN STM HDR TO STM DUMPS DR LEG ST-05 BYPASS VLV - CLOSED /

o AB LV-51, MAIN STM HDR TO STM DUMPS DR LEG ST-06 BYPASS VLV - CLOSED /

o AB LV-52, MAIN STM HDR TO STM DUMPS DR LEG ST-07 BYPASS VLV - CLOSED /

o AB LV-53, MAIN STM HDR TO STM DUMPS DR LEG ST-08 BYPASS VLV - CLOSED /

o FC HV-3, SG FWP TURB A MAIN STEAM LOW POINT DR VLV

- CLOSED /

o FC HV-103, MFW PUMP TURB B HIGH PRESS DRAIN -

CLOSED /

5.14 RCS temperature is being maintained between 552°F and 562°F using steam dump control system or atmospheric steam relief valves. /

5.15 RCS pressure is being maintained between 2220 psig and 2250 psig by pressurizer heaters and spray valves. /

5.16 Pressurizer level is being maintained between 25%

and 29% with normal letdown flow and charging flow in auto. /

5.17 Feedwater preheating is in service using SYS AE-200, FEEDWATER PREHEATING DURING PLANT STARTUP AND SHUTDOWN. [3.2.8 and 3.2.15] /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 18 of 61 INIT/DATE 5.18 Main feedwater regulating valves have been verified fully closed by performance of the following:

5.18.1 Direct I&C to perform the following:

1. On RL006, ensure main feedwater regulating valves indicate closed. /

2. Monitor valve stem movement while isolating air to valve positioners. /

3. Restore air to valve positioners. /

5.18.2 IF valve stem movement occurred, THEN direct I&C to perform a setup on the valve. /

5.19 Reactor makeup is in auto and set at blended flow greater than or equal to existing RCS boron concentration using SYS BG-200, REACTOR MAKEUP CONTROL SYSTEM NORMAL OPERATION. /

5.20 Auxiliary Steam System in service supplying miscellaneous plant loads. /

5.21 IF reactor is being restarted following a reactor trip, THEN ensure appropriate sections of AP 20-002, POST-TRIP REVIEW, are complete and approval for restart has been granted. /

5.22 Secondary corrosion removal is in progress as follows:

5.22.1 Maximum allowable flow through on line condensate demineralizers has been established as determined by Chemistry. /

5.22.2 On line condensate demineralizer differential pressures are being monitored. /

5.22.3 Condensate demineralizers are being swapped as required by Chemistry. /

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¿

³ NOTE ³

³ ³

³ If directed by the SM or CRS, the Steam Generator Blowdown Regen ³

³ Heat Exchanger may be bypassed to minimize iron transport to the ³

³ Steam Generators. ³

³ ³

5.23 Steam generator blowdown system is in service with the Regen Heat Exchanger Bypassed per SYS BM-128, SGBD COMPONENT OPERATIONS, as directed by the Shift

Manager or Control Room Supervisor. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 19 of 61 INIT/DATE 5.24 IF required Primary to Secondary Leakage Detection Instrumentation is NOT operable, THEN verify that Chemistry is taking Steam Generator grab samples at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months until required instrumentation is operable. Refer to TR 3.3.18 and BASES. /

5.25 IF desired, THEN close BM-V185, SG BLOWDOWN REGENERATIVE HX CONDENSATE OUTLET TO HTR DRAIN TK ISO to prevent overfilling the Heater Drain Tank. /

5.26 RCS hydrogen concentration is greater than or equal to 15 cc/kg. /

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¿

³ NOTE ³

³ ³

³ Step 5.27 is discretionary and shall be performed if directed by ³

³

³ the SM or CRS to minimize iron transport. ³

³

³ ³

É

º CAUTION º

º º

º The air supply valve shall be gradually closed in the next step º

º to avoid potential water hammer. [3.2.2] º

º º 1/4 5.27 IF desired, THEN locally close/check closed instrument air supply isolation to high pressure feedwater heater's 6A and 6B level control valves.

o AF LV-013, HP HTR 6A TO HTR DRN TK LEV CV - FAILED CLOSED /

o AF LV-045, HP HTR 6B TO HTR DRN TK LEV CV - FAILED CLOSED /

5.28 An individual has been designated as Management Oversight of this procedure as required by AI 15C-006, CONDUCT OF INFREQUENTLY PERFORMED TESTS OR EVOLUTIONS. (3.1.17) /

5.29 An infrequently performed tests or evolutions briefing has been completed by Division Manager, Call Superintendent, Outage Shift Manager, or higher as required by AI 15C-006, CONDUCT OF INFREQUENTLY PERFORMED TESTS OR EVOLUTIONS. (3.1.17) /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 20 of 61 INIT/DATE 6.0 PROCEDURE

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¿

³ NOTES ³

³ ³

³ o A forced flow RVLIS indication outside of the band of 100% ³

³

³ +/-4.0% when the unit is at 0% RTP and NOP/NOT with 4 RCPs ³

³

³ running requires that the channel be declared inoperable. ³

³

³ ³

³ o A forced flow RVLIS indication outside of the band of 100% +/-2% ³

³

³ when the unit is at 0% RTP and NOP/NOT with 4 RCPs running ³

³

³ must be adjusted to read 100% +/-0.5%. ³

³

³ ³

6.1 IF the unit is at 0% RTP, NOP/NOT with 4 RCPs

³ running following a mid-cycle shutdown, THEN perform

³ the following: (3.1.21)

³ 6.1.1 Check RVLIS indications:

³ o Verify BB LI-1312, REACTOR VESSEL WATER

³ LEVEL FORCED FLOW RANGE is reading 100%

³

+/-2.0%. /

³ AND o Verify BB LI-1322, REACTOR VESSEL WATER

³ LEVEL FORCED FLOW RANGE is reading 100%

³

+/-2.0%. /

³ 6.1.2 IF either RVLIS channel is reading outside

³ the allowed tolerance, THEN initiate

³ corrective actions. /

³

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 21 of 61 INIT/DATE

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¿

³ NOTES ³

³ ³

³ o It is desired to delay operation of the Heater Drain Pumps ³

³ until 60% power to minimize iron transport to the Steam ³

³ Generators. However a heater drain pump may be operated as ³

³ required to maintain heater drain tank level and minimize ³

³ water hammer as directed by Shift Manager or Control Room ³

³ Supervisor. ³

³ ³

³ o In order to minimize iron transport to the Steam Generators, ³

³ the #6 HP Heaters Drains will be routed to the Condenser until ³

³ approximately 60% power ³

³ ³

6.2 IF this is NOT initial startup after refueling, THEN adjust RCS boron concentration as follows:

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¿

³ NOTE ³

³ ³

³ If performing a startup with a positive moderator temperature ³

³ coefficient, the estimated critical position (ECP) should be ³

³ calculated for approximately 100 steps on control bank D. ³

³ ³

6.2.1 Determine estimated critical boron concentration using STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 22 of 61 INIT/DATE

É

º CAUTIONS º

º º

º o While subcritical, minimize the addition of positive º

º reactivity by more than one controlled method at a time. º

º º

º o Criticality shall be anticipated anytime the shutdown or º

º control rods are being withdrawn, or boron dilution operations º

º are in progress. º

º º

º o If during any step involving boron dilution, the source range º

º count rate increases by a factor of two, dilution shall be º

º stopped immediately and suspended until core reactivity has º

º been evaluated. º

º º 1/4 6.2.2 (r)IF RCS boron concentration is NOT within acceptable range from STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION, THEN perform the following:

1. Ensure both groups of PZR backup heaters are energized. /

2. Start boration or dilution to estimated critical concentration. /

3. Obtain boron samples every 30 minutes while adjusting boron concentration. /

4. WHEN boron concentration adjustment has been completed for at least 30 minutes, THEN obtain final boron sample and ensure boron concentration is within acceptable boron concentration range from STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION. /

6.3 Verify systems are operable for entry into Mode 2 as follows:

6.3.1 Contact Chemistry to determine if Lithium addition is required. /

6.3.2 Contact Health Physics to update Containment Radiation postings. /

6.3.3 Select both source range channels to record on NIS recorder NR-45.

o SE HS-1 /

o SE HS-2 /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 23 of 61 INIT/DATE 6.3.4 Place NR-45 recorder speed in LO-9 (30"/hr). /

6.3.5 Ensure Mode 2 requirements are complete for the following:

1. STS CR-001, SHIFT LOG FOR MODES 1, 2,

& 3 /

2. STS ML-001, MONTHLY SURVEILLANCE LOG /

6.3.6 Contact Scaffold Group to ensure all scaffolding required to be removed prior to Mode 2 has been removed. /

6.3.7 Ensure Shift Manager has reviewed the following for entry into Mode 2: [3.2.10 and 3.2.11]

1. Clearance Order Log /

2. AP 21G-001, CONTROL OF LOCKED COMPONENT STATUS /

3. Temporary Modification Log /

4. Breach Authorization Log /

a. Ensure all compensatory measures verified. /

5. Equipment Out-Of-Service Log /

6. Work Request and Work Order Mode restraints /

7. Mode Change Checklist - Mode 3 to 2

a. All surveillances on the checklist are current. /

b. Completed checklist attached to this procedure. /

6.3.8 Ensure a Reactor Engineer is present in Control Room. /

6.3.9 Ensure Shift Manager has briefed the operating shift on the additional Technical Specifications that will become applicable in Mode 2 using ATTACHMENT A, TECHNICAL SPECIFICATIONS WHICH BECOME APPLICABLE IN MODE 2. [3.2.10] /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 24 of 61 INIT/DATE 6.3.10 Ensure Manager Operations or Designee has reviewed plant status and procedural requirements are satisfied to proceed with the Mode change. [3.2.11] /

Signature, Manager Operations or Designee 6.4 Inform NRC Resident Inspector that the reactor is being taken critical. /

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¿

³ NOTE ³

³ ³

³ If a problem develops during the startup and the startup must be ³

³ aborted, alarm 00-057A, SR FLUX DOUBLED, should be re-instated ³

³ prior to returning to GEN 00-002, COLD SHUTDOWN TO HOT STANDBY, ³

³ or GEN 00-006, HOT STANDBY TO COLD SHUTDOWN. ³

³ ³

6.5 Block alarm 00-057A, SR FLUX DOUBLED as follows:

6.5.1 Depress BLOCK button on red train SR Doubled Bypass/Reset switch.

o SE HS BLOCK DEPRESSED /

6.5.2 Check annunciator 00-057B, SR FLUX DOUBLED BYP/BLOC - LIT /

6.5.3 Depress BLOCK button on yellow train SR Doubled Bypass/Reset switch.

o SE HS BLOCK DEPRESSED /

6.5.4 Check annunciator 00-057B, SR FLUX DOUBLED BYP/BLOC - REFLASHES /

6.6 IF this is the initial startup after refueling, THEN direct Reactor Engineering to perform RXE 01-002, RELOAD LOW POWER PHYSICS TESTING. /

6.7 Ensure reactor coolant average temperature is greater than or equal to 551°F as required by TS 3.4.2. /

6.8 IF desired, THEN start main feedwater pump warmup using SYS AE-120, MAIN FEEDWATER PUMPS WARMUP AND PRESTART CHECKOUT, while continuing with this procedure. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 25 of 61 INIT/DATE

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¿

³ NOTE ³

³ ³

³ Main Turbine Warmup per SYS AC-120, MAIN TURBINE GENERATOR ³

³ STARTUP maybe suspended as necessary to support temperature ³

³ requirements for RXE 01-002, RELOAD LOW POWER PHYSICS TESTING. ³

³ ³

6.9 IF desired, THEN start main turbine warmup using SYS AC-120, MAIN TURBINE GENERATOR STARTUP, while continuing with this procedure. /

6.10 (r)IF the reactor has been shut down for less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months AND the number of hours to actual criticality differs from the estimated time of criticality by more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , THEN re-calculate estimated critical position using STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION, to account for Xenon changes. /

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¿

³ NOTE ³

³ ³

³ If this is the initial startup after refueling, the estimated ³

³ critical position will be determined by RXE 01-002, RELOAD LOW ³

³ POWER PHYSICS TESTING. TS 3.1.8 allows suspension of TS 3.1.6 ³

³ during physics tests and Step 6.11 may be marked N/A. ³

³ ³

6.11 To satisfy SR 3.1.6.1, verification that critical control rod position is within insertion limits must be completed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving criticality by satisfactory completion of STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 26 of 61 INIT/DATE

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¿

³ NOTES ³

³ ³

³ o A 1/M plot will be generated for every startup. [3.2.7] ³

³ ³

³ o If this is the initial startup after refueling, Reactor ³

³ Engineering will perform the 1/M plot per RXE 01-002, RELOAD ³

³ LOW POWER PHYSICS TESTING, and section 6.12 may be N/A'd. ³

³ ³

6.12 Establish initial conditions for 1/M plot as follows:

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¿

³ NOTE ³

³ ³

³ NPIS computer points for source range flux may be used for ³

³ plotting 1/M. ³

³ ³

6.12.1 Record initial neutron flux levels:

1. Source range N-31 ________________CPS /

2. Source range N-32 ________________CPS /

6.12.2 Record the following information on 1/M plot (FIGURE 1):

1. Initial count rate (Ci) /

2. Maximum rod height from ECP /

3. Minimum rod height from ECP /

4. Estimated Critical Position from ECP /

6.13 Ensure activities that could distract the Supervisor and operators involved with reactor startup during approach to criticality, such as shift turnover and surveillance testing, are not in progress. [3.2.7] /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 27 of 61 INIT/DATE 6.14 During reactor startup, attempt to detect errors in estimated critical position and other instrumentation by monitoring the following indications: [3.2.6, 3.2.7] /

o NIS recorder (NR-45) o Source range indication o Source range startup rate o Source range audio count rate o Intermediate range indication o Intermediate range startup rate o NIS alarms o NIS permissives o Other appropriate indications 6.15 Obtain permission from Shift Manager or Control Room Supervisor to commence withdrawal of control rod banks. /

É

º CAUTIONS º

º º

º o Criticality must be achieved within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of completing º

º STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION, to º

º satisfy SR 3.1.6.1. During the initial startup after º

º refueling, TS 3.1.8 allows suspension of this requirement º

º during physics testing. º

º º

º o Criticality shall be anticipated anytime control rods are º

º being withdrawn or boron dilution is in progress. º

º º

º o DO NOT EXCEED A STABLE STARTUP RATE of 1.0 decade per minute º

º (DPM) or a transient startup rate of 1.5 DPM. º

º º

º o When the reactor is subcritical, minimize the addition of º

º positive reactivity by more than one controlled method at a º

º time. º

º º

º o When positioning control rods during startup, conservative º

º actions and compliance with reactor startup instructions is º

º required. [3.2.7] º

º º

º o Maintain all RCS loop Tavg temperature greater than or equal º

º to 551°F, minimum temperature for criticality. TS 3.4.2. º

º º 1/4 6.16 Inform plant personnel by making the following announcement twice over plant public address system; "ATTENTION ALL PLANT PERSONNEL, COMMENCING A REACTOR STARTUP". /

6.17 Ensure LTDN DIVERT TO VCT & RHT is in auto.

o BG HIS-112A - AUTO /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 28 of 61 INIT/DATE 6.18 Defeat source range high flux at shutdown as follows:

6.18.1 At NI cabinets, block high flux at shutdown alarm on both source range channels.

o N-31 High Flux At Shutdown - BLOCKED /

o N-32 High Flux At Shutdown - BLOCKED /

6.18.2 Check annunciator 00-065B, SR HI FLUX AT S/D BLOC - LIT. /

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¿

³ NOTES ³

³ ³

³ o Step 6.19 shall be reviewed prior to performance. ³

³ ³

³ o If a dropped rod event occurs during the performance of this ³

³ procedure which causes the reactor to go subcritical, all ³

³ control banks shall be re-inserted and the startup ³

³ re-performed. [3.2.3] ³

³ ³

³ o Withdrawing control rod banks is a Mode change. ³

³ ³

6.19 Commence a reactor startup:

6.19.1 Ensure Rod Bank Auto/Manual Selector switch is in manual.

o SE HS MANUAL /

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¿

³ NOTE ³

³ ³

³ If this is the initial startup following refueling, withdrawal ³

³ of control banks is not expected to take the reactor critical, ³

³ but criticality must be anticipated. ³

³ ³

6.19.2 (r)Withdraw control rod banks in manual to take the reactor critical while continuing with this procedure. /

6.19.3 WHEN Control Bank A starts to withdraw, THEN perform the following:

1. In Control Room log, record date and time the unit entered Mode 2. /

2. Announce entry into Mode 2 on the plant page system. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 29 of 61 INIT/DATE 6.19.4 While withdrawing control rods, ensure the following: (3.1.7)

1. All individual indicated rod positions shall be within 12 steps of their group step counter demand position and shall be within the insertion, sequence and overlap limits specified in the COLR in accordance with TS 3.1.4, 3.1.5 and 3.1.6. /

6.19.5 Stop every 50 steps during rod withdrawal and perform the following:

1. Check for proper rod alignment and bank overlap. /

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¿

³ NOTE ³

³ ³

³ If this is the initial startup after refueling, Reactor ³

³ Engineering will perform the 1/M plot per RXE 01-002, RELOAD LOW ³

³ POWER PHYSICS TESTING, and Step 6.19.5.2 may be N/A'd. ³

³ ³

2. Estimate critical rod position based on 1/M plot using FIGURE 1, 1/M PLOT. /

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¿

³ NOTE ³

³ ³

³ If this is the initial startup after refueling, the minimum and ³

³ maximum rod heights are not applicable and steps 6.19.5.3)a ³

³ through 6.19.5.3)d may be N/A'd. ³

³ ³

3. IF neutron flux has more than doubled its initial value AND 1/M plot predicts criticality below minimum rod height or above maximum rod height from ECP, THEN perform the following: [3.2.7]

a. Inform Reactor Engineering. /

b. Maintain stable reactor conditions. /

c. Ensure control rod positions and RCS boron concentration are correct. /

d. Recalculate estimated critical

position using STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 30 of 61 INIT/DATE

e. IF Reactor Engineering determines that the reactor will go critical below zero power rod insertion limit (Bank C at 46 steps), THEN perform the following:

1) (r)Immediately insert all control banks. /

2) (r)Emergency borate to reestablish required shutdown margin using OFN BG-009, EMERGENCY BORATION. /

3) WHEN reactor power is stable in the source range, THEN perform the following:

a) At NI cabinets, unblock high flux at shutdown alarm on both source range channels.

o N-31 High Flux At Shutdown

- NORMAL /

o N-32 High Flux At Shutdown

- NORMAL /

b) Check annunciator 00-065B, SR HI FLUX AT S/D BLOC -

CLEAR /

c) Depress RESET button on SR Doubled Bypass/Reset switch for both trains.

o SE HS RESET DEPRESSED /

d) Check annunciator 00-057B, SR FLUX DOUBLED BYP/BLOC -

CLEAR /

e) Record a detailed description in Control Room log. /

f) Proceed as directed by Reactor Engineering. /

6.19.6 (r)IF this is the initial startup after refueling, THEN dilute to criticality per RXE 01-002, RELOAD LOW POWER PHYSICS TESTING. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 31 of 61 INIT/DATE

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¿

³ NOTE ³

³ ³

³ Steps 6.20, 6.21 and 6.22 should be performed concurrently. ³

³ ³

6.20 WHEN the reactor is critical, THEN perform the following:

É

º CAUTION º

º º

º If criticality was achieved above the zero power rod insertion º

º limit but subsequent plant conditions require control banks to º

º be inserted below the rod insertion limit, then emergency borate º

º as necessary to restore control banks above the rod insertion º

º limit using OFN BG-009, EMERGENCY BORATION. º

º º 1/4 6.20.1 IF criticality is inadvertently achieved below zero power rod insertion limit (Bank C at 46 steps), THEN perform the following:

1. (r)Immediately insert all control banks. /

2. (r)Emergency borate to reestablish required shutdown margin using OFN BG-009, EMERGENCY BORATION. /

3. WHEN reactor power is stable in the source range, THEN perform the following:

a. At NI cabinets, unblock high flux at shutdown alarm on both source range channels.

o N-31 High Flux At Shutdown -

UNBLOCKED /

o N-32 High Flux At Shutdown -

UNBLOCKED /

b. Check annunciator 00-065B, SR HI FLUX AT S/D BLOC - CLEAR /

c. Depress RESET button on SR Doubled Bypass/Reset switch for both trains.

o SE HS RESET DEPRESSED /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 32 of 61 INIT/DATE

d. Check annunciator 00-057B, SR FLUX DOUBLED BYP/BLOC - CLEAR /

e. Record a detailed description in Control Room log. /

f. Proceed as directed by Reactor Engineering. /

6.20.2 In Control Room log, record date and time of criticality. /

6.20.3 Announce reactor criticality on the plant page system. /

É

º CAUTION º

º º

º DO NOT EXCEED A STABLE STARTUP RATE of 1.0 decade per minute º

º (DPM) or a transient startup rate of 1.5 DPM. º

º º 1/4 6.20.4 (r)Adjust control rod height as necessary to establish desired startup rate. /

6.20.5 Direct Chemistry to sample RCS for boron concentration. /

6.20.6 Ensure the scaler/timer is turned off by placing the power toggle switch to off.

(3.1.11) /

6.21 WHEN the intermediate range indicates between 1x10-10 amps and 1x10-11 amps, THEN perform the following:

6.21.1 Ensure both intermediate range channels are indicating properly by a channel comparison.

o NI OPERATING PROPERLY /

6.21.2 Select higher reading intermediate range channel for recording on NIS recorder NR-45. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 33 of 61 INIT/DATE

É

º CAUTION º

º º

º There is only one-half decade overlap between the P-6 permissive º

º block and source range high flux reactor trip. Delay in blocking º

º the source range could initiate a reactor trip at 105 CPS. º

º º 1/4

Ú

¿

³ NOTE ³

³ ³

³ P-6 status light is located on SB069, 16 down, 4 across. ³

³ ³

6.22 WHEN intermediate range permissive P-6 light is lit, THEN block source range high flux trip as follows:

(3.1.14) 6.22.1 Simultaneously depress both source range A and source range B block pushbuttons.

o SE HS-5 /

o SE HS-10 /

6.22.2 Ensure source range trip is blocked:

1. SR trip A block lit.

o SB069, 15 down, 1 across - LIT /

2. SR trip B block lit.

o SB069, 15 down, 2 across - LIT /

3. Annunciator 00-077E, SR HI VOLT FAIL -

LIT. /

6.22.3 WHEN source range trip is blocked, THEN select the second intermediate range channel for recording on NIS recorder NR-45. /

6.23 WHEN Intermediate range permissive P-6 light is lit, THEN perform the following:

6.23.1 At NI cabinets, unblock high flux at shutdown alarm on both source range channels.

o N-31 High Flux At Shutdown - NORMAL /

o N-32 High Flux At Shutdown - NORMAL /

6.23.2 Check annunciator 00-065B, SR HI FLUX AT S/D BLOC - CLEAR. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 34 of 61 INIT/DATE 6.24 (r)Adjust control rods as necessary to stabilize reactor neutron level at about 10-8 amps on the intermediate range. /

6.25 WHEN reactor neutron level is stable at about 10-8 amps on the intermediate range, THEN perform the following:

6.25.1 Record actual critical rod height:

Bank__________ Steps___________ /

6.25.2 Record actual critical rod height in the following: N/A for initial startup following refueling.

o ECP form /

o Control Room log /

6.25.3 Record estimated critical rod position based on last 1/M data point plotted prior to criticality. N/A for initial startup following refueling.

Bank__________ Steps___________ /

6.25.4 IF reactor was shutdown for less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , THEN check that criticality was achieved within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of estimated time of criticality from STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION. /

Ú

¿

³ NOTE ³

³ ³

³ If this is the initial startup after refueling, the estimated ³

³ critical position will be determined by RXE 01-002, RELOAD LOW ³

³ POWER PHYSICS TESTING. TS 3.1.8 allows suspension of TS 3.1.6 ³

³ during physics tests and Step 6.25.5 may be marked N/A. ³

³ ³

6.25.5 To satisfy SR 3.1.6.1, verify that criticality was achieved within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the estimated time of criticality by satisfactory completion of STS RE-002, DETERMINATION OF ESTIMATED CRITICAL POSITION. /

6.25.6 IF annunciator 00-081D, ROD BANK LO LIMIT, is lit AND critical RCS boron concentration sample has been taken, THEN borate and withdraw control rods, as necessary, to

establish critical rod height above rod bank low limit. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 35 of 61 INIT/DATE 6.26 WHEN all shutdown and control rods have been withdrawn at least 10 steps, THEN completion of SR 3.1.4.2 may be documented as follows:

6.26.1 Complete a Surveillance Procedure Credit Cross-Reference And Review sheet for STS SF-001, CONTROL AND SHUTDOWN ROD OPERABILITY VERIFICATION, as required by AP 29B-003, SURVEILLANCE TESTING. /

6.26.2 Use a surveillance commenced time corresponding to the time shutdown banks were withdrawn. /

6.26.3 Route to Surveillance Coordinator. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 36 of 61 INIT/DATE

É

º CAUTIONS º

º º

º o The motor driven startup main feed pump capability is limited º

º to around 230,000 lbs/hr (about 1.0% power). Steam generator º

º levels and blowdown rates should be carefully monitored until º

º a steam driven main feed pump is in service. º

º º

º o To minimize S/G level transients, reactor power changes should º

º be made slowly until main feedwater regulating valves are in º

º automatic. [3.2.14] º

º º 1/4

Ú

¿

³ NOTES ³

³ ³

³ o With a negative MTC, as reactor power increases to the point ³

³ of adding heat, startup rate indication will decrease to zero ³

³ as steam dumps open to maintain pressure. ³

³ ³

³ o With a positive MTC, as reactor power increases to the point ³

³ of adding heat, startup rate indication will remain constant ³

³ and power will continue to increase as steam dumps open to ³

³ maintain pressure. ³

³ ³

³ o All individual indicated rod positions shall be within 12 ³

³ steps of their group step counter demand position and shall be ³

³ within the insertion, sequence and overlap limits specified in ³

³ the COLR in accordance with TS 3.1.4, 3.1.5 and 3.1.6. ³

³ ³

³ o When the reactor is critical above the point of adding heat, ³

³ loop DTs should be monitored as well as nuclear ³

³ instrumentation to determine reactor output. [3.2.6] ³

³ ³

6.27 Increase reactor power to 0.5% as follows:

6.27.1 Ensure steam dump valves being used for heat sink are adjusted to maintain Tavg between 552°F and 562°F:

Steam header pressure control, AB PK-507 /

OR

Atmospheric relief valve controllers /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 37 of 61 INIT/DATE

É

º CAUTION º

º º

º DO NOT EXCEED A STABLE STARTUP RATE of 1.0 decade per minute º

º (DPM) or a transient startup rate of 1.5 DPM. º

º º 1/4 6.27.2 (r)Adjust control rod height, as necessary, to establish desired startup rate. /

6.27.3 Allow steam dumps or atmospheric relief valves to open until reactor power reaches 0.5%. /

6.27.4 Reduce or stop steam generator blowdown, as necessary, to maintain sufficient feedwater flow capability. /

6.27.5 (r)Adjust control rod height, as necessary, to maintain reactor power stable between 0.5% and 1.0%. /

6.27.6 WHEN reactor power is stable, THEN perform the following:

1. Select highest reading power range channel for recording on NIS recorder NR-45. /

2. Place NR-45 recorder speed in LO-0 (1"/hr). /

6.28 Place one main feedwater pump in service as follows:

6.28.1 Start a second condensate pump using SYS AD-120, CONDENSATE SYSTEM STARTUP AND CLEANUP. /

Ú

¿

³ NOTE ³

³ ³

³ When main feedwater pumps are reset, startup drains will open ³

³ requiring increased feed flow to the steam generators. ³

³ ³

6.28.2 Ensure both main feedwater pumps are reset:

[3.2.5 and 3.2.13]

1. FC HIS WHITE LIGHT LIT /

Verified /

2. FC HIS-118 - WHITE LIGHT LIT /

Verified /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 38 of 61 INIT/DATE 6.28.3 Start one main feedwater pump using SYS AE-121, TURBINE DRIVEN MAIN FEEDWATER PUMP STARTUP. /

6.28.4 WHEN one main feedwater pump is in service, THEN shutdown startup feedwater source as follows:

1. IF startup feedwater pump is running, THEN shut down startup feedwater pump using SYS AE-321, STARTUP MAIN FEEDWATER PUMP SHUTDOWN. /

2. IF any auxiliary feedwater pumps are running, THEN perform the following:

a. Shutdown auxiliary feedwater pumps using SYS AL-120, FEEDING STEAM GENERATORS WITH A MOTOR DRIVEN OR TURBINE DRIVEN AFW PUMP. /

b. IF turbine driven AFW pump was previously running, THEN ensure turbine driven AFW pump governor setting is between 3850 rpm and 3900 rpm. /

Ú

¿

³ NOTE ³

³ ³

³ When the limitorque operators on motor driven AFW pump discharge ³

³ valves are in the closed position, the motor field remains ³

³ energized causing unnecessary wear on the valve actuator. To ³

³ prolong the life of these valves, it is necessary to maintain ³

³ the valves open as much as possible. ³

³ ³

3. Ensure all motor driven AFW pump discharge valves are full open with joystick in detent open position.

o AL HK-7A for S/G A - DETENT OPEN /

o AL HK-9A for S/G B - DETENT OPEN /

o AL HK-11A for S/G C - DETENT OPEN /

o AL HK-5A for S/G D - DETENT OPEN /

4. Ensure all turbine driven AFW pump discharge valves are full open with joystick in detent open position.

o AL HK-8A for S/G A - DETENT OPEN /

o AL HK-10A for S/G B - DETENT OPEN /

o AL HK-12A for S/G C - DETENT OPEN /

o AL HK-6A for S/G D - DETENT OPEN /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 39 of 61 INIT/DATE 6.28.5 Ensure both AFP ESFAS BLOC switches are placed in permit.

[3.2.1, 3.2.5 and 3.2.13]

1. FC HS IN PERMIT /

Verified /

2. FC HS IN PERMIT /

Verified /

6.28.6 Ensure all main feedwater bypass valves in auto.

o AE LK-550 - AUTO /

o AE LK-560 - AUTO /

o AE LK-570 - AUTO /

o AE LK-580 - AUTO /

6.28.7 Trip non-running main feedwater pump using its trip/reset control to allow AFAS actuation in the event the running main feedwater pump is lost.

FC HIS-18 for MFWP A - TRIPPED /

OR

FC HIS-118 for MFWP B - TRIPPED /

6.28.8 Open the non-running Main Feedwater Pump Discharge Valve.

AE HIS-16 for MFP A - OPEN /

OR

AE HIS-15 for MFP B - OPEN /

6.29 WHEN Shift Manager or Control Room Supervisor desires to transfer steam seals from auxiliary steam to main steam, THEN transfer steam seal supply using SYS CA-120, TURBINE STEAM SEAL SYSTEM STARTUP. /

6.30 IF hot well temperature is less than 100°F OR Shift Manager or Control Room Supervisor desires condenser sparging, THEN place steam sparging to condenser in service using SYS AD-120, CONDENSATE SYSTEM STARTUP AND CLEANUP. /

6.31 Ensure steam generator blowdown is established at the proper flow rate for the number of demineralizer vessels specified by Chemistry to be in service. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 40 of 61 INIT/DATE 6.32 Roll the main turbine using SYS AC-120, MAIN TURBINE GENERATOR STARTUP, up to the point of synchronizing the turbine generator to the grid while continuing with this procedure. /

6.33 IF STS AC-001, MAIN TURBINE VALVE CYCLE TEST, has not been performed within the last 31 days, THEN make an Action Statement Summary Log entry to require completion of STS AC-001, MAIN TURBINE VALVE CYCLE TEST, within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months of placing the turbine in operation and prior to exceeding P-9. /

6.34 Verify systems are operable for entry into Mode 1 as follows:

6.34.1 Ensure steam generator chemistry is within specification using AP 02B-001, SECONDARY CHEMISTRY CONTROL. /

6.34.2 Ensure Mode 1 requirements are complete for the following:

1. STS CR-001, SHIFT LOG FOR MODES 1, 2,

& 3 /

2. STS ML-001, MONTHLY SURVEILLANCE LOG /

6.34.3 Contact Scaffold Group to ensure all scaffolding required to be removed prior to Mode 1 has been removed. /

6.34.4 Ensure Shift Manager has reviewed the following for entry into Mode 1: [3.2.10 and 3.2.11]

1. Clearance Order Log /

2. AP 21G-001, CONTROL OF LOCKED COMPONENT STATUS /

3. Temporary Modification Log /

4. Breach Authorization Log /

a. Ensure all compensatory measures verified. /

5. Equipment Out-Of-Service Log /

6. Work Request and Work Order Mode restraints /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 41 of 61 INIT/DATE

7. Mode Change Checklist - Mode 2 to 1

a. All surveillances on the checklist are current. /

b. Completed checklist attached to this procedure. /

6.34.5 Ensure Shift Manager has briefed the operating shift on the additional Technical Specifications that will become applicable in Mode 1 using ATTACHMENT B, TECHNICAL SPECIFICATIONS WHICH BECOME APPLICABLE IN MODE 1. [3.2.10] /

6.34.6 Ensure Manager Operations or Designee has reviewed plant status and procedural requirements are satisfied to proceed with the Mode change. [3.2.11] /

Signature, Manager Operations or Designee

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 42 of 61 INIT/DATE

É

º CAUTION º

º º

º DO NOT EXCEED A STABLE STARTUP RATE of 1.0 decade per minute º

º (DPM) or a transient startup rate of 1.5 DPM. º

º º 1/4

Ú

¿

³ NOTES ³

³ ³

³ o All individual indicated rod positions shall be within 12 ³

³ steps of their group step counter demand position and shall be ³

³ within the insertion, sequence and overlap limits specified in ³

³ the COLR in accordance with TS 3.1.4, 3.1.5 and 3.1.6. ³

³ ³

³ o Exceeding 5% power is a Mode change. ³

³ ³

6.35 Enter Mode 1 as follows:

6.35.1 (r)Withdraw control rods in manual, as necessary, to establish reactor power stable between 5% and 15% while continuing with this procedure. /

Ú

¿

³ NOTE ³

³ ³

³ If steam flow oscillations are observed, manual control of steam ³

³ dump controllers may be required. ³

³ ³

6.35.2 Ensure steam dumps open to control steam header pressure. /

Ú

¿

³ NOTE ³

³ ³

³ If steam generator level oscillations are observed, manual ³

³ control of main feedwater bypass valves may be required. ³

³ ³

6.35.3 Ensure main feedwater bypass valves maintain steam generator levels between 40%

and 60%. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 43 of 61 INIT/DATE 6.35.4 WHEN 2 of 4 power range channels indicate greater than 5% power, THEN perform the following:

1. In Control Room log, record date and time the unit entered Mode 1. /

2. Announce entry into Mode 1 on the plant page system. /

6.36 IF main turbine warming is not complete, THEN stabilize reactor power below 10% until turbine warming is complete. [3.2.17] /

6.37 WHEN reactor power is greater than 10%, THEN perform the following:

Ú

¿

³ NOTE ³

³ ³

³ If P-10 fails to properly change state, refer to Step 4.13. ³

³ (3.1.18) ³

³ ³

6.37.1 Check P-10 permissive properly changes state by observation of the following:

1. Bistable status lights lit o SB069, 14 down, 1 across - LIT /

o SB069, 14 down, 2 across - LIT /

o SB069, 14 down, 3 across - LIT /

o SB069, 14 down, 4 across - LIT /

2. Permissive status light lit o SB069, 15 down, 4 across - LIT /

6.37.2 Check annunciator 00-077E, SR HI VOLT FAIL

- CLEAR /

6.37.3 Block intermediate range low power trips:

1. Depress both IR TRIP BLOC pushbuttons.

o SE HS DEPRESSED /

2. Ensure intermediate range reactor trips are blocked.

o SB069, 13 down, 1 across - LIT /

o SB069, 13 down, 2 across - LIT /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 44 of 61 INIT/DATE 6.37.4 Block power range low power trips:

1. Depress both PR LO Ø Trip Bloc pushbuttons.

o SE HS DEPRESSED /

2. Ensure power range low setpoint reactor trips are blocked.

o SB069, 13 down, 3 across - LIT /

o SB069, 13 down, 4 across - LIT /

Ú

¿

³ NOTE ³

³ ³

³ When P-7 bistable is de-energized (P-7 permissive light ³

³ energizes), the following reactor trips are automatically ³

³ unblocked: ³

³ o Pressurizer low pressure ³

³ o Pressurizer high level ³

³ o Loss of flow - two loop logic ³

³ o RCP underfrequency ³

³ o RCP undervoltage ³

³ ³

6.37.5 WHEN P-10 permissive has changed state, THEN ensure that P-7 permissive light has energized.

o SB069, 12 down, 4 across - LIT /

6.37.6 Transfer NR-45 pen that is recording intermediate range to a delta flux channel. /

6.38 WHEN reactor power is stable between 10% and 15%,

THEN synchronize main generator to the grid using SYS AC-120, MAIN TURBINE GENERATOR STARTUP. /

6.39 Position the following valves:

6.39.1 Close main steam drain trap bypasses.

o AB HIS CLOSED /

6.39.2 Close Main Turbine Stop And Control Valve Startup Drains.

o AC HIS-134 - CLOSED /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 45 of 61 INIT/DATE 6.39.3 Ensure the following turbine extraction valves to high pressure feedwater heaters are open:

o AF HIS-24, FW HP Htr 5A Extraction Vlvs -

OPEN /

o AF HIS-64, FW HP Htr 5B Extraction Vlvs -

OPEN /

o AF HS-12, FW HP Htr 6A Extraction Vlvs -

OPEN /

o AF HS-44, FW HP Htr 6B Extraction Vlvs -

OPEN /

o AF HS-7, FW HP Htr 7A Extraction Vlvs -

OPEN /

o AF HS-58, FW HP Htr 7B Extraction Vlvs -

OPEN /

É

º CAUTIONS º

º º

º o The rate of power increase shall be limited to the following: º

º - Unit loading between 0 and 15 percent power shall be limited º

º to 0.5% (rated) power per minute. (3.1.15) º

º - Unit loading between 15 and 40 percent power shall be º

º limited to 5% (rated) power per minute OR a maximum step º

º change of 10% (rated) power. (3.1.15) º

º º

º o DO NOT EXCEED A STABLE STARTUP RATE of 1.0 decade per minute º

º (DPM) or a transient startup rate of 1.5 DPM. º

º º 1/4

Ú

¿

³ NOTES ³

³ ³

³ o All individual indicated rod positions shall be within 12 ³

³ steps of their group step counter demand position and shall be ³

³ within the insertion, sequence and overlap limits specified in ³

³ the COLR in accordance with TS 3.1.4, 3.1.5 and 3.1.6. ³

³ ³

³ o If steam flow oscillations are observed, manual control of ³

³ steam dump controllers may be required. ³

³ ³

6.40 WHEN turbine load is being increased, THEN use the following techniques:

6.40.1 IF moderator temperature coefficient is positive, THEN perform the following:

1. (r)Adjust control rods as necessary to

maintain Tavg greater than Tref. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 46 of 61 INIT/DATE

2. Perform turbine load increase using Load Limit Potentiometer in a slow controlled manner. /

3. As turbine load increases, adjust steam dump controllers as necessary to maintain cooldown valves or atmospheric relief valves between 80% and 100%

open.

Steam header pressure control, AB PK-507 /

OR

Atmospheric relief valve controllers /

6.40.2 (r)IF moderator temperature coefficient is negative or zero, THEN perform the following:

1. IF automatic turbine loading is desired, THEN control turbine load using automatic turbine-generator loading selected to 1/2% per minute. /

2. IF automatic turbine loading is NOT desired, THEN perform turbine load increase using Load Limit Potentiometer in a slow controlled manner. /

3. WHEN steam dumps are open, THEN adjust control rods as needed to maintain Tavg constant. /

4. WHEN steam dumps are closed, THEN adjust control rods, as necessary, to maintain Tavg within 1.5°F of Tref. /

6.41 (r)Increase reactor power by increasing turbine load while continuing with this procedure. /

6.41.1 Make Equipment Out of Service Log and Action Statement Summary Log entries to reflect the requirement to complete STS SE-001, POWER RANGE ADJUSTMENT TO CALORIMETRIC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after power is greater than or equal to 15% to satisfy SR 3.3.1.2. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 47 of 61 INIT/DATE

Ú

¿

³ NOTE ³

³ ³

³ This step may be performed during the 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months warmup required for ³

³ overspeed testing. ³

³ ³

6.42 WHEN first stage pressure is greater than 139 psig (20% of 692 psig), THEN ensure air is vented from the EHC system by performing the following:

[3.2.18]

6.42.1 SYS AC-140, MAIN TURBINE VALVE EXERCISE FOR AIR REMOVAL, Section 6.3. /

6.42.2 SYS AC-140, MAIN TURBINE VALVE EXERCISE FOR AIR REMOVAL, Section 6.4. /

6.43 IF performing Turbine Overspeed test, THEN stabilize Reactor Power at 15% to 17% AND perform STN AC-007, TURBINE OVERSPEED TRIP TEST. /

6.44 IF operating with a negative MTC AND turbine load is sufficient such that steam dump valves are closed, THEN perform the following:

6.44.1 Ensure all steam dump valves indicate closed.

o Condenser steam dumps - CLOSED /

o Atmospheric relief valves - CLOSED /

6.44.2 Momentarily place condenser steam dump control mode selector switch to reset.

o AB US-500Z - RESET /

6.44.3 Ensure loss of load interlock C-7 is reset. /

6.44.4 Place steam dump mode controller in Tavg mode.

o AB US-500Z - TAVG /

6.44.5 Ensure all atmospheric relief valve controllers are set to maintain 1125 psig in automatic.

o AB PIC-1A - IN AUTO AT 1125 PSIG /

o AB PIC-2A - IN AUTO AT 1125 PSIG /

o AB PIC-3A - IN AUTO AT 1125 PSIG /

o AB PIC-4A - IN AUTO AT 1125 PSIG /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 48 of 61 INIT/DATE

Ú

¿

³ NOTE ³

³ ³

³ Steam Generator level controllers should be left in auto for ³

³ level deviations of 10% or less. ³

³ ³

6.45 WHEN reactor power is between 15% and 20%, THEN perform the following:

6.45.1 (r)Stop turbine loading and stabilize reactor power. /

6.45.2 Check permissive P-13 has actuated.

o SB069, 12 down, 3 across - LIT /

6.45.3 Ensure the following feedwater low pressure heater extraction valves are open. (3.1.9)

AF HS-106, FW LP HTR 3A Extraction VLV -

OPEN /

AF HS-136, FW LP HTR 3B Extraction VLV -

OPEN /

AF HS-165, FW LP HTR 3C Extraction VLV -

OPEN /

AF HS-113, FW LP HTR 4A Extraction VLV -

OPEN /

AF HS-144, FW LP HTR 4B Extraction VLV -

OPEN /

AF HS-173, FW LP HTR 4C Extraction VLV -

OPEN /

Ú

¿

³ NOTE ³

³ ³

³ It is preferred to leave the Condensate pump miniflow valves ³

³ closed to minimize iron transports to the Steam Generators. ³

³ ³

6.45.4 IF desired, THEN open condensate pump miniflow valves to prevent heater drain tank dump valves from opening. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 49 of 61 INIT/DATE

Ú

¿

³ NOTE ³

³ ³

³ It is imperative for stable S/G level control that feedwater ³

³ temperature be kept as high as possible. ³

³ ³

6.45.5 (r)Adjust control rods, as necessary, to maintain Tavg stable while adjusting feedwater flow. /

6.45.6 Adjust feedwater DP, as necessary, to establish one of the following conditions:

All main feedwater regulating bypass valves are between 60% and 80% open. /

OR

IF significant variation in main feedwater regulating bypass valve position exists, THEN most open main feedwater regulating bypass valve is less than 90% open. /

6.45.7 WHEN feedwater DP has been adjusted AND steam generator levels are stable, THEN unisolate main feedwater regulating valves as follows:

1. Cycle each main feedwater regulating valve full open and return to closed position. [3.2.16]

o AE FK-510 - CYCLED AND CLOSED /

o AE FK-520 - CYCLED AND CLOSED /

o AE FK-530 - CYCLED AND CLOSED /

o AE FK-540 - CYCLED AND CLOSED /

2. Unisolate main feedwater regulating valves one at a time as follows:

a. Monitor feedwater flow to prevent overfeeding due to leakage past valve seats. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 50 of 61 INIT/DATE

b. IF feedwater flow increases while unisolating feedwater regulating valves, THEN perform the following:

1) Control associated feedwater regulating bypass valve in manual to re-establish the feedwater flow that existed prior to unisolating main feedwater regulating valve. /

2) WHEN main feedwater regulating valve has been unisolated, THEN return main feedwater regulating bypass valve controller to auto. /

c. Establish stable steam generator level prior to unisolating the next main feedwater regulating valve. /

d. DO NOT CONTINUE until all main feedwater regulating valves are unisolated.

o AE FK-510 - UNISOLATED /

o AE FK-520 - UNISOLATED /

o AE FK-530 - UNISOLATED /

o AE FK-540 - UNISOLATED /

3. Ensure "ISOLATED" magnetic information pads for main feedwater regulating valves have been removed from RL005. /

4. IF main feedwater regulating bypass valves are NOT open the same amount, THEN jog open main feedwater regulating valves whose bypass valves are most open to re-establish all bypass valves open approximately the same amount. /

6.46 Obtain required samples as follows while continuing with this procedure:

6.46.1 IF thermal power change has exceeded 15%

within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, THEN direct Chemistry to sample RCS for Iodine within 2 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after the power change has been completed as required by SR 3.4.16.2. /

6.46.2 Direct Chemistry to obtain sample from unit vent as required by AP 07B-003, OFFSITE DOSE CALCULATION MANUAL, Table 3-1. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 51 of 61 INIT/DATE 6.46.3 IF a containment purge is in progress, THEN direct Chemistry to obtain sample from containment as required by AP 07B-003, OFFSITE DOSE CALCULATION MANUAL, Table 3-1. /

6.47 Increase reactor power as follows:

6.47.1 Review turbine loading techniques in Step 6.40 including all notes and cautions. /

6.47.2 Ensure steam generator levels are stable. /

6.47.3 (r)Increase reactor power to 25% by increasing turbine load while continuing with this procedure. /

6.47.4 Adjust feedwater DP, as necessary, to establish one of the following conditions:

All main feedwater regulating bypass valves are between 60% and 80% open. /

OR

IF significant variation in main feedwater regulating bypass valve position exists, THEN most open main feedwater regulating bypass valve is less than 90% open. /

6.48 WHEN reactor power is greater than 20%, THEN on nuclear instrumentation cabinet, ensure intermediate range control rod stop bistable is illuminated.

[3.2.6]

o High Level Rod Stop - LIT /

6.49 Prior to exceeding 25% reactor power, secure feedwater heating using SYS AE-200, FEEDWATER PREHEATING DURING PLANT STARTUP AND SHUTDOWN. /

6.50 WHEN feedwater heating has been secured, THEN transfer auxiliary steam system to auxiliary steam reboiler using SYS FB-200, PLACING THE AUX STEAM REBOILER IN SERVICE. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 52 of 61 INIT/DATE 6.51 WHEN reactor power is greater than 25%, THEN perform the following: [3.2.6]

6.51.1 On nuclear instrumentation cabinet, ensure intermediate range high flux trip bistable is illuminated.

o High Level Trip - LIT /

6.51.2 Check low power reactor trip bistables properly change state by observation of the following:

1. Intermediate range hi level reactor trip status lights lit o SB069, 6 down, 1 across - LIT /

o SB069, 6 down, 2 across - LIT /

2. Power range, low setpoint reactor trip status lights lit o SB069, 5 down, 1 across - LIT /

o SB069, 5 down, 2 across - LIT /

o SB069, 5 down, 3 across - LIT /

o SB069, 5 down, 4 across - LIT /

6.51.3 IF any reactor trip bistable did NOT trip, THEN contact Reactor Engineering and I&C. /

6.52 IF this is the Initial Power Ascension of a New Core, THEN stabilize Reactor Power between 25% and 30% and Hold for Flux Map and Satisfactory Data Analysis prior to exceeding 30% Power. (3.1.12) /

6.53 WHEN reactor power is between 25% and 30%, THEN perform the following:

6.53.1 (r)Stop turbine loading and stabilize reactor power. /

6.53.2 Ensure S/G levels are greater than or equal to 50% with positive indication of steam and feedwater flows. /

6.53.3 (r)Adjust control rods as necessary to maintain Tavg stable while adjusting feedwater flow. /

6.53.4 Place main feedwater regulating valves in service as follows:

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 53 of 61 INIT/DATE

Ú

¿

³ NOTE ³

³ ³

³ Manual jogging of main feedwater regulating valves may be ³

³ necessary to optimize stable feedwater flows. ³

³ ³

1. Place main feedwater regulating valve in AUTO.

2. Jog close on associated bypass valve in manual.

3. Ensure main feedwater regulating valve is controlling in AUTO.

4. Continue jogging close on associated bypass valve until bypass valve is fully closed.

5. Establish stable steam generator level prior to placing next main feedwater regulating valve in service.

6. DO NOT CONTINUE until all main feedwater regulating valves are in service.

o AE FK-510 - IN SERVICE /

o AE FK-520 - IN SERVICE /

o AE FK-530 - IN SERVICE /

o AE FK-540 - IN SERVICE /

6.54 Increase reactor power as follows:

6.54.1 Review turbine loading techniques in Step 6.40 including all notes and cautions. /

6.54.2 Ensure steam generator levels are stable. /

6.54.3 (r)Increase reactor power to 30% by increasing turbine load while continuing with this procedure. /

6.54.4 As turbine-generator load is increased, maintain feedwater DP close to programmed value. Refer to OA-93-18 on RL005. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 54 of 61 INIT/DATE 6.55 WHEN reactor power is greater than 30%, THEN shift main feedwater pump speed control to auto as follows:

6.55.1 IF main feedwater pump is at minimum speed, THEN allow reactor power to increase until actual feedwater DP is less than or equal to programmed feedwater DP. /

6.55.2 Adjust main feedwater pump speed as necessary to match programmed feedwater DP and actual feedwater DP. Refer to OA-93-18 on RL005. /

6.55.3 WHEN programmed feedwater DP and actual feedwater DP are matched, THEN shift main feedwater pump turbine speed control to automatic as follows:

1. Place running feedwater pump speed control in manual. (Mark idle pump speed control N/A)

FC SK-509B - IN MANUAL /

OR

FC SK-509C - IN MANUAL /

2. Place master speed control in automatic.

o FC SK-509A - IN AUTO /

3. Match running feedwater pump speed control with master speed control and place in automatic. (Mark idle pump speed control N/A)

FC SK-509B - IN AUTO /

OR

FC SK-509C - IN AUTO /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 55 of 61 INIT/DATE

Ú

¿

³ NOTE ³

³ ³

³ Performing portions of STN AC-008, STEAM DRAIN VALVE ³

³ OPERABILITY, may be required in conjunction with SYS AC-130, ³

³ OPERATION OF MOISTURE SEPARATOR REHEATERS. ³

³ ³

6.56 WHEN reactor power is greater than 30% power, THEN commence placing first and second stage reheaters in service using SYS AC-130, OPERATION OF MOISTURE SEPARATOR REHEATERS. /

6.57 IF SG BLOWDOWN REGENERATIVE HX CONDENSATE OUTLET TO HTR DRAIN TK ISO was closed in Step 5.25, THEN open SG BLOWDOWN REGENERATIVE HX CONDENSATE OUTLET TO HTR DRAIN TK ISO.

o BM-V185 - OPEN /

6.58 IF the S/G Blowdown Regen Heat Exchanger was bypassed in step 5.23, THEN realign the S/G Blowdown Regen Heat Exchanger per SYS BM-128, SGBD COMPONENT OPERATIONS. /

6.59 Maintain turbine load as directed by Shift Manager or Control Room Supervisor and System Operations. /

6.60 IF the plant has been in Mode 3 AND STS AC-001, MAIN TURBINE VALVE CYCLE TEST, has not been performed within the last 31 days, THEN perform STS AC-001, MAIN TURBINE VALVE CYCLE TEST. /

6.61 Transfer loads from the startup transformer to the auxiliary transformer, by performing the following:

6.61.1 Place 13.8 KV Source Select Switch to auxiliary transformer position.

o PA HS UNIT AUX /

6.61.2 Close unit auxiliary 13.8 KV breaker PA0101.

o PA HIS CLOSED /

6.61.3 Match flags on startup transformer 13.8 KV breaker PA0110.

o PA HIS FLAGS MATCHED /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 56 of 61 INIT/DATE 6.61.4 Close unit auxiliary 13.8 KV breaker PA0211.

o PA HIS CLOSED /

6.61.5 Match flags on startup transformer 13.8 KV breaker PA0202.

o PA HIS FLAGS MATCHED /

6.61.6 Place 13.8 KV Source Select Switch in off position.

o PA HS OFF /

6.62 IF Reactor Engineering desires to change control rod park position, THEN perform STN SF-001, CONTROL ROD PARKING. /

6.63 Close the following turbine drain valves:

o AC HIS-72, HP TURB S/U DRNS JOG CTRL - CLOSED /

o AC HIS-131, COLD REHEAT DRNS JOG CTRL - CLOSED /

o AC HIS-119, MSR SHELL DRNS JOG CTRL - CLOSED /

6.64 Ensure service water system parameters, including backpressure, are within the normal band per SYS EA-120, SERVICE WATER SYSTEM STARTUP. /

6.65 Go to GEN 00-004, POWER OPERATION. /

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 57 of 61 INIT/DATE 7.0 FINAL CONDITIONS 7.1 The unit is operating at greater than or equal to 30% of full power.

7.2 Main generator is synchronized and supplying the grid.

7.3 The 13.8 kV buses PA01 and PA02 are being supplied from either the unit auxiliary or startup transformer.

8.0 RECORDS 8.1 The following QA records are generated by this procedure:

8.1.1 Section 5.0 8.1.2 Section 6.0 8.1.3 FIGURE 1

-END-

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 58 of 61 ATTACHMENT A (Page 1 of 2)

TECHNICAL SPECIFICATIONS WHICH BECOME APPLICABLE IN MODE 2 A.1 Safety Limits A.1.1 TS 2.1.1 - REACTOR CORE

1. The combination of thermal power, pressurizer pressure, and the highest operating loop coolant temperature (Tavg) shall not exceed the limits shown in FIGURE 2.1.1-1 for four loop operation.

A.1.2 TS 2.1.2 - REACTOR COOLANT SYSTEM PRESSURE

1. The time limit for taking action if RCS pressure exceeds 2735 psig is relaxed at higher RCS temperatures.

A.2 Reactivity Control Systems A.2.1 TS 3.1.3 - MODERATOR TEMPERATURE COEFFICIENT

1. MTC now applies for less positive at beginning of life (BOL) as well as less negative at end of life (EOL) as specified in Figure 3.1.3-1. (N/A when TS 3.1.8 is in effect)

A.2.2 TS 3.1.4 - ROD GROUP ALIGNMENT LIMITS

1. All shutdown and control rods shall be operable.

Individual indicated rod positions shall be within 12 steps of their group step counter demand positions.

A.2.3 TS 3.1.5 - SHUTDOWN BANK INSERTION LIMITS

1. Each shutdown bank shall be within insertion limits specified in the COLR. Applicable when in Mode 1 and Mode 2 with any control bank not fully inserted.

A.2.4 TS 3.1.6 - CONTROL BANK INSERTION LIMITS

1. Control banks shall be within the insertion, sequence and overlap limits specified in the COLR. Applicable when in Mode 1 and Mode 2 with Keff ³1.0.

A.2.5 TS 3.1.7 - ROD POSITION INDICATION

1. The Digital Rod Position Indication (DRPI)

System and the Demand Position Indication System shall be operable.

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 59 of 61 ATTACHMENT A (Page 2 of 2)

TECHNICAL SPECIFICATIONS WHICH BECOME APPLICABLE IN MODE 2 A.2.6 TS 3.1.8 - PHYSICS TEST EXCEPTIONS - MODE 2

1. During the performance of PHYSICS TESTS, the requirements of TS 3.1.3, 3.1.4, 3.1.5, 3.1.6 and 3.4.2 may be suspended, provided the following remain satisfied:

o RCS lowest operating loop average temperature is ³541°F; o SDM is within the limits provided in the COLR; and o THERMAL POWER is less than or equal to 5% RTP.

A.2.7 TS 3.4.2 - MINIMUM TEMPERATURE FOR CRITICALITY

1. The RCS lowest operating loop temperature (Tavg) shall be greater than or equal to 551°F. (N/A when TS 3.1.8 is in effect)

A.3 Instrumentation A.3.1 TS 3.3.1 - REACTOR TRIP SYSTEM INSTRUMENTATION

1. Most reactor trip instrumentation are required to be operable. Refer to Table 3.3.1-1.

A.3.2 TS 3.3.2 - ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

1. ESFAS for turbine trip and feedwater isolation are required to be operable.

A.3.3 TR 3.3.13 - LOOSE-PART DETECTION SYSTEM

1. Loose Parts Monitoring System shall be operable.

A.4 Reactor Coolant System A.4.1 TS 3.4.4 - REACTOR COOLANT LOOPS AND COOLANT CIRCULATION

1. All reactor coolant pumps shall be in operation.

A.5 Containment Systems A.5.1 TS 3.6.8 - HYDROGEN RECOMBINERS

1. Two hydrogen recombiners shall be operable.

-END-

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 60 of 61 ATTACHMENT B (Page 1 of 1)

TECHNICAL SPECIFICATIONS WHICH BECOME APPLICABLE IN MODE 1 B.1 Power Distribution Limits B.1.1 TS 3.2.3 - AXIAL FLUX DIFFERENCE (AFD)

1. AFD is applicable in Mode 1 greater than or equal to 50%.

B.1.2 TS 3.2.1 - HEAT FLUX HOT CHANNEL FACTOR - FQ(X,Y,Z)

1. Heat Flux Hot Channel Factor-FQ(X,Y,Z) becomes applicable.

B.1.3 TS 3.2.2 - NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR

- FDH(X,Y)

1. Nuclear Enthalpy Rise Hot Channel Factor FDH(X,Y) becomes applicable.

B.1.4 TS 3.2.4 - QUADRANT POWER TILT RATIO

1. QPTR is applicable in Mode 1 above 50%.

B.1.5 TS 3.4.1 - DNB PARAMETERS

1. RCS DNB parameters for pressurizer pressure, RCS average temperature and RCS total flow rate shall be with the specified limits.

B.2 Instrumentation B.2.1 TS 3.3.1 - REACTOR TRIP SYSTEM INSTRUMENTATION

1. All reactor trip instrumentation are required to be operable. Refer to Table 3.3.1-1.

B.2.2 TS 3.3.2 - ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

1. Auto start of motor driven AFW pumps on trip of all main feedwater pumps is required to be operable. Refer to Table 3.3.2-1 FUNCTION 6.g.

-END-

Revision: 62 GEN 00-003 HOT STANDBY TO MINIMUM LOAD Continuous Use Page 61 of 61 FIGURE 1 1/M PLOT

Administrative RO A1b WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 002-A K/A NO: 2.1.7 COMPLETION TIME: K/A RATING: 3.7 JOB TITLE: Reactor Operator REVISION: 0 TASK TITLE: Given Data, complete a 1/M plot and determine estimated critical rod position DUTY: Conduct of Operations ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

MAY BE PERFORMED IN ANY LOCATION WHERE PROPER REFERENCE MATERIAL IS AVAILABLE.

METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

GEN 00-002, Hot standby to Minimum Load STS RE-002, Estimated Critical Position SOER 88-2, Premature Criticality Events During Reactor Startup TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 002-A RO A1b Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in hot standby recovering from a short forced outage at middle of core life. The crew is performing a reactor startup in accordance with GEN 00-003, Hot Standby To Minimum Load. Initial data has been entered on Figure 1, 1/M Plot which is provided.

Initiating Cues: With the data supplied, initiate the 1/M Plot per step 6.12 and complete the 1/M Plot.

Estimate the critical position per steps 6.19.5.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the Candidate with an information only copy of GEN 00-003, Step 6.19.5.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have completed a 1/M Plot that indicates criticality will occur at a rod position higher than the maximum rod height calculated by Reactor Engneering and have notified the CRS that Reactor Engineering must be informed.

START TIME:

STOP TIME:

PAGE 1 of 4

JPM NO: 002-A RO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Enter the supplied data on

1. *Estimate Critical Rod Figure 1 Comments:

Position Calculate 1/M for each rod withdrawal sequence Note estimated critical postion for each rod withdrawal sequence Note when rods are withdrawn to Bank B at 185 steps that flux is more than double its initial value and the ECP is Bank D at 162 steps Note this is higher than the max heighth supplied by Reactor Engineering of Bank D at 81 steps STEP 6.19.5.2 S U Note the requirement to

2. *Inform Reactor maintain the reactor Comments:

Engineering and stable and notify reactor maintain reactor stable engineering STEP 6.19.5.3 Acknowledge Report THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 4

JPM NO: 002-A RO A1b Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in hot standby recovering from a short forced outage at middle of core life. The crew is performing a reactor startup in accordance with GEN 00-003, Hot Standby To Minimum Load. Initial data has been entered on Figure 1, 1/M Plot which is provided.

Initiating Cues: With the data supplied, initiate the 1/M Plot per step 6.12 and complete the 1/M Plot.

Estimate the critical position per steps 6.19.5.

THE FOLLOWING DATA IS PROVIDED From Reactor Engineering Maximum rod height for criticality: Bank D at 81 steps Minimum rod height for criticality: Bank C at 72 steps Estimated critical position: Bank D at 29 step Initial count rate 520 cps Source Range NI response to rod withdrawals Rod Position A50 A100 B35 B85 B135 B185 C95 C145 Channel SR SR SR SR SR SR SR SR SR SR Cf 553 634 732 881 1019 1300 1575 2166 PAGE 4 of 4

JPM 003-A Data Sheet STS AB-201D STEP AB PV-4 INDICATION AND PIT PARAMETER SAT/UNSAT/NA STEP AB PV-4 INDICATION AND PIT PARAMETER SAT/UNSAT/NA 8.4.6 AB PIC-4A Output indicates approximately 100% UNSAT Green indicating light on AB ZL-4A is out SAT Red indicating light on AB ZL-4A is out SAT Computer point ABE0004 indicates valve NCLSD SAT If PIT was performed, THEN valve moved from NA closed to open position STEP STROKE TEST PARAMETERS MEASURED 8.4.7 AB PV-4 opening stroke time* 15.4 sec 8.4.9 AB PV-4 closing stroke time* 16.1 sec 8.4.15 AB PV-4 Complete Cycle** SAT 8.4.17.4 AB PV-4 Steam Trap Inspection 1650 ml 8.4.19 AB PV-4 Complete Cycle SAT

Administrative RO A2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 003-A K/A NO: 2.2.12 COMPLETION TIME: K/A RATING: 3.0 JOB TITLE: RO REVISION: 0 TASK TITLE: Given Data, Complete the Surveillance Test Data sheet identifying and documenting any out of spec readings.

DUTY: Equipment Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

MAY BE PERFORMED IN ANY LOCATION WHERE PROPER REFERENCE MATERIAL IS AVAILABLE.

METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

STS AB201D, Atmospheric Relief Valve Inservice Valve Test TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 003-A RO A2 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: STS AB-201D, Atmospheric Relief Valve Inservice Valve Test, is being performed in Mode 1 for AB PV-4 only.

Initiating Cues: Given data observed, complete Attachment A for AB PV-4 only and document any required actions if applicable. The JPM will be complete when you have completed Attachment A and made any necessary entries on the Surveillance Test Routing Sheet based on Attachment A entries only.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the Candidate with a copy of Attachment A of STS AB-201D. The readings to be annotated are included on the instruction sheet for this JPM.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: This JPM will be complete when Attachment A is complete and Part 3 of the APF 29B 01 is completed noting that :

Action 2 is required for step 8.4.6, AB PIC-4A Output Indication

Action 1 is required for step 8.4.9. The valve is inoperable.

Action 2 is required for step 8.4.17.4.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 003-A RO A2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Record supplied data on

1. *Complete Attachment Attachment A as on Comments:

A Attachment Key STEP: Attachment A S U Complet block 3 of the

2. *Complete STRS as on the attached Comments:

Surveillance Test Key.

Routing Sheet May report directly to STEP : Routing Sheet CRS that several deficiencies exist and that the valve is inoperable THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 003-A RO A2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: STS AB-201D, Atmospheric Relief Valve Inservice Valve Test, is being performed in Mode 1 for AB PV-4 only.

Initiating Cues: Given data observed, complete Attachment A for AB PV-4 only and document any required actions if applicable. The JPM will be complete when you have completed Attachment A and made any necessary entries on the Surveillance Test Routing Sheet based on Attachment A entries only.

THE FOLLOWING DATA IS PROVIDED STEP AB PV-4 INDICATION AND PIT PARAMETER SAT/UNSAT/NA 8.4.6 AB PIC-4A Output indicates approximately 100% ~80%

Green indicating light on AB ZL-4A is out out Red indicating light on AB ZL-4A is lit out Computer point ABE0004 indicates valve NCLSD nclsd If PIT was performed, THEN valve moved from NA closed to open position STEP STROKE TEST PARAMETER MEASURED 8.4.7 AB PV-4 opening stroke time* 15.4 sec 8.4.9 AB PV-4 closing stroke time* 20.1 sec 8.4.15 AB PV-4 Complete Cycle** Complete Cycle - SAT 8.4.17.4 AB PV-4 Steam Trap Inspection 1650 ml 8.4.19 AB PV-4 Complete Cycle Complete Cycle - SAT PAGE 3 of 3

FORM APF 29B-003-01 REV 04 SURVEILLANCE TEST ROUTING SHEET (STRS)

DOCUMENT NUMBER: STS AB-201D **TEST FREQ. 2 Years

- DUE DATE/TIME: 03/26/2004 00:00 DOCUMENT TITLE: **LATE DATE/TIME: 11/08/2004 19:27 ATMOSPHERIC RELIEF VALVE INSERVICE VALVE TEST **T/S REQUIRED MODE: 1 2 3

- REQUIRED PLANT MODE: 1 2 3 4 5 6

- INITIATING DOCUMENT #(S):

- SUPPORTING CLEARANCE ORDER(s) [Commitment Step 3.2.29]

- RESPONSIBLE GROUP: OPS

- SUPPORT GROUP(S):

- PRE-TEST COMMENTS: PIT Not required

1) PROCEDURE VERIFIED TO BE CORRECT REVISION WITH ALL _______/_______

TEMPORARY CHANGES ATTACHED AND INCORPORATED. INIT/DATE TEST PERFORMERS:

PRINT NAME INIT/DATE PRINT NAME INIT/DATE

/ / / /

2) PRE-TEST REVIEWS: SIGNATURE DATE TIME

/ /

SM/CRS/DESIGNEE AUTH/NOTIF/NI / /

(CIRCLE AS APPLICABLE) / /

3) *TEST DEFICIENCY DESCRIPTION:

/

4) *T/S OR TRM FAILURE? TP INIT / DATE

¨ YES ¨ NO /

SM/CRS/DESIGNEE SIGNATURE DATE IF NO - JUSTIFICATION:

5) *ACTION TAKEN:

EOL # WR/WO#

TEST SUSPENDED ¨ YES ¨ NO /

SM/CRS/DESIGNEE SIGNATURE DATE

SECTIONS 3, 4, AND 5 ARE COMPLETED IF A TEST DEFICIENCY OCCURS. OTHERWISE MARK N/A.

6) POST TEST REVIEWS: (GROUP SUP. CHECK ONE) ¨ COMPLETE ¨ PARTIAL ¨ N/A TOTAL MAN HOURS:

SIGNATURE DATE TIME

/ /

TEST PERFORMER

/ /

SM/CRS/DESIGNEE REVIEW/NOTIF:

GROUP SUPERVISOR:

SC/SURV. TECHNICIAN

7) ADDITIONAL COMMENTS**:

- OPTIONAL INFORMATION NOT REQUIRED TO BE FILLED IN FORM APF 29B-003-01 REV 04 SURVEILLANCE TEST ROUTING SHEET (STRS)

DOCUMENT NUMBER: STS AB-201D **TEST FREQ. 2 Years

- DUE DATE/TIME: 03/26/2004 00:00 DOCUMENT TITLE: Manual/Auto Start, Synch **LATE DATE/TIME: 11/08/2004 19:27

& Loading of Emergency DG NE01

- T/S REQUIRED MODE: 1 2 3 4 5 6

- REQUIRED PLANT MODE:

- INITIATING DOCUMENT #(S):

- SUPPORTING CLEARANCE ORDER(s) [Commitment Step 3.2.29]

- RESPONSIBLE GROUP: OPS

- SUPPORT GROUP(S):

- PRE-TEST COMMENTS:

1) PROCEDURE VERIFIED TO BE CORRECT REVISION WITH ALL _______/_______

TEMPORARY CHANGES ATTACHED AND INCORPORATED. INIT/DATE TEST PERFORMERS:

PRINT NAME INIT/DATE PRINT NAME INIT/DATE

/ / / /

2) PRE-TEST REVIEWS: SIGNATURE DATE TIME

/ /

SM/CRS/DESIGNEE AUTH/NOTIF/NI / /

(CIRCLE AS APPLICABLE) / /

3) *TEST DEFICIENCY DESCRIPTION:

/

4) *T/S OR TRM FAILURE? TP INIT / DATE

¨ YES ¨ NO /

SM/CRS/DESIGNEE SIGNATURE DATE IF NO - JUSTIFICATION:

5) *ACTION TAKEN:

EOL # WR/WO#

TEST SUSPENDED ¨ YES ¨ NO /

SM/CRS/DESIGNEE SIGNATURE DATE

SECTIONS 3, 4, AND 5 ARE COMPLETED IF A TEST DEFICIENCY OCCURS. OTHERWISE MARK N/A.

6) POST TEST REVIEWS: (GROUP SUP. CHECK ONE) ¨ COMPLETE ¨ PARTIAL ¨ N/A TOTAL MAN HOURS:

SIGNATURE DATE TIME

/ /

TEST PERFORMER

/ /

SM/CRS/DESIGNEE REVIEW/NOTIF:

GROUP SUPERVISOR:

SC/SURV. TECHNICIAN

7) ADDITIONAL COMMENTS**:

- OPTIONAL INFORMATION NOT REQUIRED TO BE FILLED IN

Administrative RO A3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 004-A K/A NO: 2.3.1 COMPLETION TIME: K/A RATING: 2.6 JOB TITLE: RO REVISION: 0 TASK TITLE: Given a Clearance Order for venting/draining a contaminated system in the RCA, Determine the RWP, limits and time allowed to complete the job.

DUTY: Radiation Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED

REFERENCES:

TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

Administrative RO A3 JPM NO: 004-A RO A3 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are a spare Reactor Operator. Another Operator has contacted you for assistance in completing a Clearance Order in the RCA.

Initiating Cues: The other Operator is requesting assistance in opening BG V0374, RWST To Charging Pump Suction Line Drain Valve, located in the A CCP Room. For this task:

# identify the correct RWP.

describe the dress out requirements.

identify the dosimetry settings .

consider that you have received 1830 MR dose this calendar year, and estimate your stay time in the lowest dose area of the room.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: #If performed at the RCA entrance. Allow the candidate to access the book of RWPs and tell you which RWP would be correct. When the Candidate indicates they are going to read the posted survey map for the indicated area, provide them with the survey map attached to this JPM.

If performed in a classroom. Provide the candidate with the attached four RWPs and ask them to select the one appropriate for the job.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have identified:

RWP 04-045

dress out requirement of full set

dosimetry setting of 20 mr Dose and 200 mr Dose Rate

an estimated stay time of 4 hrs. (4 hrs. X 5mr = 20 mr dose)

START TIME:

STOP TIME:

PAGE 1 of 4

JPM NO: 004-A RO A3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 1 *Identify the correct Comments:

RWP If performed at the RCA entrance. Look in book outside Access Control. Note that RWP 04-045 is for Operations access for contaminated systems venting and draining activities If performed in a classroom. Select the correct RWP from the four provided.

S U In work activity block of

2. *Describe the dress RWP 04-045, note that Comments:

out requirements the requirement is for a full set.

Under setting block of 3 *Identify the dosimetry RWP 04-045, note the settings settings are :

Dose 20 MR

Rate 200 MR/HR

CRITICAL STEP PAGE 2 of 4

JPM NO: 004-A RO A3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE Note that the limiting time

4. *Estimate your stay time is 20 MR dose from the in the lowest dose area RWP. The survey map of the room indicates a lowest dose area of 5 mr. 20 MR divided by 5 MR = 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months stay time THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 3 of 4

JPM NO: 004-A RO A3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are a spare Reactor Operator. Another Operator has contacted you for assistance in completing aClearance Order in the RCA.

Initiating Cues: The other Operator is requesting assistance in opening BG V0374, RWST To Charging Pump Suction Line Drain Valve, located in the A CCP Room. For this task:

identify the correct RWP.

describe the dress out requirements.

identify the dosimetry settings .

consider that you have received 1830 MR dose this calendar year, and estimate your stay time in the lowest dose area of the room.

PAGE 4 of 4

WCGS RADIOLOGICAL SURVEY MAP RPF02-210-1(Q)REV 3 Page of Date Time All Dose Rates in mrem/hr 1974' AUX BLDG "A" CENTRIFUGAL CHARGING PUMP RM #1114 unless specified.

All Dose Rates <2 mRem/hr unless specified.

All Smears which were counted for Beta/Gamma <1000 dpm/100cm 2 unless specified.

All Smears which were counted for Alpha <20 dpm/100cm 2 ROOM COOLER unless specified.

All Large Area Smears (LAS)

<1000 dpm/LAS, unless specified.

STATUS BOARD UPDATED:

YES NO CHANGE F-2 Smear Data For Smears > Limits above.

(DPM/Smear Area)

No. Beta/Gamma Alpha HS-1 F-1 G 1114 FPWIN\MTHLY\3RD\1114 SURVEY REASON RWP# % POWER INST(S)/WC#

REMARKS HP Dose for Survey mRem Performed By: Reviewed By:

HP Technician ACAD HP Supervisor Operations Date G = GAITRONICS P = PHONE LR = LADDER RACK 1 = RADIATION AREA 4 = CONTAMINATED AREA 7 = HOT PARTICLE AREA 10 = AIRBORNE RADIOACTIVITY AREA, DUE TO NOBLE GAS 2 = HIGH RADIATION AREA 5 = HIGHLY CONTAMINATED AREA 8 = HOT PARTICLE STORAGE AREA 11 = RADIOACTIVE MATERIALS AREA 3 = LOCKED HIGH RADIATION AREA 6 = POTENTIAL HOT PARTICLE AREA 9 = AIRBORNE RADIOACTIVITY AREA 12 = RADIOLOGICALLY CONTROLLED AREA (REF RPP 02-210)

RWP: 040045 REV: 000 STATUS: ACTIVE TYPE: SPECIFIC WORK DESCRIPTION:

OPERATIONS PERSONNEL ACCESS TO THE RCA FOR CONTAMINATED SYSTEMS VENTING AND DRAINING ACTIVITIES.

LOCATION/ROOM: 10 BUILDING: RCA ELEVATION: ALL LOCATION/ROOM DESC: ALL RADIOLOGICAL CONTROLLED AREAS -

EXCLUDING CONTAINMEN SYSTEM/COMPONENT: N/A DESCRIPTION:

RADIOLOGICAL CONDITIONS l l l lAirbornel l Work Activity l

Radiation l* ContaminationlActivityl l l mR/Hr l Dpm/100 cm2 lExpectedl l RCA & RADIATION AREAS l >2 G/A l SEE CONTAM. l NO l l l <100 ME l WORK ACTIVITY l l HP COVERAGE: START OF JOB /INTERMITTENT PC`S: PC'S PER THE ALLOWED CONTAMINATED AREA WORK ACTIVTIES l HIGH RADIATION AREAS l <200 MA l SEE CONTAM. l NO l l l l WORK ACTIVITY l l HP COVERAGE: START OF JOB / INTERMITTENT PC`S: PC'S PER THE ALLOWED CONTAMINATED AREA WORK ACTIVITIES l CONTAMINATED & POTENT. l SEE DOSE RATE l >1K G/A l NO l l HOT PARTICLE AREAS l WORK ACTIVITY l l l HP COVERAGE: START OF JOB / INTERMITTENT PC`S: FULL SET

l HIGHLY CONTAMINATED & l SEE DOSE RATE l >99K G/A l YES l l HOT PARTICLE AREAS l WORK ACTIVITY l l l HP COVERAGE: START OF JOB / INTERMITTENT PC`S: DOUBLE SET

G/A = GENERAL AREA CON = CONTACT ME = MAXIMUM EXPECTED

ME = MAXIMUM EXPECTED MA = MAXIMUM ALLOWED 1K = 1000 SPECIAL INSTRUCTIONS: 1) MEDIUM RISK- YELLOW RWP 2) DISCUSS ALL ACTIVITIES TO BE COMPLETED AND ALL AREAS TO BE ENTERED WITH HP SHIFT TECHNICIAN PRIOR TO COMMENCING WORK. 3) NOTIFY HP PRIOR TO AND AFTER THE VENTING/DRAINING OF CONTAMINATED SYSTEMS. 4)

CONSIDERATION SHALL BE GIVEN TO USE BAGS WITH ABSORBENTS ( NOT HOSES ) FOR STS /

VENTING AND DRAINING. EXAMPLE STS BG-002 DUE TO DOSE REDUCTION FOR ALARA. 5)

NO ENTRY INTO LOCKED HIGH RADIATION AREAS. 6) NO ENTRY TO AIRBORNE RADIOACTIVITY AREAS > 2 DAC (EXCEPT FOR ONES POSTED DUE TO NOBLE GAS)

7) CONTACT HP SHIFT TECH PRIOR TO ENTRY TO HIGHLY CONTAMINATED, HOT PARTICLE AREAS 2 & 3, OR WHEN ACCESSING AIRBORNE RADIOACTIVITY AREAS (

EXCEPT FOR NOBLE GAS ) 8) FULL HOOD AND/OR FACE SHIELD MAY BE REQUIRED BY HP, BASED ON JOB TASK AND CURRENT WORK AREA CONDITIONS, PER RPP 03-505. 9) CONTACT HP SHIFT TECHNICIAN PRIOR TO ENTERING HIGH RADIATION AREAS OR WHEN PERFORMING SURVEILLANCES WHERE RADIATION LEVELS ARE EXPECTED TO CHANGE. 10) NO PRIMARY RESIN TRANSFERS PERMITTED ON THIS RWP.

Simulator S1 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO:101-S K/A NO: 029 EA1.02 COMPLETION TIME:15 Minutes K/A RATING: 3.6/3.3 JOB TITLE:RO/SRO REVISION: 0 TASK TITLE: Emergency Borate using EMG FR-S1 DUTY:Anticipated Transient Without Scram ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

EMG FR-S1, Response To Nuclear Power Generation ATWT TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 101-S S1 Simulator Setup IC 173 On monitor screen:

Monitor ybg8104 Set 1=0.045 Run Read to Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Your are the Reactor Operator, an ATWT has occurred, The Control Room Supervisor has entered EMG FR-S1, Safety Injection is not in progress.

Initiating Cues: The Control Room Supervisor directs you to complete steps 5-7 of EMG FR-S1 to commence emergency boration.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide a copy of EMG FR-S1, Steps 5 thru 7 to the Candidate.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have established emergency boration flow via the RWST thru the Normal Charging Pump.

START TIME:

STOP TIME:

PAGE 1 of 5

JPM NO: 101-S S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Initiate Emergency Boration of RCS: Comments:

Ensure one charging pump running Note that BG HIS-3 for the NCP has a red lite only and flow is indicated on BG FI-121a

*Align boration flowpath

a. Ensure boric Rotate handswitch BG acid pumps - HIS-5a and/or BG HIS -

AT LEAST 6a clockwise and note ONE red lite only illuminated.

RUNNING

b. Open emergency Depress the open button borate to on BG HIS-8104 and note charging red lite only illuminated.

pump suction valve STEP 5.

CRITICAL STEP PAGE 2 of 5

JPM NO: 101-S S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

2. Verify Charging Flowpath Comments:

Ensure Charging Pumps to Regen HX Verify red lite only lit on Containment Iso Vlvs BG HIS-8105 and BG

- OPEN HIS-8106.

Ensure Regen HX to Verify red lite only Loop Cold Leg illuminated on BG-8146 valves - ONLY ONE OR BG 8147. Verify OPEN green lite only on the remaining valve

Adjust Charging flow NOTE: When the to maintain Note pressurizer level at candidate gets to this or trending to 27% on BB pressurizer level step, cue them that LI-459A or 460A or 461.

Pressurizer level is Select manual control and satisfactory (Prevents adjust BG FK-462 if interference with the necessary to establish other ongoing JPM) desired level.

*Adjust back pressure control to NOTE: When the Rotate BG HC-182 as establish between 8- candidate gets to this necessary to establish 8-13 gpm seal injection step, cue them that seal 13 gpm on BG FR 154, flow to each RCP flow is satisfactory 155, 156, and 157.

(Prevents interference STEP 6 with the other ongoing JPM)

S U

3. *Check Emergency Note flow on BG FI-183A is <30 GPM and Comments:

Borate Flow Greater recognize need to peform Than 30 GPM the RNO for Step 7 STEP 7

CRITICAL STEP PAGE 3 of 5

JPM NO: 101-S S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. Perform the following:

Comments:

Depress open button on

*Align RWST to BN HIS-112D or BN charging pump HIS-112E and note red suction lite only illuminated.

Depress the close pushbutton on BG HIS-112B or BG HIS-112C and verify green lite only is illuminated.

Check RWST flow through charging Check BG FI-121A or system - EM FI-917A or EM FI-GREATER THAN 917B and note flow is 90 GPM greater than 90 GPM

IF RWST flow through charging Determine that system is less than Attachment A is not 90 gpm THEN required. Report to the establish alternate Control Room Supervisor boration flowpath that Immediate Borate using Attachment A flow of greater than 90 GPM has been STEP 7 RNO established via the RWST Control Room Supervisor acknowledges the report This completes this JPM RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 5

JPM NO: 101-S S1 Rev: 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Your are the Reactor Operator, an ATWT has occurred, The Control Room Supervisor has entered EMG FR-S1, Safety Injection is not in progress.

Initiating Cues: The Control Room Supervisor directs you to complete steps 5-7 of EMG FR-S1 to commence emergency boration.

PAGE 5 of 5

Simulator S2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO:301-S K/A NO: 006 A2.03 COMPLETION TIME:15 Minutes K/A RATING: 3.3/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: OFN BB-31 S/D LOCA, Isolate RHR Leak DUTY:Emergency Core Cooling System The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OFN BB-031, Shutdown LOCA TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 301-S S2 Rev 0 Simulator Setup IC 173 Malfunction mRHR07A and tie to event 1 Ensure Digital Displays are selected to Top BBT0413A and place sticky note on label Bottom BBP0403 and place sticky note on label DNO SIP A, SIP B, and CCP A Run Read to Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 4. You are the Reactor Operator, a loss of reactor coolant is occurring . The crew has entered OFN BB-31 and performed steps 1 thru 26 a.

Initiating Cues: Per Step 26a RNO, the Control Room Supervisor directs you to perform Attachment C to transfer RHR suction to the RWST. Pressure is 375 pounds and decreasing.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide a copy of OFN BB-031, Attachment C, to the Candidate..

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have isolated the RCS leak by closing the RCS hot leg to RHR Pump A Suction Valves.

START TIME:

STOP TIME:

PAGE 1 of 5

JPM NO: 301-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Check at least one RHR Determine that red lite Pump - OPERATING IN only is illuminated on EJ Comments:

COOLDOWN MODE HIS-1 with EJ PI-614 indicating discharge pressure and EJ FI-618 STEP C1 indicating flow.

S U Check EJ TR-612 and

2. *Check operating RHR determine that Comments:

Pump discharge temperature is greater temperature - than 260°F GREATER THAN 260°F STEP C2 S U

3. Isolate flow through operating RHR train Comments:

Operate EJ HIC-606 clockwise until scale

*Close RHR HX indicates closed flow control valve Depress the Man pushbutton on EJ FK-618

*Place RHR HX and depress the close bypass controls in pushbutton until the scale manual and close the indicates 0 output valves STEP C3

CRITICAL STEP PAGE 2 of 5

JPM NO: 301-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. Check operating RHR Check EJ TR-612 red pen Pump discharge and note decreasing Comments:

temperature - temperature trend DECREASING:

NOTE: Candidate may perform Step C4 RNO STEP C4 and ensure RHR recirc valves and CCW to HX valves - OPEN if immediate temperature decrease is not apparent.

S U Check EJ TR-612 red pen

5. *Check operating RHR and note temperature Comments pump discharge <260°F temperature - LESS THAN OR EQUAL TO 260°F :

NOTE: Temperature may not be <260°F yet Candidate may be STEP C5 required to perform the RNO and loop back to Step C4 until temperature reaches <260°F S U

6. Check RHR pump A - Check lineup from hot RUNNING IN legs to HX into CVCS. Comments COOLDOWN MODE NOTE: This was part of initial conditions STEP C6

CRITICAL STEP PAGE 3 of 5

JPM NO: 301-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

7. Check RHR pump A for leakage Comments

*Stop RHR Pump A Rotate EJ HIS-1 to the left and note green lite only illuminated. with EJ PI-614 indicating no discharge pressure and EJ FI-618 indicating no flow.

*RCS leakage stopped or reduced Note wide range pressure increasing.

*Isolate RHR Train Depress the close A from the RCS by pushbutton on BB HIS-closing RCS hot leg 8702A and EJ HIS-to RHR Pump A 8701A and note green suction valves lites only illuminated.

Note wide range pressure

*Check RCS increasing.

leakage isolated Announce that the leak

Align RHR Train B has been isolated and for RCS cooldown next intended action is to per SYS EJ-120 Control Room perform SYS EJ-120 Supervisor acknowledges the report STEP C7 This completes this JPM RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 5

JPM NO: 301-S S2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 4. You are the Reactor Operator, a loss of reactor coolant is occurring . The crew has entered OFN BB-31 and performed steps 1 thru 26 a.

Initiating Cues: Per Step 26a RNO, the Control Room Supervisor directs you to perform Attachment C to transfer RHR suction to the RWST. Pressure is 375 pounds and decreasing.

PAGE 5 of 5

Simulator S3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 501-S K/A NO: E15 EA1.3 COMPLETION TIME: 14 Minutes K/A RATING: 2.8/3.0 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE Isolate Source of Containment Flooding, EMG FR-Z2 DUTY: Containment Flooding The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

EMG FR-Z2, Response To Containment Flooding TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 501-S S3 Rev 0 Simulator Setup IC 174 Run Override annuns 60E and 60F ON Insert transformer lockout mEPS05A Insert ESW break mWAT07A at 30%

Insert override on P20013a (value 87)

Insert override on P20013b(value 87)

Freeze until JPM begins Read to Examinee I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The crew is recovering from a reactor trip. An Orange Path exists for Critical Safety Function -Containment.

NOTE: The simulator may or may not match all conditions expected.

Initiating Cues: The Control Room Supervisor directs you to perform Steps of EMG FR-Z2, Response To Containment Flooding.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide a current copy of EMG FR-Z2 to the Candidate.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have determined the leak location and will have isolated it per EMG FR-Z2.

START TIME:

STOP TIME:

PAGE 1 of 4

JPM NO: 501-S S3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Try to identify unexpected source of Comments:

water to sump Check EF FI-53 and 54.

*Check Essential Note that EF FI-53 is Service Water - indicating significantly NOT LEAKING higher than EF FI-54.

STEP 1 S U Depress the close

2. *Close valves and stop pushbutton on EF HIS-31 Comments:

pumps as necessary to and note green lite only limit containment illuminated.

flooding.

NOTE: Closing EF STEP 1 RNO HV31 isolates the leak.

EF HV33, 45, and 49 are isolation valves that are downstream of the break.

CRITICAL STEP PAGE 2 of 4

JPM NO: 501-S S3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

3. Sample Containment Sumps Comments:

Request Chemistry to sample containment Notify Control Room sumps Supervisor to order Chemistry to sample the Containment sumps for activity, chlorides, and STEP 2 boron.

Acknowledge request.

CRS will contact Chemistry.

S U

4. Notify Plant Engineering Notify the Control Room of sump level and Supervisor that the Comments:

activity level and obtain procedure is on hold until a recommended action. the sample results have been obtained.

STEP 3 Control Room Supervisor acknowledges the report This completes this JPM RECORD STOP TIME ON PAGE 1.

CRITICAL STEP PAGE 3 of 4

JPM NO: 501-S S3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The crew is recovering from a reactor trip. An Orange Path exists for Critical Safety Function -Containment.

NOTE: The simulator may or may not match all conditions expected.

Initiating Cues: The Control Room Supervisor directs you to perform Steps of EMG FR-Z2, Response To Containment Flooding.

PAGE 4 of 4

Simulator S4 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 401-S K/A NO: 061 A1.01 COMPLETION TIME: 15 Minutes K/A RATING: 3.9/4.2 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Feed S/Gs with TDAWP DUTY: Auxiliary/Emergency Feedwater System The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

SYS AL-120, Feeding Steam Generators With A Motor Driven or Turbine Driven AFW Pump TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 401-S S4 Rev 0 Simulator Preparation:

IC 174 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 3 at normal operating temperature and pressure. SG NR levels are less than 42% on narrow range instruments The Motor Driven Feed Pump has been lost.

Initiating Cues: The Control Room Supervisor directs you to start the Turbine Driven Auxiliary Feed Water Pump (TDAFWP) and increase SG levels to clear the SG level deviation alarms using Section 6.2 of SYS AL-120. Feed at 75,000 to 100,000 LBM/HR per SG. Stabilize level at 50%, do not exceed 55%. Return the TDAFWP to standby conditions when finished. The procedure prerequisites are satisfied.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide a current copy of SYS AL-120 to the Candidate.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have increase SG level to 50% narrow range using the Turbine Driven Auxiliary Feedwater Pump.

START TIME:

STOP TIME:

PAGE 1 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Verify AFP Turb On FC HIS-312A verify mechanical trip/throttle green lite only is lit. Comments:

valve is closed STEP 6.2.1

CRITICAL STEP PAGE 2 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

2. *Close the TDAFWP Comments:

discharge throttle valves to each SG Operate the AL HK-8A

SG A control to the closed detent position and verify output meter indicates zero.

Operate the AL HK-10A

SG B control to the closed detent position and verify output meter indicates zero Operate the AL HK-12A

SG C control to the closed detent position and verify output meter indicates zero Operate the AL HK-6A

SG D control to the closed detent position and verify output meter indicates zero STEP 6.2.2

CRITICAL STEP PAGE 3 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

3. *Open at least one Comments:

steam supply valve to TDAFWP Depress the open

Open loop 2 steam pushbutton on AB HIS-supply 5A and verify red lite only is lit And/Or And/Or Depress the open

Open loop 3 steam pushbutton on AB HIS-supply 6A and verify red lite only is lit STEP 6.2.3 S U

4. Start TDAFWP Comments:

*Open trip/throttle valve Depress the open pushbutton on FC HIS-312A and note red lite only is lit. Note red light only on FC ZL-315A/317A, discharge pressure and flow indicated on AL PI 21A, and the SG flow indicator(s).

Record time opened in

Time valve opened blank on 6.2.4.2

Verify discharge Note pressure on AL PI-pressure greater than 21A is >1625 psig and 1625 psig record in blank on 6.2.4.3 STEP 6.2.4

CRITICAL STEP PAGE 4 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

5. *Throttle flow to Comments:

desired steam generators

SG A Operate the controller on AL HK-8A to the open position until 75,00-100,000 LBM is indicated on AL FI-2A

SG B Operate the controller on AL HK-10A to the open position until 75,00-100,000 LBM is indicated on AL FI-3A

SG C Operate the controller on AL HK-12A to the open position until 75,00-100,000 LBM is indicated on AL FI-4A

SG D Operate the controller on AL HK-6A to the open position until 75,00-100,000 LBM is indicated on AL FI-1A STEP 6.2.5

CRITICAL STEP PAGE 5 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

6. Record TDAFWP total Add the indication on AL flow FI-1A, 2A, 3A, and 4A Comments:

and record sum in blank STEP 6.2.6 provided S U Monitor SG level on

7. *Monitor appropriate level recorders and SG Comments:

SG levels NR indicators.

Determine NR levels are STEP 6.2.7 increasing as appropriate

CRITICAL STEP PAGE 6 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Note 50% NR level

8. *When desired SG indicated on SG A. Comments:

level is obtained, Operate the controller on then adjust the flow AL HK-8A until 25%

control valve demand is indicated or to controllers to 25% the signal necessary to demand position stabilize level.

STEP 6.2.8 Note 50% NR level indicated on SG B.

Operate the controller on AL HK-8A until 25%

demand is indicated or to the signal necessary to stabilize level.

Note 50% NR level indicated on SG C.

Operate the controller on AL HK-8A until 25%

demand is indicated or to the signal necessary to stabilize level.

Note 50% NR level indicated on SG D.

Operate the controller on AL HK-8A until 25%

demand is indicated or to the signal necessary to stabilize level.

CRITICAL STEP PAGE 7 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

9. Stop the TDAFWP:

Comments:

If running after auto Realize this step is NA start then ensure all activation signals are reset/blocked

*Close Depress the close pushbutton on FC HIS-Trip/Throttle valve 312A and note green lite only is lit. Should check discharge pressure (AL PI-21A) and SG flow indicators (AL FI-1A, 2A, 3A, and 4A) returning to zero.

Record the time the valve

Time valve closed was closed in blank provided.

*Close steam supply Depress the close valves to TDAFWP pushbutton on AB HIS-5A and verify green lite only is lit And/Or Depress the close pushbutton on AB HIS-6A and verify green lite only is lit STEP 6.2.9

CRITICAL STEP PAGE 8 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

10. Return TDAFWP Comments:

discharge throttle valves to safeguards lineup.

Operate controller to

AL HK-8A for SG A latch detent open position and note demand meter indicates 100.

Operate controller to latch detent open position

AL HK-10A for SG and note demand meter B indicates 100.

Operate controller to latch detent open position

AL HK-12A for SG and note demand meter C indicates 100.

Operate controller to latch detent open position and note demand meter indicates 100.

AL HK-6A for SG D STEP 6.2.10 S U

11. If stopping the TDAFWP Realize this step is NA after auto start, then Comments:

perform the following STEP 6.2.11

CRITICAL STEP PAGE 9 of 11

JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

12. Section 6.2 complete Report to Control Room Supervisor that section Comments:

STEP 6.2.12 6.2 is complete.

ACKNOWLEDGE THE REPORT THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 10 of 11

JPM NO: 401-S S4 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 3 at normal operating temperature and pressure. SG NR levels are less than 42% on narrow range instruments The Motor Driven Feed Pump has been lost.

Initiating Cues: The Control Room Supervisor directs you to start the Turbine Driven Auxiliary Feed Water Pump (TDAFWP) and increase SG levels to clear the SG level deviation alarms using Section 6.2 of SYS AL-120. Feed at 75,000 to 100,000 LBM/HR per SG. Stabilize level at 50%, do not exceed 55%. Return the TDAFWP to standby conditions when finished. The procedure prerequisites are satisfied.

PAGE 11 of 11

Simulator S5 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 801-S K/A NO: 008 A4.01 COMPLETION TIME: 25 minutes K/A RATING: 3.3/3.1 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Swap CCW Trains DUTY: Component Cooling Water The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

SYS EG-201, Transferring Supply Of CCW Service Loop And CCW Train Shutdown TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 801-S S5 Rev 0 Simulator Setup IC 175 (low power IC)

Ensure the NCP is in service Run Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. The CCW Service Loop is on the B Train. Maintenance is pending on the B Train CCW Heat Exchanger.

Initiating Cues: The Control Room Supervisor directs you to shift the CCW Service Loop to A Train and secure the B Train pump. The Auxiliary Building Operator is performing the Section 6.2 of SYS EG-201. A reactivity briefing has been performed for the completion of this procedure. The Spent Fuel Pool Cooling will be transferred by the balance of the crew.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide an information only copy of SYS EG-201 to the Candidate.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have transferred the CCW Service Loop to A Train with the A CCW Pump running and all B Train Pumps secured.

START TIME:

STOP TIME:

PAGE 1 of 9

JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Start desired Train A CCW Pump Comments:

Turn off the motor space heater supply Contact the local operator breaker. and direct that breaker PG19NJF118 be turned off Local Operator will acknowledge request and call back immediately and state the breaker has been turne off

*Start desired CCW Pump Actuate EG HIS-21 to the right. Note that the red lite only is illuminated.

Verify operating Contact local operator to CCW Pump monitor EG FI-95 or use discharge flow is computer point EGF0095.

greater than 1.5 E6 Note that flow is LBM/HR adequate.

If local operator is contacted they will report that flow is 1.6

If operating CCW E6 LBM/HR. Determine that this step is Pump discharge flow NA is less than 1.5 E6 LBM/HR then refer to step 4.4 STEP6.1.1

CRITICAL STEP PAGE 2 of 9

JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

2. Locally verify CCW Contact local operator Train A Pump Room Comments:

Cooler running.

STEP 6.1.2 When called, the local opeator will report the cooler is running.

S U

3. If CCW Pump A was started, then verify Comments:

proper room cooler damper alignment:

GL-D156 - OPEN Contact local operator and ask them to verify that GL-D156 is open

GL-D157 - CLOSED Contact local operator and ask them to verify that GL-D157 is closed When called, the local STEP 6.1.3 operator will report GL-D156 open and GL-D157 is closed.

CRITICAL STEP PAGE 3 of 9

JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. If CCW Pump C was Realize that the step is started, then verity NA Comments:

proper room cooler damper alignment STEP 6.1.4 S U Depress the open

5. *If RHR Train B is not pushbutton on EC HIS-12 Comments:

in service, then ensure and note red lite only is SFP HX B CCW Outlet illuminated.

Vlv is open to provide a flow path for CCW Train B STEP 6.1.5 S U

6. *Close CCW Surge Comments:

Tank A and B Vent Valves Depress the close

EG HIS-9 pushbutton on EG HIS-9 and note green lite only is illuminated.

EG HIS-10 Depress the close pushbutton on EG HIS-10 and note green lite only is illuminated STEP 6.1.6

CRITICAL STEP PAGE 4 of 9

JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Actuate the EG HS-15

7. *Open CCW Train A open pushbutton and note Comments:

Supply/Return Valves red lites only illuminted for the Train A Supply If candidate mentions and Return Valves.

reactivity briefing is STEP 6.1.7 required, cue them the briefing was already conducted.

Thermal Barriers will isolate at his point.

When candidate announces the alarms, the Control Room Supervisor will acknowledge the report.

S U Actuate the EG HS-16

8. *Close CCW Train B close pushbutton and note Comments:

Supply/Return Valves green lite only on the Train B Supply and STEP 6.1.8 Return Valves.

CRITICAL STEP PAGE 5 of 9

JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

9. Verify CCW to RW and Read EG FI-55A and RCS Flow indication confirm flow is >1.6 E6 Comments:

LBM/HR and <4.3 E6 STEP 6.1.9 LBM/H

10. *Open CCW Surge Tank A and B Vent Valves Actuate the EG HIS-9

EG HIS-9 open pushbutton and note red lite only is illuminated.

EG HIS-10 Actuate the EG HIS-10 open pushbutton and note STEP 6.1.10 red lite only is illuminated.

CRITICAL STEP PAGE 6 of 9

JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

11. *Ensure CCW from Comments:

RCP Thermal Barriers are open Actuate BB HIS-13 open

BB HIS OPEN pushbutton and note red lite only is illuminated Actuate BB HIS-14 open

BB HIS OPEN pushbutton and note red lite only is illuminated Actuate BB HIS-15 open

BB HIS OPEN pushbutton and note red lite only is illuminated Actuate BB HIS-16 open

BB HIS OPEN pushbutton and note red lite only is illuminated STEP 6.1.11 S U

12. Section 6.1 complete Announce that section 6.1 is complete and move on Comments:

to section 6.3 to secure B Train.

CRITICAL STEP PAGE 7 of 9

JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

13. Ensure all train B ECCS Note the handswitch and pumps stopped discharge pressure Comments:

indication for CCP B, STEP 6.3.1 RHR Pump B, and SI Pumpt B all green lite only illuminated with no discharge pressure indicated.

S U

14. Align Spent Fuel Pool Announce intention to Cooling Train A for perform SYS EC-120. Comments:

operation using SYS EC- Will be performed by 120 spare RO.

STEP 6.3.2 S U

15. Stop the running train B Actuate EG HIS-22 to the CCW Pump left and note green lite Comments:

only illuminated STEP 6.3.3

CRITICAL STEP PAGE 8 of 9

JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

15. Ensure the motor space Contact the local operator heater breaker for the and direct that breaker Comments:

CCW Pump is turned PG20GBR240 be closed on.

The local operator will STEP 6.3.4 acknowledge the request and report the breaker is closed.

S U

16. Section 6.3 complete Announce that Section 6.3 is complete. Comments:

STEP 6.3.5 Acknowledge the report THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 9 of 9

JPM NO: 801-S S5 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. The CCW Service Loop is on the B Train. Maintenance is pending on the B Train CCW Heat Exchanger.

Initiating Cues: The Control Room Supervisor directs you to shift the CCW Service Loop to A Train and secure the B Train pump. The Auxiliary Building Operator is performing the Section 6.2 of SYS EG-201. A reactivity briefing has been performed for the completion of this procedure. The Spent Fuel Pool Cooling will be transferred by the balance of the crew.

PAGE 9 of 9

Simulator S6 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 701-S K/A NO: 015 A1.03 COMPLETION TIME: K/A RATING: 3.7/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Rx Start Up, 10-8 amps to Point of Adding Heat DUTY: Nuclear Instrumentation System ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

GEN 00-003, Hot Standby to Minimum Load TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 701-S S6 Rev 0 Simulator Setup IC 175 Run Insert malfunctions mNIS03A, C, and D. Set value to 0 Ensure that GDSU & BB01 are displayed on NPIS.

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The crew is performing a reactor startup per GEN-003. The reactor is critical at 10-8 AMPS, and the crew is holding at step 6.28 of GEN 00-003.

Initiating Cues: The Control Room Supervisor directs you to perform the steps necessary to increase reactor power at a rate of .5 to .8 dpm to the point of adding heat (POAH) and stabilize reactor power at 0.5% to 1.0%.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide an information only copy of Step 28 of GEN 00-003, Hot Standby To Minimum Load, to the Candidate.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have stabilized power between .5 to 2.0%

and reported the NI failure to the CRS.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 701-S S-6 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. *Increase reactor Comments:

power

Ensure dump valves Adjust the pot on AB PK-are adjusted to 507 to 7.18 turns for maintain Tavg 557°F. ARVs not between 552°F and required.

562°F

Adjust control rod Pull control rods per height, as necessary, CRS instructions until a to establish desired steady startup of rate startup rate between 0.5 and 0.8 DPM is achieved on SE NI 35D and 36D

Reduce or stop steam Determine that SG level generator blowdown, is being maintained as necessary to without reducing maintain sufficient blowdown.

feedwater flow capability Determine that power range nuclear instrumentation is not responding on channel A, C, or D. Stablize power and report to CRS.

NOTE: JPM is complete when power is stabilized.

Acknowledge report.

THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1 STEP 6.28

CRITICAL STEP PAGE 2 of 3

JPM NO: 701-S S-6 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The crew is performing a reactor startup per GEN-003. The reactor is critical at 10-8 AMPS, and the crew is holding at step 6.28 of GEN 00-003.

Initiating Cues: The Control Room Supervisor directs you to perform the steps necessary to increase reactor power at a rate of .5 to .8 dpm to the point of adding heat (POAH) and stabilize reactor power at 0.5% to 1.0%.

PAGE 3 of 3

Simulator S7 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 201-S K/A NO: 013 A4.01 COMPLETION TIME: 20 Minutes K/A RATING: 4.5/4.8 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Manually align one train of CREVS DUTY: Engineered Safety Features Actuation System The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 201-S S7 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Maintenance is planned on the Control Building Normal Supply Fan.

Initiating Cues: The Control Room Supervisor directs you to perform SYS GK-122, Attachment C, to manually align both trains of Control Room Emergency Ventilation.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide an information only copy of SYS GK-122 to the Candidate.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have manually placed both trains of Control Room Emergency Ventilation in service.

START TIME:

STOP TIME:

PAGE 1 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. Place Control Room in CRVIS Lineup Comments:

Inform Chemistry the Hot Lab fume hoods Call Chemistry and will not have flow inform them the Access Control Exhaust Fans are being secured Acknowledge the call.

Inform Health Call HP and inform them Physics the exhaust the Access Control path for the clothes Exhaust Fans are being dryers will be secured unavailable Acknowledge the call

*Align Control Transition to Attachment C

Room Emergency Ventilation as desired.

STEP 6.1 S U

2. GK HIS Actuate GK HIS-19 to RUN/OPEN run and note red lite only Comments:

on GK ZL19B, C, and D.

STEP: Attachment C

CRITICAL STEP PAGE 2 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

3. GK HIS-160 - OPEN Actuate GK HIS-160 to open and note red lite Comments:

STEP: Attachment C only illuminated.

S U Actuate GK HIS-29 to the 4 *GK HIS right and note red lite Comments:

RUN/OPEN only illuminated OR OR Actuate GK HIS-40 to the

GK HIS right and note red lite RUN/OPEN only illuminated STEP: Attachment C S U Actuate GK HIS-75 to the

5. *GK HIS right and note red lite Comments:

RUN/OPEN only illuminated STEP: Attachment C

CRITICAL STEP PAGE 3 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

6. GK HIS-100 - RUN Actuate GK HIS-100 to open and note Note red Comments:

lite only lit.

STEP: Attachment C S U

7. GK HIS CLOSED Actuate GK HIS-13 to close and note green lite Comments:

STEP: Attachment C only lit on S U

8. GK HIS-172 - CLOSED Actuate GK HIS-172 to close and note green lite Comments:

STEP: Attachment C only illuminated.

CRITICAL STEP PAGE 4 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

9. GK HIS-174 - CLOSED Actuate GK HIS-174 to close and note green lite Comments:

STEP: Attachment C only illuminated.

S U

10. GK HIS STOP Actuate GK HIS-8 to stop and note green lite only Comments:

STEP: Attachment C illuminated.

S U Actuate GK HIS-16 to the

11. *GK HIS left and note green lites Comments:

STOP/CLOSED only for the fan and the damper STEP: Attachment C

CRITICAL STEP PAGE 5 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Actuate GK HIS-47 to the

12. *GK HIS STOP left and note green lite Comments:

only illuminated STEP: Attachment C S U

13. GK HIS CLOSED Actuate GK HIS-59 to close and note green lite Comments:

STEP: Attachment C only illuminated.

S U Actuate GK HIS-83 to the

14. *GK HIS right and note red lite Comments:

RUN/OPEN only lit for the fan and the damper STEP: Attachment C

CRITICAL STEP PAGE 6 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Actuate GK HIS-30 to the

15. *GK HIS right and note red lite Comments:

RUN/OPEN only lit for the fan and the damper STEP: Attachment C S U Actuate GK HIS-161

16. *GK HIS-161 - OPEN open pushbutton and note Comments:

red lite only lit.

STEP: Attachment C S U Actuate GK HIS-103 to

17. *GK HIS-103 - RUN run and note red lite only Comments:

lit.

STEP: Attachment C

CRITICAL STEP PAGE 7 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Note red lite only lit on

18. *GK HIS Actuate GK HIS-98 to Comments:

CLOSED close and note green lite only illuminated.

STEP: Attachment C S U Actuate GK HIS-57 close

19. *GK HIS CLOSED button and note green lite Comments:

only lit.

STEP: Attachment C S U Actuate GK HIS-55 close

20. *GK HIS CLOSED button and note green lite Comments:

only lit STEP: Attachment C

CRITICAL STEP PAGE 8 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Actuate GK HIS-184

21. *GK HIS-184 - close button and note Comments:

CLOSED green lite only lit STEP: Attachment C S U Actuate GK HIS-173

22. *GK HIS-173 - close button and note Comments:

CLOSED green lite only lit STEP: Attachment C S U Actuate GK HIS-175

23. *GK HIS-175 - close button and note Comments:

CLOSED green lite only lit STEP: Attachment C

CRITICAL STEP PAGE 9 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Actuate GK HIS-122

24. *GK HIS-122 - close button and note Comments:

CLOSED green lite only lit STEP: Attachment C S U Actuate GK HIS-123

25. *GK HIS-123 - close button and note Comments:

CLOSED green lite only lit STEP: Attachment S U

26. GK HIS Check GK HIS-17 and STOP/CLOSED note green lite only lit for Comments:

the fan and the damper STEP: Attachment C

CRITICAL STEP PAGE 10 of 12

JPM NO: 201-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

27. GK HIS STOP Check GK HIS-49 and note green lite only Comments:

STEP: Attachment C illuminated S U 28.

Comments:

S U

29. Attachment C complete Initial and date the completion and report Comments:

STEP: 6.1.5 CRVIS manually aligned.

Acknowledge report THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 11 of 12

JPM NO: 201-S S7 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Maintenance is planned on the Control Building Normal Supply Fan..

Initiating Cues: The Control Room Supervisor directs you to perform SYS GK-122, Attachment C, to manually align both trains of Control Room Emergency Ventilation.

PAGE 12 of 12

Administrative SRO A1a WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 005-A K/A NO: 2.1.33 COMPLETION TIME: K/A RATING: 4.0 JOB TITLE: SRO REVISION: 0 TASK TITLE: Review Surveillance Test for AFD and based on results determine any required actions.

DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

MAY BE PERFORMED IN ANY LOCATION WHERE PROPER REFERENCE MATERIAL IS AVAILABLE.

METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

STS SF-002, Axial Flux Differential Core Operating Limits Report Technical Specification 3.2.3 TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 005-A SRO A1a Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has been stable at 100% power. The AFD Monitor Alarm is inoperable. You are a spare Senior Reactor Operator.

Initiating Cues: The Shift Manager has directed you to perform STS SF-002 and determine T/S actions as appropriate.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the candidate with an Information Only copy of STS SF-002.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

The following data is provided on the THE FOLLOWING DATA IS PROVIDED ON THE CUE SHEET N41 N42 N43 N44

% Power 100 100 100 100

% Flux Difference -13 -16 -16 -14 Task Standard: Upon completion of this JPM, the Candidate will have determined that the Plant is in Technical Specification 3.2.3, Action A, and power must be reduced below 50% within 30 minutes.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 005-A SRO A1a Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Go to Attachment A and

1. *Record data as enter the data provide on Comments:

required on Attachment the cue sheet A

Determine that N41 and

Compare % flux N44 are in the acceptable for each channel to region and annotate the COLR limits attachment accordingly.

Determine that N42 and STEP 8.1 N43 are in the unacceptable region and annotate the attachment accordingly.

S U Determine that the Plant

2. *If the indicated FLUX is in TS 3.2.3 Condition Comments:

DIFF is outside the A and must reduce acceptable limits of thermal power to <50%

COLR on two or more within 30 minutes.

operable PR channels, then perform the actions required by Tech Specs. THE JPM IS COMPLETE STEP 8.1.2 RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 005-A SRO A1a Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant has been stable at 100% power. The AFD Monitor Alarm is inoperable. You are a spare Senior Reactor Operator.

Initiating Cues: The Shift Manager has directed you to perform STS SF-002 and determine T/S actions as appropriate.

THE FOLLOWING DATA IS PRESENT ON PLANT INSTRUMENTATION N41 N42 N43 N44

% Power 100 100 100 100

% Flux Difference -13 -16 -16 -14 PAGE 3 of 3

CORRECTED COPY 07-03-2002 STS SF-002 CORE AXIAL FLUX DIFFERENCE Responsible Manager Manager Operations

Ú

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³ Revision Number ³ 7 ³

Ã

Å'

³ Use Category ³ Continuous

³

Ã

Å'

³ Administrative Controls Procedure ³ No ³

Ã

Å'

³ Infrequently Performed Procedure ³ No ³

Ã

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³ Program Number ³ 21D ³

DC22 12/18/1999

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 1 of 6 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 2 3.1 References 2 3.2 Commitments 2 4.0 PRECAUTIONS/LIMITATIONS 2 5.0 TEST EQUIPMENT 2 6.0 ACCEPTANCE CRITERIA 2 7.0 PREREQUISITES 2 8.0 PROCEDURE 4 9.0 RESTORATION 4 10.0 RECORDS 5 ATTACHMENT A AXIAL FLUX DIFFERENCE LOG 6

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 2 of 6 1.0 PURPOSE 1.1 The purpose of this procedure is to monitor and log Axial Flux Difference (AFD) at least once per hour when the AFD Monitor Alarm (NPIS Computer) is inoperable.

2.0 SCOPE 2.1 This procedure satisfies the requirements of Technical

³ Requirements Manual TR 3.3.17 and Technical Specification

³ SR 3.2.3.1 if/when the NPIS Computer is inoperable for

³ more than 7 days.

³

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3.1.1 WCGS Technical Specifications 3.1.2 COLR, Core Operating Limits Report 3.1.3 WCGS Technical Requirements Manual

³ 3.2 Commitments 3.2.1 None

³ 4.0 PRECAUTIONS/LIMITATIONS 4.1 Report any irregularities or component malfunctions to the

³ Shift Manager immediately, and reference Technical

³ Specification LCO 3.2.3.

³ 4.2 The Control Rods should not be moved when the AFD is being monitored.

4.3 The AFD Monitor Alarm is an NPIS Computer generated alarm.

It is considered operable by the performance of STN RJ-001, VERIFICATION OF OPERABILITY OF COMPUTER PROCESSES, whenever the NPIS Computer is operable, and is inoperable whenever the NPIS Computer is down.

5.0 TEST EQUIPMENT 5.1 None 6.0 ACCEPTANCE CRITERIA

6.1 AFD is monitored to be within the limits specified in the COLR.

6.2 The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 3 of 6 7.0 PREREQUISITES INIT/DATE 7.1 The plant is in Mode 1 with thermal power greater

³ than or equal to 50% rated thermal power. /

³ 7.2 The AFD Monitor Alarm is inoperable. /

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 4 of 6 INIT/DATE 8.0 PROCEDURE

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³ NOTE ³

³ ³

³ The recorded values of indicated FLUX DIFF shall be assumed to ³

³ exist during the interval preceding each logging. ³

³ ³

8.1 At RL004, record data as required on ATTACHMENT A, at least once per hour for each operable power range channel. (Mark inoperable channel(s) N/A) 8.1.1 Compare the % FLUX DIFF from each operable power range channel to the limits of COLR, Figure 2.5.

1. Designate whether the indicated % FLUX DIFF is within the acceptable operation range of COLR, Figure 2.5 for each operable channel by placing a check mark in yes (Y) or no (N) column.

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³ NOTE ³

³ ³

³ The AFD shall be considered outside the limits when two or more ³

³ operable excore channels indicate AFD to be outside the limits. ³

³ ³

8.1.2 IF the indicated FLUX DIFF is outside the acceptable limits of COLR, Figure 2.5 on two or more operable power range channels, THEN perform the actions required by Technical Specification 3.2.3.

8.2 IF additional copies of ATTACHMENT A are needed, THEN attach copies as necessary and sequentially number each sheet in the space provided.

9.0 RESTORATION 9.1 None

9.2 Comments

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 5 of 6 10.0 RECORDS 10.1 The following QA records are generated by this procedure:

10.1.1 Sections 7, 8 and 9 10.1.2 ATTACHMENT A

-END-

Revision: 7 STS SF-002 CORE AXIAL FLUX DIFFERENCE Continuous Use Page 6 of 6 ATTACHMENT A (Page 1 of 1)

AXIAL FLUX DIFFERENCE LOG (Step 8.2) Sheet of

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³ ³ Step 8.1 (RL004) ³Step 8.1.1.1 ³ ³

³ ÃÂ'In COLR Fig.2.5³ ³

³ ³ % POWER ³ % FLUX DIFF ³Acceptable Rg. ³ ³

³ TIME

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-END-

FORM APF 29B-003-01 REV 04 SURVEILLANCE TEST ROUTING SHEET (STRS)

DOCUMENT NUMBER: STS SF-002 **TEST FREQ. Contingent

- DUE DATE/TIME: N/A DOCUMENT TITLE: **LATE DATE/TIME: N/A CORE AXIAL FLUX DIFFERENCE **T/S REQUIRED MODE: 1

- REQUIRED PLANT MODE: 1

- INITIATING DOCUMENT #(S):

- SUPPORTING CLEARANCE ORDER(s) [Commitment Step 3.2.29]

- RESPONSIBLE GROUP: OPS

- SUPPORT GROUP(S):

- PRE-TEST COMMENTS:

1) PROCEDURE VERIFIED TO BE CORRECT REVISION WITH ALL _______/_______

TEMPORARY CHANGES ATTACHED AND INCORPORATED. INIT/DATE TEST PERFORMERS:

PRINT NAME INIT/DATE PRINT NAME INIT/DATE

/ / / /

2) PRE-TEST REVIEWS: SIGNATURE DATE TIME

/ /

SM/CRS/DESIGNEE AUTH/NOTIF/NI / /

(CIRCLE AS APPLICABLE) / /

3) *TEST DEFICIENCY DESCRIPTION:

/

4) *T/S OR TRM FAILURE? TP INIT / DATE

¨ YES ¨ NO /

SM/CRS/DESIGNEE SIGNATURE DATE IF NO - JUSTIFICATION:

5) *ACTION TAKEN:

EOL # WR/WO#

TEST SUSPENDED ¨ YES ¨ NO /

SM/CRS/DESIGNEE SIGNATURE DATE

SECTIONS 3, 4, AND 5 ARE COMPLETED IF A TEST DEFICIENCY OCCURS. OTHERWISE MARK N/A.

6) POST TEST REVIEWS: (GROUP SUP. CHECK ONE) ¨ COMPLETE ¨ PARTIAL ¨ N/A TOTAL MAN HOURS:

SIGNATURE DATE TIME

/ /

TEST PERFORMER

/ /

SM/CRS/DESIGNEE REVIEW/NOTIF:

GROUP SUPERVISOR:

SC/SURV. TECHNICIAN

7) ADDITIONAL COMMENTS**:

- OPTIONAL INFORMATION NOT REQUIRED TO BE FILLED IN Administrative SRO A1b WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 006-A K/A NO: 2.1.20 COMPLETION TIME: K/A RATING: 4.2 JOB TITLE: SRO REVISION: 0 TASK TITLE: Given initial plant conditions of a SG tube leak, determine from the OFN the required actions.

DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

OFN BB-07A, Steam Generator Tube Leakage TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 006-A SRO A1b Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. SG tube leakage of 45 gallons per day has been detected and the crew is performing OFN BB-07A, Steam Generator Tube Leakage. Radiation Monitor BM RE-25 is not calibrated.

Initiating Cues: You are the Control Room Supervisor. Beginning at step 9 of OFN 7A, document the procedure flowpath and actions to be taken.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide and information only copy of OFN 7A, When the candidate indicates they will perform Attachment C, Steps C1 and C4, cue them that EG RE-92 is now inoperable.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have documented that they will perform Attachment C, Steps C1 and C4. After being cued that EG RE-92 is now inoperable, the Candidate will document that they will perform Step C2 directing that grab samples be performed once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

START TIME:

STOP TIME:

PAGE 1 of 5

JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. *Monitor SG Tube Comments:

Leakage

Monitor Attachment Go to Attachment C, C action level table action level table and take appropriate action STEP 9 S U

2. *Action Level Table Comments:

Action Level 1 Determine that 45 gpd is Action Level 1 and go to step C4 STEP C1

CRITICAL STEP PAGE 2 of 5

JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

3. *IF SG leakage is Comments:

greater than or equal to 30 gpd and less than 75 gpd Identify the trend and the need to monitor at least

Establish NPIS time once per 15 minutes trend Identify that Chemistry

Direct Chemistry to would be notified to take obtain grab samples 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months grab samples Identify that when the leak is stable for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ,

WHEN leak rate the rad monitors will be stabilizes, THEN reset so an increase in the reset radiation rate will cause an alert monitors reflash Indicate that they will

Review procedures review OFN 7A, STN associated with CH-020, OFN MA-38, leakage and rupture EMG E-0, EMG E-3, and the Emergency Plan STEP C4 Procedures. (This is a suggested list. It is not critical that the candidate identify this complete list)

At this point, cue the candidate the Radiation Monitor GE RE-92 is now inoperable.

CRITICAL STEP PAGE 3 of 5

JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

4. *Action Level Table Comments:

Document that Step C2 is

No Operable required Continuous Rad Monitors STEP C1 S U

5. *IF both GE RE-92 and Comments:

BM RE-25 are unavailable for continuous monitoring Indicate that actions

Return them to would be taken to restore service rapidly the radiation monitors to service rapidly.

Direct Chemistry to Direct Chemistry to analyze the off gas analyze off gas grab samples once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months IAW C2 b. table

IF leak rate was Indicate consideration of unstable or increased frequency of increasing THEN sampling and consider more consideration of freqent sampling performing step C5.

Indicate consideration of

Temporay radiation monitors may be used directing that temporary radiation monitors be STEP C2 used IAW Step C2 d.

The JPM is Complete RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 4 of 5

JPM NO: 006-A SRO A1b Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The Plant is in Mode 1. SG tube leakage of 45 gallons per day has been detected and the crew is performing OFN BB-07A, Steam Generator Tube Leakage. Radiation Monitor BM RE-25 is not calibrated.

Initiating Cues: You are the Control Room Supervisor. Beginning at step 9 of OFN 7A, document the procedure flowpath and actions to be taken.

PAGE 5 of 5

Administrative SRO A2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 007-A K/A NO: 2.2.23 COMPLETION TIME: K/A RATING: 3.8 JOB TITLE: SRO REVISION: 0 TASK TITLE: Given a sequence of events, Determine the end time of an LCO including any extensions.

DUTY: Equipment Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

WCGS Integrated Technical Specifications and Bases, LCO 3.5.2 and Section 1.3 TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 007-A SRO A2 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Control Room Supervisor, the Plant is stable in Mode 1.

The A train SI pump has been declared inoperable. The time of discovery is 1000 on 5/08/2004. The B train SI is OPERABLE.

Twelve (12) hours after the A train SI is declared inoperable, the B train RHR pump is declared inoperable.

At 1000 on 5/09/2004, the A train SI pump is restored to OPERABLE status.

Initiating Cues: The Shift Manager directs you to determine when the B train RHR pump must be restored to OPERABLE status to avoid commencing a unit shutdown, including any extensions permitted by Technical Specifications.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Ensure that a copy of Improved Technical Specification is available for the candidate to refer to.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM the candidate will have determined that the extensions allowed by section 1.3, Completion Times, would apply and that LCO 3.5.2 must be exited by 2200 on 12/11/2001.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 007-A SRO A2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U

1. The A train SI pump has been declared Comments:

inoperable. The time of discovery is 1000 on 12/08/2001. The B train SI is OPERABLE.

Twelve (12) hours after the A train SI was declared inoperable, the B train RHR pump is declared inoperable

*Twelve (12) hours Determine that the extensions allowed by after the A train SI was section 1.3, Completion declared inoperable, the Times, would apply and B train RHR pump is that LCO 3.5.2 must be declared inoperable exited by 2200 on 5/11/2004 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 007-A SRO A2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Control Room Supervisor, the Plant is stable in Mode 1.

The A train SI pump has been declared inoperable. The time of discovery is 1000 on 5/08/2004. The B train SI is OPERABLE.

Twelve (12) hours after the A train SI is declared inoperable, the B train RHR pump is declared inoperable.

At 1000 on 5/09/2004, the A train SI pump is restored to OPERABLE status.

Initiating Cues: The Shift Manager directs you to determine when the B train RHR pump must be restored to OPERABLE status to avoid commencing a unit shutdown, including any extensions permitted by Technical Specifications.

PAGE 3 of 3

Administrative SRO A3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 008-A K/A NO: 2.3.6 COMPLETION TIME: K/A RATING: 3.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: Given a Release Permit, review for technical accuracy DUTY: Radiation Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

AP 07B-001, Radioactive Releases AI 07B- 024, Preparation of Containment Purge Permits APF-07B-001-09-08, Containment Purge Release Permit TOOLS/EQUIPMENT:

PREPARER: DATE: 3/09/04

Administrative SRO A3 JPM NO: 008-A SRO A3 Rev 0 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: It is May 11, 2004, at 0800. You are a spare Senior Reactor Operator. A containment purge has been initiated and stopped. The crew is preparing to initiate the purge again. The Reactor Operator has performed the prepatory steps on page 2 of 3 of the release permit provided.

Initiating Cues: The Shift Manager directs you to examine the permit for accuracy and compliance for the reinitiation. Locate and document the three errors on this permit.

The following readings are indicated on the RM11 High Setpoint Low Setpoint GTRE-22/33 2.06E-03 2.06E-04 GTRE-31/32 1.00E-03 5.83E-05 ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Provide the candidate with a copy of the partially completed APF 07B-001-09-08, Containment Purge Release Permit THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: At the completion of this JPM, the Candidate will have documented that:

The RO inadvertently transposed the number for GTRE-22/33 and GTRE-31/32 when establishing the setpoints.

This permit has expired and cannot be used.

The reading for GTG 313 exceeds the restart limit and the purge cannot be reinitiated START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 008-A SRO A3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Note that the RO

1. *Check the release transposed the number for Comments:

conditions GTRE-22/33 and GTRE-31/32 when establishing the setpoints.

Note that the permit has expired

2. *Check the special instructions Note that the reading for GTG 313 exceeds the allowable value for

3. *Check the restart of the purge Authorization Section, Release Data, and the continuation sheet THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 008-A SRO A3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: It is May 11, 2004, at 0800. You are a spare Senior Reactor Operator. A containment purge has been initiated and stopped. The crew is preparing to initiate the purge again. The Reactor Operator has performed the prepatory steps on page 2 of 3 of the release permit provided.

Initiating Cues: The Shift Manager directs you to examine the permit for accuracy and compliance for the reinitiation. Locate and document the three errors on this permit.

The following readings are indicated on the RM11 High Setpoint Low Setpoint GTRE-22/33 2.06E-03 2.06E-04 GTRE-31/32 1.00E-03 5.83E-05 PAGE 3 of 3

APF 07B-001-09-08 Page 1 of 3 CONTAINMENT PURGE RELEASE PERMIT Wolf Creek Nuclear Operating Corporation GRP No. _________________

Date_____________________

K04-008 RELEASE CONDITIONS Containment Atmosphere Activity Containment Monitor Gas Reading Gas _____________µCi/cc Particulate____________µCi/cc GTG313 ___________µCi/cc Tritium_____________µCi/cc Iodine ____________µCi/cc GTG323 ___________µCi/cc Expected Monitor Response (GTG 223/333): ____________ µCi/cc NOTE: Refer to Section 6.6 of SYS SP-121 for setpoint changes.

Containment Purge SP056A Number High Setpoint Low Setpoint (GT RE-22/33) GTG223/GTG333 (Channel Item 009) (Channel Item 010)

______________µCi/cc ______________µCi/cc Containment Atmos. SP056A Number High Setpoint Low Setpoint (GTRE-31/32) GTG313/GTG323 (Channel Item 009) (Channel item 010)

______________µCi/cc ______________µCi/cc SPECIAL INSTRUCTIONS Initiate release prior to: (Date/Time)_______________/____________

Permit Expiration (Date/Time) _______________/____________

Comments:

AUTHORIZATION SECTION Release Permit Initiated by:_______________________/_____________Chemistry Technician Release Permit Verified by:_______________________/_____________Chemistry Tech. or Supervisor Check Source, per STN SP-001:__________________________/_____________Operator Supervisor RM-80 Database Setpoints Entered by:______________________/____________Operator Supervisor RM-80 Database Setpoints Verified by: _____________________/___________Operator Release Approved by: __________________________/_____________Shift Manager RELEASE DATA:

Time/Date Time/Date Exhaust Dampers _______/_______ Exhaust Fan STARTED _______/_______

OPENED Exhaust Dampers _______/_______ Exhuast Fan STOPPED _______/_______

CLOSED Supply Dampers OPENED _______/_______ Supply Fan STARTED _______/_______

Supply Dampers CLOSED _______/_______ Supply Fan STOPPED _______/_______

Mini-Purge Flow Rate= _____________cfm Full Purge Flow Rate= _____________cfm

APF-07B-001-09-08 Page 2 of 3 GRP #_____________________

NOTE: Refer to Section 6.6 of SYS SP-121 for setpoint changes.

Reading Restart Limit Cont. Atmos. Noble Gas Monitor * (GTG 313) ________ µCi/cc _______ µCi/cc

(GTG 323) ________ µCi/cc _______ µCi/cc Check Source, per STN SP-001: ________________/_______Operator Supervisor RM-80 Database Setpoints Entered by: ________________/_______Operator Supervisor RM-80 Database Setpoints Verified ________________/________Operator Release Approved by: ________________/________Shift Manager PART V RELEASE DATA:Date / Time Date / Time Exhaust Dampers OPENED ______/______ Exhaust Fan STARTED ______/______

Exhaust Dampers CLOSED ______/______ Exhaust Fan STOPPED ______/______

Supply Dampers OPENED______/______ Supply Fan STARTED ______/______

Supply Dampers CLOSED______/______ Supply Fan STOPPED ______/______

Mini-Purge Flow Rate = ____________cfm Full Purge Flow Rate = _____________cfm

If Noble Gas Monitor reading is greater than Restart Limit DO NOT restart the purge.

Contact Chemistry for sample required prior to restart.

CONTINUATION SHEET : CONTAINMENT PURGE NOTE: Refer to Section 6.6 of SYS SP-121 for setpoint changes.

Reading Restart Limit Cont. Atmos. Noble Gas Monitor * (GTG 313) ________ µCi/cc ________ µCi/cc

(GTG 323) ________ µCi/cc ________ µ Ci/cc Check Source, per STN SP-001: _________________/_______Operator Supervisor RM-80 Database Setpoints Entered by: ________________/_______Operator Supervisor RM-80 Database Setpoints Verified ________________/_______Operator Release Approved by: ________________/_______Shift Manager PART V RELEASE DATA:Date / Time Date / Time Exhaust Dampers OPENED ______/______ Exhaust Fan STARTED ______/______

Exhaust Dampers CLOSED ______/______ Exhaust Fan STOPPED ______/______

Supply Dampers OPENED______/______ Supply Fan STARTED ______/______

Supply Dampers CLOSED______/______ Supply Fan STOPPED ______/______

Mini-Purge Flow Rate = _____________cfm Full Purge Flow Rate = _____________cfm

If Noble Gas Monitor reading is greater than Restart Limit DO NOT restart the purge.

Contact Chemistry for sample required prior to restart.

Release Packet Data Reviewed by Chemistry Supervisor or designee/Date:____________/______

APF 07B-001-09-08 Page 3 of 3 Containment Purge Checklist GRP#_______________

A. Count 1st Initial 2nd Initial

1. Sample volume

2. Sample date/time

3. Live time

4. Dead time (<15%)

5. Geometry and Geometry shelf

6. >95% of the gamma lines identified

7. Check Ar-41 trend

8. Check H-3 numbers

9. H-3 LLD requirements B. Pre-Release/Permit

1. Release point/permit number

2. Check isotopes

3. Check isotopes added/deleted

4. Check setpoints

5. Check restart limits

6. Permit initiation times

7. Permit expiration time C. Related Paperwork

1. Check isotopes on lowset calculation

2. CDM data

3. Whole Body Dose Rate <1mR/yr

4. Skin Dose Rate<1mR/yr

5. Organ Dose Rate (use highest organ)

<1mR/yr

6. Estimated Curies Released <25 Ci D. Post Release

1. Release Point

2. Release Permit Number

3. Start date/time

4. End date/time

5. Verify minutes calculated are correct

6. Permit started within initiation time

7. Permit expiration time

8. Check restart limits

9. Waste flow rate/total volume

10. Check each isotope

11. Check setpoints

EPP 06-006 PROTECTIVE ACTION RECOMMENDATIONS Responsible Manager Superintendent Emergency Planning Revision Number 3 Use Category Reference Administrative Controls Procedure No Infrequently Performed Procedure No Program Number 06 DC2 04/25/03

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TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 2 4.0 DEFINITIONS 2 5.0 RESPONSIBILITIES 3 6.0 PRECAUTIONS/LIMITATIONS 3 7.0 PROCEDURE 4 8.0 RECORDS 5 9.0 FORMS 5 ATTACHMENT A PROTECTIVE ACTION RECOMMENDATION CHART 6 ATTACHMENT B SUBZONES AFFECTED BY THE WIND DIRECTION 7 ATTACHMENT C 10-MILE EVACUATION TIME ESTIMATES 21 ATTACHMENT D POPULATION BY SUBZONE 23 FIGURE 1 EFFECTIVE 10-MILE EMERGENCY PLANNING ZONE 24

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1.0 PURPOSE{ tc \l 1 1.0 PURPOSE }

1.1 This procedure provides guidelines for Wolf Creek Generating Station to formulate and recommend protective action measures to the State of Kansas and Coffey County authorities.

2.0 SCOPE{ tc \l 1 2.0 SCOPE }

2.1 This procedure is implemented to determine recommendations for protective action(s).

3.0 REFERENCES

AND COMMITMENTS{ tc \l 1

3.0 REFERENCES

AND COMMITMENTS }

3.1 References 3.1.1 EPA-400-R-92-001, May 1992, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 3.1.2 Kansas Protective Action Guides 3.1.3 RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP) 3.1.4 U.S. Food and Drug Administration, Federal Register, Vol. 47, No. 205 - October 22, 1982 3.1.5 USNRC IE Information Notice No. 83-28: Criteria for Protective Action Recommendations for General Emergencies - May 4, 1983 3.2 Commitments 3.2.1 None 4.0 DEFINITIONS{ tc \l 1 4.0 DEFINITIONS }

4.1 Projected Dose 4.1.1 Dose to persons from ionizing radiation which could be received if no protective actions were implemented.

4.2 Protective Actions 4.2.1 Emergency measures taken for preventing or minimizing radiological exposures to affected population groups.

4.3 Protective Action Guides (PAG) 4.3.1 Projected radiological dose to the public that warrant the implementation of protective actions. Protective actions would be warranted if the expected reduction in individual dose is not offset by risks to individual safety caused by implementing the protective action.

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4.4 Protective Action Recommendation (PAR) 4.4.1 A recommendation from WCGS based on an analysis of plant and/or radiological parameters to the State of Kansas and Coffey County, to implement protective measures for the public.

4.5 Emergency Planning Zone (EPZ) 4.5.1 Area for which planning is needed to assure that prompt and effective actions can be taken to protect the public in the event of an accidental release of radioactive material from WCGS.

5.0 RESPONSIBILITIES{ tc \l 1 5.0 RESPONSIBILITIES }

5.1 Emergency Managers 5.1.1 For acquiring plant operational and radiological assessments to evaluate and recommend protective action(s) to the State of Kansas and Coffey County.

6.0 PRECAUTIONS/LIMITATIONS{ tc \l 1 6.0 PRECAUTIONS/LIMITATIONS }

6.1 The authority to transmit protective action recommendations to the State of Kansas and Coffey County shall not be delegated by the Emergency Manager.

6.2 Protective actions outlined in this procedure shall be presented to off-site authorities as recommendations only.

6.3 The final decision-making authority regarding protective action(s) shall be Coffey County for State of Local Disaster Emergencies, and the State of Kansas for State of Disaster Emergencies.

6.4 Recommendations shall be timely in order to achieve the desired degree of protection for the public.

6.5 IF projected doses exceed the EPA PAGs past the 10-mile EPZ, THEN an immediate notification for a PAR for the distance from the plant, as indicated on the Estimated Dose Calculation Program (EDCP), should be made. The Emergency Manager should coordinate with the State Radiological Assessment Manager to have Joint Radiological Monitoring Teams determine the actual dose beyond 10-miles. The State has the authority to develop and implement protective actions outside the 10-mile EPZ.

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7.0 PROCEDURE{ tc \l 1 7.0 PROCEDURE }

7.1 Making Protective Action Recommendations 7.1.1 Upon declaration of an Alert or higher emergency, evaluate the need for making protective action recommendation(s) based on the following:

o Actual or potential radiological releases based on plant conditions o Evaluate actual or potential radiological releases in accordance with EPP 06-012, DOSE ASSESSMENT NOTES o Ingestion Exposure Pathway PARs are developed by the State of Kansas.

o Subzones are based on stability Class A, the most unstable class, and may have to be adjusted by using appropriate isopleths for other stability classes.

7.1.2 Determine the protective action recommendation(s) based on one of the following:

o Affected subzones identified on the EDCP printout.

o ATTACHMENT A, PROTECTIVE ACTION RECOMMENDATION CHART OR the PROTECTIVE ACTION RECOMMENDATION CHART located in the emergency facilities.

o ATTACHMENT B, SUBZONES AFFECTED BY WIND DIRECTION o ATTACHMENT C, 10-MILE EVACUATION TIME ESTIMATES o ATTACHMENT D, POPULATION BY SUBZONE o FIGURE 1, EFFECTIVE 10-MILE EMERGENCY PLANNING ZONE, which identifies the subzone areas on a County map.

7.1.3 Indicate the protective action recommendation on EPF 06-007-01, WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION.

1. Once a PAR has been made, that PAR remains in effect until the event is terminated. All PARs made should be indicated on all notification forms once they are made.

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CAUTION The authority to transmit protective action recommendations to the State of Kansas and Coffey County shall not be delegated by the Emergency Manager.

7.1.4 Ensure transmittal of EPF 06-007-01, WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION, to State of Kansas and Coffey County officials.

7.1.5 Continue to monitor plant and radiological conditions.

IF changes occur, THEN re-evaluate the adequacy of the protective action recommendations.

NOTES o The State has the authority to develop and implement protective actions outside the 10-mile EPZ.

o Positioning of teams beyond ten miles is determined by the State Radiological Assessment Manager.

7.1.6 IF dose projections on EDCP indicate the need for protective actions beyond the 10-mile EPZ, THEN make an immediate notification of the PAR for the distance from the plant as indicated on the EDCP printout.

8.0 RECORDS{ tc \l 1 "8.0 RECORDS" }

8.1 None 9.0 FORMS{ tc \l 1 "9.0 FORMS" }

9.1 None

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ATTACHMENT A (Page 1 of 1)

PROTECTIVE ACTION RECOMMENDATION CHART

{ tc \l 5 "ATTACHMENT A PROTECTIVE ACTION RECOMMENDATION CHART"}ATTACHMENT A" INSTRUCTIONS

1. These protective actions recommendations are for planning purposes only. Practical decisions must take existing conditions into consideration. Conditions to consider are actual threat to the public based on plant conditions, weather, evacuation routes, evacuation times etc. Discussions, taking these conditions into account, with the appropriate State, County, NRC, and FEMA officials may yield recommendations different than those specified by this flow chart.

2. Protective action recommendations should include all subzones meeting or anticipated to meet the projected dose limits.

PRECAUTION Sheltering of the public should be considered as an alternative to evacuation if the dose received during evacuation might be greater than the dose received remaining indoors or the expected risk from radation is offset by safety risks involved in carrying out the protective action.

NOTES:

A. John Redmond Reservoir (JRR) and Coffey County Lake (CCL) are recommended for evacuation as a precautionary measure upon declaration of a Site Area Emergency.

B. Projected severe core damage is indicated by core cooling orange path, or core cooling red path, or heat sink red path. Actual severe core damage is indicated by GTRE59 or 60 reading > 2500 R/Hr.

Continue operational and START radiological assessments.

(See Note A)

No No Are Dose Projections General Actual / Imminent available to make a timely Emergency No release of Yes Protective Action Declared ? radioactivity?

Recommendation?

Yes Yes Are Dose Projections available to make a timely No Protective Action Yes Recommendation?

Projected Dose No TEDE >1Rem OR Thyroid > 1 Rem ?

Actual or Actual or projected severe Imminent breach core damage of three fission No OR No product barriers?

loss of control of facility.

Yes (See Note B)

Protective Action Recommendation Yes Protective Action Yes Recommendation Evacuate JRR, CCL, CTR, and all downwind Subzones SAE- meeting or anticipated to Protective Action Protective Action Protective Action Evacuate JRR, meet the projected dose Recommendation Recommendation Recommendation CCL limits. Use the EAB limits for CTR, the 2 mile limit for Evacuate JRR, Evacuate JRR, Evacuate JRR, GE- 2-5 mile subzones, the 5 CCL, CTR, and CCL, CTR and CCL, and CTR Evacuate JRR, mile limit for 5-10 mile Subzones 2-10 Subzones 2-5 (See Precaution) CCL, & CTR subzones. (See miles downwind. miles downwind (See Precaution) Precaution)

(See Precaution) (See Precaution)

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ATTACHMENT B (Page 1 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION

{ tc \l 5 "ATTACHMENT B SUBZONES AFFECTED BY THE WIND DIRECTION"}ATTACHMENT B" NOTE The data in this Attachment is based on Stability Class A. For other stability classes adjust by using appropriate isopleths.

WIND DIRECTION IN DOWNWIND AFFECTED SUBZONES DEGREES (NPIS) SECTOR FROM TO 0-2 MILES 2-5 MILES 5-10 MILES 0 (360) 180 1 181 2 182 J CTR, CCL SE-1, S-1, SE-3, SE4, S-2, 3 183 JRR SW-2 4 184 5 185 6 186 7 187 8 188 J CTR, CCL SE-1, S-1, SW-1, SE-3, SE-4, S-2, 9 189 JRR SW-2 10 190 11 191 12 192 13 193 14 194 K CTR, CCL SE-1, S-1, SW-1, SE-3, SE-4, S-2, 15 195 JRR SW-2 16 196 17 197 18 198 19 199 20 200 21 201 K CTR, CCL S-1, SW-1, SE-3, S-2, SW-2 22 202 JRR 23 203 24 204 25 205 26 206 27 207 28 208 29 209 30 210 K CTR, CCL S-1, SW-1, W-1, SE-3, S-2, SW-2, 31 211 JRR W-2 32 212 33 213 34 214 35 215 36 216 L CTR, CCL S-1, SW-1, W-1, SE-3, S-2, SW-2, 37 217 JRR W-2 38 218 39 219

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ATTACHMENT B (Page 2 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION 40 220 41 221 42 222 L CTR, CCL S-1, SW-1, W-1, S-2, SW-2, W-2 43 223 JRR 44 224 45 225 46 226

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ATTACHMENT B (Page 3 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION WIND DIRECTION IN DOWNWIND AFFECTED SUBZONES DEGREES (NPIS) SECTOR FROM TO 0-2 MILES 2-5 MILES 5-10 MILES 47 227 L CTR, CCL S-1, SW-1, W-1, S-2, SW-2, W-2 48 228 JRR 49 229 50 230 51 231 52 232 53 233 54 234 55 235 56 236 57 237 58 238 59 239 M CTR, CCL S-1, SW-1, W-1, S-2, SW-2, W-2 60 240 JRR 61 241 62 242 63 243 64 244 M CTR, CCL S-1, SW-1, W-1, S-2, SW-2, W-2 65 245 JRR 66 246 67 247 68 248 69 249 70 250 M CTR, CCL SW-1, W-1, JRR SW-2, W-2 71 251 72 252 73 253 74 254 75 255 76 256 M CTR, CCL SW-1, W-1, NW-1, SW-2, W-2 77 257 JRR 78 258 79 259 80 260 81 261 N CTR, CCL SW-1, W-1, NW-1, SW-2, W-2 82 262 JRR 83 263 84 264 85 265 86 266 87 267 88 268 89 269 90 270 N CTR, CCL SW-1, W-1, NW-1, W-2 91 271 JRR 92 272 93 273 94 274 95 275

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ATTACHMENT B (Page 4 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION 96 276 97 277 98 278 99 279 N CTR, CCL SW-1, W-1, NW-1, W-2, NW-2 100 280 N-1, JRR 101 281

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ATTACHMENT B (Page 5 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION WIND DIRECTION IN DOWNWIND AFFECTED SUBZONES DEGREES (NPIS) SECTOR FROM TO 0-2 MILES 2-5 MILES 5-10 MILES 102 282 103 283 104 284 P CTR, CCL SW-1, W-1, NW-1, W-2, NW-2 105 285 N-1, JRR 106 286 107 287 108 288 109 289 110 290 111 291 112 292 P CTR, CCL W-1, NW-1, N-1, W-2, NW-2 113 293 JRR 114 294 115 295 116 296 117 297 118 298 119 299 120 300 121 301 P CTR, CCL W-1, NW-1, N-1, W-2, NW-2, N-2 122 302 JRR 123 303 124 304 125 305 126 306 Q CTR, CCL W-1, NW-1, N-1, W-2, NW-2, N-2 127 307 JRR 128 308 129 309 130 310 131 311 132 312 133 313 134 314 135 315 136 316 137 317 Q CTR, CCL W-1, NW-1, N-1, NW-2, N-2 138 318 JRR 139 319 140 320 141 321 142 322 143 323 144 324 145 325 146 326 147 327 148 328 149 329 150 330

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ATTACHMENT B (Page 6 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION 151 331 R CTR, CCL W-1, NW-1, N-1, NW-2, N-2 152 332 JRR 153 333 154 334 155 335 156 336

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ATTACHMENT B (Page 7 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION WIND DIRECTION IN DOWNWIND AFFECTED SUBZONES DEGREES (NPIS) SECTOR FROM TO 0-2 MILES 2-5 MILES 5-10 MILES 157 337 158 338 159 339 R CTR, CCL W-1, NW-1, N-1, NW-2, N-2 160 340 JRR 161 341 162 342 163 343 164 344 165 345 R CTR, CCL W-1, NW-1, N-1, NW-2, N-2, NE-2 166 346 NE-1, JRR 167 347 168 348 169 349 170 350 171 351 A CTR, CCL W-1, NW-1, N-1, NW-2, N-2, NE-2 172 352 NE-1, JRR 173 353 174 354 175 355 176 356 177 357 178 358 179 359 A CTR, CCL NW-1, N-1, NE-1, NW-2, N-2, NE-2 180 360 (0) JRR 181 1 182 2 183 3 184 4 185 5 186 6 187 7 188 8 189 9 A CTR, CCL NW-1, N-1, NE-1, NW-2, N-2, NE-2, 190 10 JRR NE-3 191 11 192 12 193 13 194 14 B CTR, CCL NW-1, N-1, NE-1, NW-2, N-2, NE-2, 195 15 JRR NE-3 196 16 197 17 198 18 199 19 200 20 201 21 202 22 B CTR, CCL N-1, NE-1, JRR N-2, NE-2, NE-3 203 23 204 24 205 25

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ATTACHMENT B (Page 8 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION 206 26 207 27 208 28 209 29 B CTR, CCL N-1, NE-1, E-1, N-2, NE-2, NE-3 210 30 JRR 211 31

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ATTACHMENT B (Page 9 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION WIND DIRECTION IN DOWNWIND AFFECTED SUBZONES DEGREES (NPIS) SECTOR FROM TO 0-2 MILES 2-5 MILES 5-10 MILES 212 32 B CTR, CCL N-1, NE-1, E-1, N-2, NE-2, NE-3 213 33 JRR 214 34 215 35 216 36 217 37 218 38 219 39 C CTR, CCL N-1, NE-1, E-1, N-2, NE-2, NE-3 220 40 JRR 221 41 222 42 223 43 224 44 225 45 226 46 227 47 228 48 229 49 230 50 231 51 C CTR, CCL N-1, NE-1, E-1, NE-2, NE-3, E-2 232 52 JRR 233 53 234 54 235 55 236 56 237 57 238 58 239 59 240 60 241 61 242 62 D CTR, CCL N-1, NE-1, E-1, NE-2, NE-3, E-2 243 63 JRR 244 64 245 65 246 66 247 67 248 68 249 69 250 70 251 71 D CTR, CCL NE-1, E-1, JRR NE-3, E-2 252 72 253 73 254 74 255 75 256 76 D CTR, CCL NE-1, E-1, JRR NE-3, E-2, SE-2 257 77 258 78 259 79 260 80

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ATTACHMENT B (Page 10 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION 261 81 E CTR, CCL NE-1, E-1, JRR NE-3, E-2, SE-2 262 82 263 83

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ATTACHMENT B (Page 11 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION WIND DIRECTION IN DOWNWIND AFFECTED SUBZONES DEGREES (NPIS) SECTOR FROM TO 0-2 MILES 2-5 MILES 5-10 MILES 264 84 265 85 266 86 267 87 268 88 269 89 E CTR, CCL NE-1, E-1, JRR NE-3, E-2, SE-2 270 90 271 91 272 92 273 93 274 94 275 95 276 96 277 97 278 98 E CTR, CCL NE-1, E-1, SE-1, NE-3, E-2, SE-2, 279 99 JRR SE-4 280 100 281 101 282 102 283 103 284 104 285 105 286 106 F CTR, CCL E-1, SE-1, JRR NE-3, E-2, SE-2, 287 107 SE-4 288 108 289 109 290 110 291 111 292 112 293 113 294 114 295 115 F CTR, CCL E-1, SE-1, JRR E-2, SE-2, SE-3, 296 116 SE-4 297 117 298 118 299 119 300 120 301 121 F CTR, CCL E-1, SE-1, S-1, E-2, SE-2, SE-3, 302 122 JRR SE-4 303 123 304 124 305 125 306 126 307 127 308 128 309 129 G CTR, CCL E-1, SE-1, S-1, E-2, SE-2, SE-3, 310 130 JRR SE-4 311 131 312 132

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ATTACHMENT B (Page 12 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION 313 133 314 134 315 135 316 136 317 137 G CTR, CCL E-1, SE-1, S-1, E-2, SE-2, SE-3, 318 138 JRR SE-4, S-2 319 139

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ATTACHMENT B (Page 13 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION WIND DIRECTION IN DOWNWIND AFFECTED SUBZONES DEGREES (NPIS) SECTOR FROM TO 0-2 MILES 2-5 MILES 5-10 MILES 320 140 321 141 322 142 323 143 G CTR, CCL E-1, SE-1, S-1, E-2, SE-2, SE-3, 324 144 JRR SE-4, S-2 325 145 326 146 327 147 328 148 329 149 H CTR, CCL E-1, SE-1, S-1, E-2, SE-2, SE-3, 330 150 JRR SE-4, S-2 331 151 332 152 333 153 334 154 335 155 336 156 337 157 338 158 H CTR, CCL E-1, SE-1, S-1, SE-2, SE-3, 339 159 JRR SE-4, S-2 340 160 341 161 342 162 343 163 344 164 345 165 346 166 H CTR, CCL E-1, SE-1, S-1, SE-2, SE-3, 347 167 JRR SE-4, S-2, SW-2 348 168 349 169 350 170 351 171 J CTR, CCL E-1, SE-1, S-1, SE-2, SE-3, 352 172 JRR SE-4, S-2, SW-2 353 173 354 174 355 175 356 176 357 177 J CTR, CCL SE-1, S-1, JRR SE-3, SE-4, S-2, 358 178 SW-2 359 179

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ATTACHMENT B (Page 14 of 7)

SUBZONES AFFECTED BY THE WIND DIRECTION

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ATTACHMENT C (Page 8 of 2) 10-MILE EVACUATION TIME ESTIMATES

{ tc \l 5 "ATTACHMENT C 10-MILE EVACUATION TIME ESTIMATES"}ATTACHMENT C"

NOTES o For all transportation-dependent people, including the non-ambulatory occupants of the Life Care Center of Burlington, Sunset Manor Nursing Home and the Coffey County Hospital, an evacuation time of 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months is estimated using area resources.

An evacuation time of 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months is also estimated for John Redmond Reservoir and Coffey County Lake.

o These evacuation times are based on population figures from the 1980 census. The 1980 figures were larger than the numbers presented in the 2000 census. Because the evacuation times are based on a greater population than what is presently in Coffey County, and because the condition of some of the evacuation routes has improved (e.g. paving), the times are considered to be conservative.

AVERAGE WEATHER CONDITIONS Effective Effective Effective Subzone 2-mile 5-mile 10-mile CTR 42 min 54 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min N-1 - 48 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min NE-1 - 54 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min E-1 - 54 min 54 min SE-1 - 48 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months S-1 - 54 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 12 min SW-1 - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 24 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 30 min W-1 - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min NW-1 - 48 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months N-2 - - 54 min NE-2 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months NE-3 - - 54 min E-2 - - 48 min SE-2 - - 54 min SE-3 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SE-4 - - 42 min S-2 - - 54 min SW-2 - - 54 min W-2 - - 48 min NW-2 - - 42 min

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ATTACHMENT C (Page 9 of 2) 10-MILE EVACUATION TIME ESTIMATES NOTES o For all transportation-dependent people, including the non-ambulatory occupants of the Life Care Center of Burlington, Sunset Manor Nursing Home and the Coffey County Hospital, an evacuation time of 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months is estimated using area resources.

An evacuation time of 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months is also estimated for John Redmond Reservoir and Coffey County Lake.

o These evacuation times are based on population figures from the 1980 census. The 1980 figures were larger than the numbers presented in the 2000 census. Because the evacuation times are based on a greater population than what is presently in Coffey County, and because the condition of some of the evacuation routes has improved (e.g. paving), the times are considered to be conservative.

ADVERSE WEATHER CONDITIONS Subzone Effective Effective Effective 2-mile 5-mile 10-mile CTR 42 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 18 min N-1 - 54 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 18 min NE-1 - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min E-1 - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min SE-1 - 54 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min S-1 - 54 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 24 min SW-1 - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 42 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 48 min W-1 - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 18 min NW-1 - 54 min 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min N-2 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months NE-2 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min NE-3 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months E-2 - - 54 min SE-2 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SE-3 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 6 min SE-4 - - 48 min S-2 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SW-2 - - 54 min W-2 - - 54 min NW-2 - - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

- END -

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Revision: 3 PROTECTIVE ACTION RECOMMENDATIONS EPP 06-006

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Reference Use Page 23 of 23

+-----------------------------------------------------------------------+

ATTACHMENT D (Page 8 of 1)

POPULATION BY SUBZONE

{ tc \l 5 "ATTACHMENT D POPULATION BY SUBZONE"}ATTACHMENT D" Evacuation Subzone Evacuation Zone Population Center (CTR) 0 - 2 75 North-1 (N-1) 2 - 5 65 Northeast-1 (NE-1) 2 - 5 82 East-1 (E-1) 2 - 5 53 Southeast-1 (SE-1) 2 - 5 40 South-1 (S-1) 2 - 5 40 Southwest-1 (SW-1) 2 - 5 2,866 West-1 (W-1) 2 - 5 463 Northwest-1 (NW-1) 2 - 5 82 North-2 (N-2) 5 - 10 121 Northeast-2 (NE-2) 5 - 10 721 Northeast-3 (NE-3) 5 - 10 144 East-2 (E-2) 5 - 10 71 Southeast-2 (SE-2) 5 - 10 138 Southeast-3 (SE-3) 5 - 10 650 Southeast-4 (SE-4) 5 - 10 56 South-2 (S-2) 5 - 10 88 Southwest-2 (SW-2) 5 - 10 88 West-2 (W-2) 5 - 10 142 Northwest-2 (NW-2) 5 - 10 114 Effective 10-Mile Emergency Planning Zone Subtotals:

Effective 0 mile zone = 75 persons Effective 2 mile zone = 3,691 persons Effective 5 mile zone = 2,333 persons Effective 0 mile zone = 6,099 persons Total Coffey County population = 8,865 persons

The Effective 0 mile zone encompasses all of CTR and CCL subzones

- END -

+-----------------------------------------------------------------------+

Revision: 3 PROTECTIVE ACTION RECOMMENDATIONS EPP 06-006

+---------------- +----------------

Reference Use Page 24 of 24

+-----------------------------------------------------------------------+

FIGURE 1 EFFECTIVE

{ tc \l 5 "FIGURE 1 10-MILE EMERGENCY EFFECTIVE PLANNING ZONE 10-MILE EMERGENCY PLANNING ZONE"}FIGURE 1"

JPM 009A-A (Scenario: 1) KEY A-4 EPF 06-007-01 Rev 7 MESSAGE NO.:

WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION

7. RADIOLOGICAL RELEASE STATUS:

1. STATUS: o ACTUAL o DRILL o NONE o PLANNED o MONITORED

2. CODE WORD (County/State only):

o TERMINATED o UNPLANNED o UNMONITORED

3. NOTIFICATION TYPE: (If NONE, N/A steps 10, 11, & 12 for Follow-up o IMMEDIATE (Steps 1-8, & 13) o FOLLOWUP (ALL)

Notifications)

4. EMERGENCY CLASSIFICATION: 8. PROTECTIVE ACTION RECOMMENDATION: o NONE IF making a PAR only, TIME OF PAR:

TIME: DATE: / /

o UNUSUAL EVENT o ALERT o SITE AREA o CCL & JRR 0 - 2 MILES: o CTR o GENERAL o RECOVERY o TERMINATION 2 - 5 MILES: o N-1 o NE-1 o E-1 o SE-1

5. REASON FOR CLASSIFICATION: (EAL) o 1-RER o 2-SGTF o 3-LRCB o 4-MSLB o S-1 o SW-1 o W-1 o NW-1 o 5-FEF o 6-LEP/AC o 7-FHA o 8-SSFM 5 -10 MILES: o N-2 o NE-2 o NE-3 o E-2 o 9-LPC/SC o 10-FR o 11-NP o 12-OH o 13-ADM o SE-2 o SE-3 o SE-4 o S-2 EAL Step Numbers

6. METEOROLOGICAL DATA: o SW-2 o W-2 o NW-2 o

WIND: AT: MPH, FROM: TOWARDS: Degrees

> 10 MILES: DISTANCE FROM PLANT: MILES STABILITY CLASS: PRECIPITATION: o YES o NO

9. CURRENT PLANT CONDITION: o IMPROVING o STABILIZED o DEGRADING TIME REACTOR TRIPPED

10. FIELD TEAM DATA: o Not Available; Time Collected: At Miles From CTMT =

mR/hr GAMMA, (uCi/cc) IODINE, (uCi/cc) PART.

11. RELEASE RATE: Release Start Time: Estimated Total Release Time In Hours:

At (Time) Release Rate = Ci/Sec NOBLE GAS and Ci/Sec RADIOIODINE

12. CENTERLINE DOSES (Based on):

o RAD MONITORING SYSTEM o USAR SOURCE TERM ESTIMATE o FIELD TEAM MONITORING DATA INTEGRATED DOSES PROJECTED (TIME): RELEASE START RELEASE STOPPED TEDE (REM) THYROID (REM)

EAB 2 MI 5 MI 10 MI COMMENTS: [Commitment Step 3.2.1]

13. NOTIFICATION APPROVAL: /

Signature Title (FOR WCNOC USE ONLY) PRIMARY CONTACT ALTERNATE CONTACTS PERSON/TIME COFFEY COUNTY SHERIFF 620-364-2123 STATION RADIO KHP 785-827-4437 KANSAS DIVISION OF 785-296-3176 STATE EOC ACTIVATED EMERGENCY MANAGEMENT LEAVE MESSAGE STATE RADIO 785-274-1422 NRC RESIDENT INSPECTOR OFFICE EXT. FRANK BRUSH Cell: 620-343-0577 4574 Home: 620-364-3631 NRC PAGER 816-466-5209 TOPEKA SYSTEM DISPATCH 785-575-6078

ANI (ALERT OR HIGHER) 860-561-3433; OFF HOURS LEAVE MESSAGE INPO (ALERT OR HIGHER) 800-321-0614

JPM 009B-A (Scenario: 2) KEY A-4 EPF 06-007-01 Rev 7 MESSAGE NO.:

WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION

7. RADIOLOGICAL RELEASE STATUS:

1. STATUS: o ACTUAL o DRILL o NONE o PLANNED o MONITORED

2. CODE WORD (County/State only):

o TERMINATED o UNPLANNED o UNMONITORED

3. NOTIFICATION TYPE: (If NONE, N/A steps 10, 11, & 12 for Follow-up o IMMEDIATE (Steps 1-8, & 13) o FOLLOWUP (ALL)

Notifications)

4. EMERGENCY CLASSIFICATION: 8. PROTECTIVE ACTION RECOMMENDATION: o NONE IF making a PAR only, TIME OF PAR:

TIME: DATE: / /

o UNUSUAL EVENT o ALERT o SITE AREA o CCL & JRR 0 - 2 MILES: o CTR o GENERAL o RECOVERY o TERMINATION 2 - 5 MILES: o N-1 o NE-1 o E-1 o SE-1

5. REASON FOR CLASSIFICATION: (EAL) o 1-RER o 2-SGTF o 3-LRCB o 4-MSLB o S-1 o SW-1 o W-1 o NW-1 o 5-FEF o 6-LEP/AC o 7-FHA o 8-SSFM 5 -10 MILES: o N-2 o NE-2 o NE-3 o E-2 o 9-LPC/SC o 10-FR o 11-NP o 12-OH o 13-ADM o SE-2 o SE-3 o SE-4 o S-2 EAL Step Numbers

6. METEOROLOGICAL DATA: o SW-2 o W-2 o NW-2 o

WIND: AT: MPH, FROM: TOWARDS: Degrees

> 10 MILES: DISTANCE FROM PLANT: MILES STABILITY CLASS: PRECIPITATION: o YES o NO

9. CURRENT PLANT CONDITION: o IMPROVING o STABILIZED o DEGRADING TIME REACTOR TRIPPED

10. FIELD TEAM DATA: o Not Available; Time Collected: At Miles From CTMT =

mR/hr GAMMA, (uCi/cc) IODINE, (uCi/cc) PART.

11. RELEASE RATE: Release Start Time: Estimated Total Release Time In Hours:

At (Time) Release Rate = Ci/Sec NOBLE GAS and Ci/Sec RADIOIODINE

12. CENTERLINE DOSES (Based on):

o RAD MONITORING SYSTEM o USAR SOURCE TERM ESTIMATE o FIELD TEAM MONITORING DATA INTEGRATED DOSES PROJECTED (TIME): RELEASE START RELEASE STOPPED TEDE (REM) THYROID (REM)

EAB 2 MI 5 MI 10 MI COMMENTS: [Commitment Step 3.2.1]

13. NOTIFICATION APPROVAL: /

Signature Title (FOR WCNOC USE ONLY) PRIMARY CONTACT ALTERNATE CONTACTS PERSON/TIME COFFEY COUNTY SHERIFF 620-364-2123 STATION RADIO KHP 785-827-4437 KANSAS DIVISION OF 785-296-3176 STATE EOC ACTIVATED EMERGENCY MANAGEMENT LEAVE MESSAGE STATE RADIO 785-274-1422 NRC RESIDENT INSPECTOR OFFICE EXT. FRANK BRUSH Cell: 620-343-0577 4574 Home: 620-364-3631 NRC PAGER 816-466-5209 TOPEKA SYSTEM DISPATCH 785-575-6078

ANI (ALERT OR HIGHER) 860-561-3433; OFF HOURS LEAVE MESSAGE INPO (ALERT OR HIGHER) 800-321-0614

JPM 009B-A (Scenario: 2) KEY A-4 EPF 06-007-01 Rev 7 MESSAGE NO.:

WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION

7. RADIOLOGICAL RELEASE STATUS:

1. STATUS: o ACTUAL o DRILL o NONE o PLANNED o MONITORED

2. CODE WORD (County/State only):

o TERMINATED o UNPLANNED o UNMONITORED

3. NOTIFICATION TYPE: (If NONE, N/A steps 10, 11, & 12 for Follow-up o IMMEDIATE (Steps 1-8, & 13) o FOLLOWUP (ALL)

Notifications)

4. EMERGENCY CLASSIFICATION: 8. PROTECTIVE ACTION RECOMMENDATION: o NONE IF making a PAR only, TIME OF PAR:

TIME: DATE: / /

o UNUSUAL EVENT o ALERT o SITE AREA o CCL & JRR 0 - 2 MILES: o CTR o GENERAL o RECOVERY o TERMINATION 2 - 5 MILES: o N-1 o NE-1 o E-1 o SE-1

5. REASON FOR CLASSIFICATION: (EAL) o 1-RER o 2-SGTF o 3-LRCB o 4-MSLB o S-1 o SW-1 o W-1 o NW-1 o 5-FEF o 6-LEP/AC o 7-FHA o 8-SSFM 5 -10 MILES: o N-2 o NE-2 o NE-3 o E-2 o 9-LPC/SC o 10-FR o 11-NP o 12-OH o 13-ADM o SE-2 o SE-3 o SE-4 o S-2 EAL Step Numbers

6. METEOROLOGICAL DATA: o SW-2 o W-2 o NW-2 o

WIND: AT: MPH, FROM: TOWARDS: Degrees

> 10 MILES: DISTANCE FROM PLANT: MILES STABILITY CLASS: PRECIPITATION: o YES o NO

9. CURRENT PLANT CONDITION: o IMPROVING o STABILIZED o DEGRADING TIME REACTOR TRIPPED

10. FIELD TEAM DATA: o Not Available; Time Collected: At Miles From CTMT =

mR/hr GAMMA, (uCi/cc) IODINE, (uCi/cc) PART.

11. RELEASE RATE: Release Start Time: Estimated Total Release Time In Hours:

At (Time) Release Rate = Ci/Sec NOBLE GAS and Ci/Sec RADIOIODINE

12. CENTERLINE DOSES (Based on):

o RAD MONITORING SYSTEM o USAR SOURCE TERM ESTIMATE o FIELD TEAM MONITORING DATA INTEGRATED DOSES PROJECTED (TIME): RELEASE START RELEASE STOPPED TEDE (REM) THYROID (REM)

EAB 2 MI 5 MI 10 MI COMMENTS: [Commitment Step 3.2.1]

13. NOTIFICATION APPROVAL: /

Signature Title (FOR WCNOC USE ONLY) PRIMARY CONTACT ALTERNATE CONTACTS PERSON/TIME COFFEY COUNTY SHERIFF 620-364-2123 STATION RADIO KHP 785-827-4437 KANSAS DIVISION OF 785-296-3176 STATE EOC ACTIVATED EMERGENCY MANAGEMENT LEAVE MESSAGE STATE RADIO 785-274-1422 NRC RESIDENT INSPECTOR OFFICE EXT. FRANK BRUSH Cell: 620-343-0577 4574 Home: 620-364-3631 NRC PAGER 816-466-5209 TOPEKA SYSTEM DISPATCH 785-575-6078

ANI (ALERT OR HIGHER) 860-561-3433; OFF HOURS LEAVE MESSAGE INPO (ALERT OR HIGHER) 800-321-0614

JPM 009C-A (Scenario: 3) KEY A-4 EPF 06-007-01 Rev 7 MESSAGE NO.:

WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION

7. RADIOLOGICAL RELEASE STATUS:

1. STATUS: o ACTUAL o DRILL o NONE o PLANNED o MONITORED

2. CODE WORD (County/State only):

o TERMINATED o UNPLANNED o UNMONITORED

3. NOTIFICATION TYPE: (If NONE, N/A steps 10, 11, & 12 for Follow-up o IMMEDIATE (Steps 1-8, & 13) o FOLLOWUP (ALL)

Notifications)

4. EMERGENCY CLASSIFICATION: 8. PROTECTIVE ACTION RECOMMENDATION: o NONE IF making a PAR only, TIME OF PAR:

TIME: DATE: / /

o UNUSUAL EVENT o ALERT o SITE AREA o CCL & JRR 0 - 2 MILES: o CTR o GENERAL o RECOVERY o TERMINATION 2 - 5 MILES: o N-1 o NE-1 o E-1 o SE-1

5. REASON FOR CLASSIFICATION: (EAL) o 1-RER o 2-SGTF o 3-LRCB o 4-MSLB o S-1 o SW-1 o W-1 o NW-1 o 5-FEF o 6-LEP/AC o 7-FHA o 8-SSFM 5 -10 MILES: o N-2 o NE-2 o NE-3 o E-2 o 9-LPC/SC o 10-FR o 11-NP o 12-OH o 13-ADM o SE-2 o SE-3 o SE-4 o S-2 EAL Step Numbers

6. METEOROLOGICAL DATA: o SW-2 o W-2 o NW-2 o

WIND: AT: MPH, FROM: TOWARDS: Degrees

> 10 MILES: DISTANCE FROM PLANT: MILES STABILITY CLASS: PRECIPITATION: o YES o NO

9. CURRENT PLANT CONDITION: o IMPROVING o STABILIZED o DEGRADING TIME REACTOR TRIPPED

10. FIELD TEAM DATA: o Not Available; Time Collected: At Miles From CTMT =

mR/hr GAMMA, (uCi/cc) IODINE, (uCi/cc) PART.

11. RELEASE RATE: Release Start Time: Estimated Total Release Time In Hours:

At (Time) Release Rate = Ci/Sec NOBLE GAS and Ci/Sec RADIOIODINE

12. CENTERLINE DOSES (Based on):

o RAD MONITORING SYSTEM o USAR SOURCE TERM ESTIMATE o FIELD TEAM MONITORING DATA INTEGRATED DOSES PROJECTED (TIME): RELEASE START RELEASE STOPPED TEDE (REM) THYROID (REM)

EAB 2 MI 5 MI 10 MI COMMENTS: [Commitment Step 3.2.1]

13. NOTIFICATION APPROVAL: /

Signature Title (FOR WCNOC USE ONLY) PRIMARY CONTACT ALTERNATE CONTACTS PERSON/TIME COFFEY COUNTY SHERIFF 620-364-2123 STATION RADIO KHP 785-827-4437 KANSAS DIVISION OF 785-296-3176 STATE EOC ACTIVATED EMERGENCY MANAGEMENT LEAVE MESSAGE STATE RADIO 785-274-1422 NRC RESIDENT INSPECTOR OFFICE EXT. FRANK BRUSH Cell: 620-343-0577 4574 Home: 620-364-3631 NRC PAGER 816-466-5209 TOPEKA SYSTEM DISPATCH 785-575-6078

ANI (ALERT OR HIGHER) 860-561-3433; OFF HOURS LEAVE MESSAGE INPO (ALERT OR HIGHER) 800-321-0614

JPM 009D-A (Scenario: 4) KEY A-4 EPF 06-007-01 Rev 7 MESSAGE NO.:

WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION

7. RADIOLOGICAL RELEASE STATUS:

1. STATUS: o ACTUAL o DRILL o NONE o PLANNED o MONITORED

2. CODE WORD (County/State only):

o TERMINATED o UNPLANNED o UNMONITORED

3. NOTIFICATION TYPE: (If NONE, N/A steps 10, 11, & 12 for Follow-up o IMMEDIATE (Steps 1-8, & 13) o FOLLOWUP (ALL)

Notifications)

4. EMERGENCY CLASSIFICATION: 8. PROTECTIVE ACTION RECOMMENDATION: o NONE IF making a PAR only, TIME OF PAR:

TIME: DATE: / /

o UNUSUAL EVENT o ALERT o SITE AREA o CCL & JRR 0 - 2 MILES: o CTR o GENERAL o RECOVERY o TERMINATION 2 - 5 MILES: o N-1 o NE-1 o E-1 o SE-1

5. REASON FOR CLASSIFICATION: (EAL) o 1-RER o 2-SGTF o 3-LRCB o 4-MSLB o S-1 o SW-1 o W-1 o NW-1 o 5-FEF o 6-LEP/AC o 7-FHA o 8-SSFM 5 -10 MILES: o N-2 o NE-2 o NE-3 o E-2 o 9-LPC/SC o 10-FR o 11-NP o 12-OH o 13-ADM o SE-2 o SE-3 o SE-4 o S-2 EAL Step Numbers

6. METEOROLOGICAL DATA: o SW-2 o W-2 o NW-2 o

WIND: AT: MPH, FROM: TOWARDS: Degrees

> 10 MILES: DISTANCE FROM PLANT: MILES STABILITY CLASS: PRECIPITATION: o YES o NO

9. CURRENT PLANT CONDITION: o IMPROVING o STABILIZED o DEGRADING TIME REACTOR TRIPPED

10. FIELD TEAM DATA: o Not Available; Time Collected: At Miles From CTMT =

mR/hr GAMMA, (uCi/cc) IODINE, (uCi/cc) PART.

11. RELEASE RATE: Release Start Time: Estimated Total Release Time In Hours:

At (Time) Release Rate = Ci/Sec NOBLE GAS and Ci/Sec RADIOIODINE

12. CENTERLINE DOSES (Based on):

o RAD MONITORING SYSTEM o USAR SOURCE TERM ESTIMATE o FIELD TEAM MONITORING DATA INTEGRATED DOSES PROJECTED (TIME): RELEASE START RELEASE STOPPED TEDE (REM) THYROID (REM)

EAB 2 MI 5 MI 10 MI COMMENTS: [Commitment Step 3.2.1]

13. NOTIFICATION APPROVAL: /

Signature Title (FOR WCNOC USE ONLY) PRIMARY CONTACT ALTERNATE CONTACTS PERSON/TIME COFFEY COUNTY SHERIFF 620-364-2123 STATION RADIO KHP 785-827-4437 KANSAS DIVISION OF 785-296-3176 STATE EOC ACTIVATED EMERGENCY MANAGEMENT LEAVE MESSAGE STATE RADIO 785-274-1422 NRC RESIDENT INSPECTOR OFFICE EXT. FRANK BRUSH Cell: 620-343-0577 4574 Home: 620-364-3631 NRC PAGER 816-466-5209 TOPEKA SYSTEM DISPATCH 785-575-6078

ANI (ALERT OR HIGHER) 860-561-3433; OFF HOURS LEAVE MESSAGE INPO (ALERT OR HIGHER) 800-321-0614

EPF 06-007-01 Rev 7 MESSAGE NO.:

WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION

7. RADIOLOGICAL RELEASE STATUS:

1. STATUS: o ACTUAL o DRILL o NONE o PLANNED o MONITORED

2. CODE WORD (County/State only):

o TERMINATED o UNPLANNED o UNMONITORED

3. NOTIFICATION TYPE: (If NONE, N/A steps 10, 11, & 12 for Follow-up o IMMEDIATE (Steps 1-8, & 13) o FOLLOWUP (ALL)

Notifications)

4. EMERGENCY CLASSIFICATION: 8. PROTECTIVE ACTION RECOMMENDATION: o NONE IF making a PAR only, TIME OF PAR:

TIME: DATE: / /

o UNUSUAL EVENT o ALERT o SITE AREA o CCL & JRR 0 - 2 MILES: o CTR o GENERAL o RECOVERY o TERMINATION 2 - 5 MILES: o N-1 o NE-1 o E-1 o SE-1

5. REASON FOR CLASSIFICATION: (EAL) o 1-RER o 2-SGTF o 3-LRCB o 4-MSLB o S-1 o SW-1 o W-1 o NW-1 o 5-FEF o 6-LEP/AC o 7-FHA o 8-SSFM 5 -10 MILES: o N-2 o NE-2 o NE-3 o E-2 o 9-LPC/SC o 10-FR o 11-NP o 12-OH o 13-ADM o SE-2 o SE-3 o SE-4 o S-2 EAL Step Numbers

6. METEOROLOGICAL DATA: o SW-2 o W-2 o NW-2 o

WIND: AT: MPH, FROM: TOWARDS: Degrees

> 10 MILES: DISTANCE FROM PLANT: MILES STABILITY CLASS: PRECIPITATION: o YES o NO

9. CURRENT PLANT CONDITION: o IMPROVING o STABILIZED o DEGRADING TIME REACTOR TRIPPED

10. FIELD TEAM DATA: o Not Available; Time Collected: At Miles From CTMT =

mR/hr GAMMA, (uCi/cc) IODINE, (uCi/cc) PART.

11. RELEASE RATE: Release Start Time: Estimated Total Release Time In Hours:

At (Time) Release Rate = Ci/Sec NOBLE GAS and Ci/Sec RADIOIODINE

12. CENTERLINE DOSES (Based on):

o RAD MONITORING SYSTEM o USAR SOURCE TERM ESTIMATE o FIELD TEAM MONITORING DATA INTEGRATED DOSES PROJECTED (TIME): RELEASE START RELEASE STOPPED TEDE (REM) THYROID (REM)

EAB 2 MI 5 MI 10 MI COMMENTS: [Commitment Step 3.2.1]

13. NOTIFICATION APPROVAL: /

Signature Title (FOR WCNOC USE ONLY) PRIMARY CONTACT ALTERNATE CONTACTS PERSON/TIME COFFEY COUNTY SHERIFF 620-364-2123 STATION RADIO KHP 785-827-4437 KANSAS DIVISION OF 785-296-3176 STATE EOC ACTIVATED EMERGENCY MANAGEMENT LEAVE MESSAGE STATE RADIO 785-274-1422 NRC RESIDENT INSPECTOR OFFICE EXT. FRANK BRUSH Cell: 620-343-0577 4574 Home: 620-364-3631 NRC PAGER 816-466-5209 TOPEKA SYSTEM DISPATCH 785-575-6078

ANI (ALERT OR HIGHER) 860-561-3433; OFF HOURS LEAVE MESSAGE INPO (ALERT OR HIGHER) 800-321-0614

Administrative (Simulator Scenario #1) SRO A4 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 009A-A K/A NO: 2.4.41 COMPLETION TIME: K/A RATING: 4.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: After observing an event on the simulator, make the E-plan Classification and Protective Action Recommendation.

DUTY: Emergency Plan The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

AP 06-002, Radiological Emergency Response Plan EPP 06-001, Control Room Operations EPP 06-005, Emergency Classification EPP 06-006, Protective Action Recommendations APF 06-002-01, Emergency Action Levels EPF 06-007-01, WCGS Emergency Notification TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04

JPM NO: 009A-A SRO A4 Rev 0 (Scenario #1)

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Shift Manager.

Initiating Cues: Analyze the events you have just experienced on the simulator, complete items 4, 5, 7, and 8 of an EPF 06-007-01, WCGS Emergency Notification form (provided). Use current plant status.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: Present the blank Emergency Notification Form attached to this JPM.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have made the correct classification and the correct protective action recommendation per the performance page for the scenario just completed.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 009A-A SRO A4 Rev 0 (Scenario #1)

TASK NUMBER - ELEMENT CUE STANDARD SCORE S U EAL

1. *The classification for Comments:

Scenario #1 8-SSFM1 - No 8-SSFM4 - Yes 8-SSFM5 - Yes 8-SSFM6 - No Site Area Emergency

2. *Perform Attachment A PAR of EPP 06-006 Complete EMERGENCY ACTION NOTIFICATION as indicated on attached Key.

Sections 4, 5, 7, and 8 are critical THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 009A-A SRO A4 Rev 0 (Scenario #1)

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Shift Manager.

Initiating Cues: Analyze the events you have just experienced on the simulator, complete items 4, 5, 7, and 8 of an EPF 06-007-01, WCGS Emergency Notification form (provided). Use current plant status.

PAGE 3 of 3

Administrative (Simulator Scenario #2) SRO A-4 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 009B-A K/A NO: 2.4.41 COMPLETION TIME: K/A RATING: 4.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: After observing an event on the simulator, make the E-plan Classification and Protective Action Recommendation.

DUTY: Emergency Plan The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

AP 06-002, Radiological Emergency Response Plan EPP 06-001, Control Room Operations EPP 06-005, Emergency Classification EPP 06-006, Protective Action Recommendations APF 06-002-01, Emergency Action Levels EPF 06-007-01, WCGS Emergency Notification TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 009B-A SRO A-4 Rev 0 (Scenario #2)

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Shift Manager.

Initiating Cues: Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: After the Candidate indicates they would obtain the Emergency Notification form from the Shift Managers desk drawer, present the blank form attached to this JPM.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have made the correct classification and the correct protective action recommendation per the performance page for the scenarion just completed.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 009B-A SRO A-4 Rev 0 (Scenario #2)

TASK NUMBER - ELEMENT CUE STANDARD SCORE S U EAL

1. *The classification for Comments:

Scenario #2 2-SGTF1 - Yes 2-SGTF2 - NO 2-SGTF9 - Yes 2-SGTF10 - No 2-SGTF12 - No Alert

2. *Perform Attachment A PAR of EPP 06-006 Complete EMERGENCY ACTION NOTIFICATION as indicated on attached Key.

Sections 4, 5, 7, and 8 are critical THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 009B-A SRO A-4 Rev 0 (Scenario #2)

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Shift Manager.

Initiating Cues: Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

PAGE 3 of 3

Administrative (Simulator Scenario #3) SRO A-4 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 009C-A K/A NO: 2.4.41 COMPLETION TIME: K/A RATING: 4.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: After observing an event on the simulator, make the E-plan Classification and Protective Action Recommendation.

DUTY: Emergency Plan The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

AP 06-002, Radiological Emergency Response Plan EPP 06-001, Control Room Operations EPP 06-005, Emergency Classification EPP 06-006, Protective Action Recommendations APF 06-002-01, Emergency Action Levels EPF 06-007-01, WCGS Emergency Notification TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 009C-A SRO A-4 Rev 0 (Scenario #3)

Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Shift Manager.

Initiating Cues: Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: After the Candidate indicates they would obtain the Emergency Notification form from the Shift Managers desk drawer, present the blank form attached to this JPM.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have made the correct classification and the correct protective action recommendation per the performance page for the scenarion just completed.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 009C-A SRO A-4 Rev 0 (Scenario #3)

TASK NUMBER - ELEMENT CUE STANDARD SCORE S U EAL

1. *This classification is Comments:

for Scenario #3 12-OH1 - No 12-OH3 - No NOTE: Cue must have 12-OH4 - Yes been given during the scenario that the steam 12-OH6 - Yes line break caused damage in Area 5. See EAL 12 Alert Block 4 Background

2. *Perform Attachment A PAR of EPP 06-006 Perform Attachment A of EPP 06-006 Complete EMERGENCY ACTION NOTIFICATION as indicated on attached Key.

Sections 4, 5, 7, and 8 are critical THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 009C-A SRO A-4 Rev 0 (Scenario #3)

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Shift Manager.

Initiating Cues: Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

PAGE 3 of 3

Administrative (Simulator Scenario #4) SRO A-4 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 009D-A K/A NO: 2.4.41 COMPLETION TIME: K/A RATING: 4.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: After observing an event on the simulator, make the E-plan Classification and Protective Action Recommendation.

DUTY: Emergency Plan The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

TASK PERFORMER:

LOCATION OF PERFORMANCE:

CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X

REFERENCES:

AP 06-002, Radiological Emergency Response Plan EPP 06-001, Control Room Operations EPP 06-005, Emergency Classification EPP 06-006, Protective Action Recommendations APF 06-002-01, Emergency Action Levels EPF 06-007-01, WCGS Emergency Notification TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04

JPM NO: 009D-A SRO A-4 Rev 0 Scenario #4 Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Shift Manager.

Initiating Cues: Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.

Notes: After the Candidate indicates they would obtain the Emergency Notification form from the Shift Managers desk drawer, present the blank form attached to this JPM.

THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)

Task Standard: Upon completion of this JPM, the Candidate will have made the correct classification and the correct protective action recommendation per the performance page for the scenarion just completed.

START TIME:

STOP TIME:

PAGE 1 of 3

JPM NO: 009D-A SRO A-4 Rev 0 Scenario #4 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U EAL

1. *This classification is Comments:

for Backup Scenario #4 3-LRCB1 - Yes 3-LRCB2 - Yes 3-LRCB3 - No 3-LRCB5 - Yes 3-LRCB6 - No 3-LRCB7 - No Alert

2. *Perform Attachment A PAR of EPP 06-006 Perform Attachment A of EPP 06-006 Complete EMERGENCY ACTION NOTIFICATION as indicated on attached Key.

Sections 4, 5, 7, and 8 are critical THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1

CRITICAL STEP PAGE 2 of 3

JPM NO: 009D-A SRO A-4 Rev 0 Scenario #4 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: You are the Shift Manager.

Initiating Cues: Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.

PAGE 3 of 3

INITIAL LICENSE EXAM OPERATING TEST # 1 SCENARIO # 1 Revision 02 Week of May 10, 2004

OP-TEST #1 SCENARIO #1 Page 2 of 2 Facility: Wolf Creek NRC Scenario No.: 1 Op-Test No.: 1 Revision 02 Source:

New X Bank - Significantly Modified Bank - Initial Condition Change See page 3 for Examiner/student assignments Initial Conditions: 100% Power, MOL, A MDAFWP is OOS for bearing replacement.

A Safety Injection Pump is OOS for oil change.

Severe Thunderstorm Warning for Coffey County.

Turnover: Maintain current plant conditions.

Event Malf. Event Event No. No. Type* Description 1 mRCS I Loop Two Thot average channel fails high.

T+1 01B 2 mMSS I Steam Header Pressure Channel fails low. (Affects both MFPs)

T+14 13 3 mPRS C Pzr Spray Valve fails full open in Automatic.

T+22 03A 4 mEPS C Vital 4160volt NB02 bus lockout T+27 06B 5 N (BOP)

N/A Tech Spec Required Shutdown due to loss of two AFW pumps.

T+45 R (RO) 6 mFWM M Main Feed Line break in Turbine Building T+60 20 7 mAFW C TDAFW pump fails. Entry to FR-H1.

T+63 02B 8 C A CCP fails to Auto Start on Safety Injection.

T+72

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

OP-TEST #1 SCENARIO #1 Page 3 of 3 Scenario # 1 Crew Assignments Session 1 Crew A Examiners Applicants E1: CRS: SRO-U E2: RO: RO1 E3: BOP: RO2 Session 2 Crew C Examiners Applicants CRS: Surrogate E2: RO: SRO-I3 E1: BOP: RO4 Session 3 Crew B Examiners Applicants CRS: Surrogate E3: RO: SRO-I4 E4: BOP: RO5 Session 4 Crew D Examiners Applicants E4: CRS: SRO-I1 E3: RO: SRO-I2 E1: BOP: RO3

OP-TEST #1 SCENARIO #1 Page 4 of 4 SCENARIO MISCELLANEOUS INFORMATION SCENARIO OBJECTIVE:

The objective for this scenario is to mitigate a Loss of Heat Sink event by initiating feed and bleed using plant procedures. Initial conditions have one Aux Feedwater (AFW) pump and one Safety Injection (SI) pump out of service for maintenance. The scenario contains a loop 2 temperature instrument failure, a steam header pressure instrument failure and failure of the controller for one PZR spray valve. All will require operator action to prevent a reactor trip. These are followed by a loss of one vital 4160 volt AC bus. The crew must start the alternate train cooling systems to prevent a loss of the reactor coolant pumps (RCP).

The SRO will evaluate technical specifications associated with the loop temperature failure and the vital AC bus loss. For the vital AC bus loss, numerous tech specs are involved, however the SRO must realize the limiting specifications is for AFW, since two pumps are now inoperable, requiring the unit to be in Mode 3 within six hours. The crew will be cued to commence a 1% per minute downpower The major event is a feed line break in the turbine building and a subsequent loss of the Turbine Driven AFW pump. This places the crew in a red path, Loss of Heat Sink, functional recovery procedure. The crew will meet requirements to initiate bleed and feed to the reactor coolant system (RCS). The crew must realize that the only available high head injection pump did not autostart and manually start it to establish a feed path to the RCS. The scenario terminates when the crew has completed the bleed and feed portion of the functional recovery procedure.

The following is the expected major procedure flow path:

OFN SB-008, INSTRUMENT MALFUNCTIONS

OFN NB-030, LOSS OF AC EMRGENCY BUS NB01 (NB02)

OFN MA-038, RAPID PLANT SHUTDOWN

EMG E-0, REACTOR TRIP OR SAFETY INJECTION

EMG ES-02, REACTOR TRIP RESPONSE

EMG FR-H1, LOSS OF HEAT SINK CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance when the scenario is completed:

Vital AC bus failure:

RCP bearing and motor temperatures.

Loss of Heat Sink S/G Wide Range Levels RCS pressure Hot Leg/Incore Temperatures High head injection flow (BIT)

PZR PORV and block valve status.

OPERATOR ACTIONS TABLE NOTES:

OP-TEST #1 SCENARIO #1 Page 5 of 5

1. Critical Tasks are indicated by a bolded "C" in the position column and in bold type in the actions column.

2. Actions required throughout the event are indicated as "(continuous)" in the position column.

3. Shaded cells indicate procedural entry points.

OP-TEST #1 SCENARIO #1 Page 6 of 6 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 1 Event

Description:

Loop Two Thot average channel fails high.

Time Position Applicant's Actions or Behavior Notes Notices and communicates to the crew RO rods stepping in.

Verifies and communicates, no loss of BOP load has occurred.

Rods must be placed in manual RO Places rod control in manual.

in time to prevent a Rx Trip.

Acknowledge communications and that rod CRS control is in manual.

Notes that Tavg and Delta T indication on RO Loop Bravo are high.

Enter and direct OFN SB-008, Instrument CRS Malfunctions, Attachment L. Steps L1 and L2 are already complete.

Checks steam dumps in Tavg mode and BOP dumps are closed.

Confirms Loop 2 temperature channel failed.

RO Selects loop 2 on Tavg / DT defeat switches.

Conduct Reactivity brief and withdraw control rods back to the parked position.

BOP Peer check rod motion. Management Expectation that CRS/RO all reactivity actions be peer Checks Tavg/Tref within 1 degree checked.

Place rod control in Automatic.

Monitor Rod Control System.

OP-TEST #1 SCENARIO #1 Page 7 of 7 OPERATOR ACTIONS (Event 1 continued)

On Miscellaneous Bi-Stable Panel, checks C-7 interlock not lit.

Check Steam Dump Bypass interlock BOP switches in ON Monitor Steam Dump System.

Check Failed Temperature Channel not used on OPDT and OTDT recorders.

Contact Work Week Manager (WWM) and request I&C assistance to trip bi-stables and repair channel.

Review and comply with Tech Specs.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to place channel in trip CRS T.S. 3.3.1 Reactor Trip System or be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Condition A Table 3.3.1-1, Functions 6 and 7.

Control Rods are in automatic and Termination Criteria: returned to the park position. Tech Spec time limit has been identified.

OP-TEST #1 SCENARIO #1 Page 8 of 8 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 2 Event

Description:

Steam Header Pressure Channel fails low. (Affects both MFPs)

Time Position Applicant's Actions or Behavior Notes Notes and communicates that level is BOP decreasing in all four S/Gs.

Master Speed Controller must Communicate and takes manual control of be placed in manual and SG CRS/BOP the Master MFP Speed controller. levels stabilized in time to prevent a Rx Trip.

Identify Steam Header Pressure channel RO/BOP 507 has failed low.

Enter and direct OFN SB-008, Instrument CRS Malfunctions, Attachment B.

Verify Steam Header Pressure channel malfunction.

RO/BOP Check Steam Dump select switch NOT in Steam Pressure Mode.

Manually control MFP speed.

At 100% power Main Feed Establish dP IAW Figure 1.

BOP header pressure should read (Operator may match steam and feed flows, (Continuous) ~165 psi higher than S/G then adjust MFP speed to maintain FRVs pressure.

positioned at ~ 80%.)

Place Steam Header Pressure Controller in BOP manual.

Contact WWM to request I&C repair failed CRS channel.

MFP speed controller in manual, all S/G Termination Criteria: levels stable or trending to program level (50%).

OP-TEST #1 SCENARIO #1 Page 9 of 9 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 3 Event

Description:

PZR Spray Valve A fails full open in Automatic.

Time Position Applicant's Actions or Behavior Notes RO/BOP/ Note and Communicate that RCS pressure CRS is decreasing.

Monitor RCS pressure for entry into DNB RO/BOP/

Tech. Spec. at < 2220 psig. T.S. 3.4.1, two hours to restore.

CRS As RCS pressure decreases to < 2220, the CRS/RO crew may energize 2nd set of PZR back-up heaters.

Note and communicate A Spray valve is A spray controller must be failing open.

RO placed in Manual and closed in Place A spray controller in Manual and time to prevent a Rx Trip.

close A spray valve.

Enter and direct OFN SB-008, Instrument CRS Malfunctions, Attachment V.

Verify A Spray Valve controller failed RO open in auto and is now in manual/closed.

Contact WWM to request I&C repair failed CRS channel.

A Spray Valve Controller in Termination Criteria: manual/closed. RCS pressure stable at or trending to program (2235).

OP-TEST #1 SCENARIO #1 Page 10 of 10 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 4 Event

Description:

Vital 4160 volt NB02 bus lockout.

Time Position Applicant's Actions or Behavior Notes Acknowledge and communicates RO/CRS annuniciators for NB02 Bus Lock Out (21A)

Crew may enter OFN NB-030 CRS Direct Actions for ALR 00-021A directly.

Ensures all NB02 supply breakers open.

NB0209 RO/BOP NB0211 NB0212 Align CCW to Red Train:

Start one CCW pump (A or C)

RO/BOP Open Red Train to Service Loop Valves CCW is required to prevent (C) (EG HIS-15) damage to RCPs.

Dispatch operator to locally close Yellow Train to Service Loop (EG HV-16/54).

Dispatch operator to locally shutdown RO/BOP B EDG.

Review and comply with Tech. Specs. The Limiting T.S. action is from T.S. 3.8.1 AC Sources. T.S. 3.7.5, condition C, the CRS CRS T.S. 3.8.9 Distribution Systems. must recognize that two trains T.S. 3.7.8 ESW (per 3.8.1) of AFW are inoperable, T.S. 3.7.5 AFW requiring Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Enter and direct OFN NB-030, Loss of AC CRS Emergency Bus. Attachment B.

Check Rx power < 100%

RO Close FW Heaters Bypass valve, AE HV-38.

OP-TEST #1 SCENARIO #1 Page 11 of 11 OPERATOR ACTIONS Event 4 Continued Check Yellow Train AC Emergency Bus RO De-energized.

Verify CCW Service Loop Aligned to Red Train.

Start A or C CCW pump.

May have been performed in BOP

Open Red Train Supply/Return the ALR.

Valves. EG HS-15

Dispatch Operator to locally close Yellow Train Supply/Return valves.

BOP Check RCP Thermal Barrier L/U Normal BOP Verify Instrument Air from Red Train.

RO/BOP Check RCP Cooling Normal.

Ensure RCP Seal Injection to each RCP RO between 8-13 gpm.

Establish ESW to Red Train

Start A ESW Pump

Open Train A to UHS EF HIS-37 BOP

Close red train ESW valves EF HIS 23 EF HIS-41 Check if TDAFW flow should be reduced:

CRS - NOT needed for Heat Sink BOP - Close or throttle all TDAFW flow CRS/BOP control valves.

(Crew may decide to leave open/throttled for minimum flow concerns.)

RO/BOP Start Red Train SFP cooling pump.

At panel RP068 (in back), Start Red Train BOP CR AC unit. GK HIS-29.

Determine Bus Lockout is not clear and this CRS is a hold point in procedure at step B12.

Termination Criteria: Red Train ESW and CCW are in service.

OP-TEST #1 SCENARIO #1 Page 12 of 12 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 5 Event

Description:

Tech Spec Required Shutdown (Cue provided from Shift Manager to reduce power at 1% per minute.)

Time Position Applicant's Actions or Behavior Notes Enter and direct actions of OFN MA-038. Crew should commence 10%

Conduct Reactivity Brief with board downpower from pre-shift brief CRS operators. Pre-Shift brief for reduction to then determine remaining 90%. actions.

RO Calculate Boration required. 155 gallons at 15.4 gpm.

Establish 1% per minute power decrease on the Load Set potentiometer.

Press Decrease Load till Load Limit light is out.

BOP

Select 1%/Minute on Loading Rate.

(Continuous)

Select Decrease Loading Rate -

ON.

Decrease Load Set, maintain within 200 MW of actual load.

Use rods to maintain Tavg/Tref error between 0 and +5 RO

Energize both PZR B/U heaters.

(Continuous)

Borate and adjust rods as necessary to maintain rods above RIL.

Check PZR PORVs / Block Valves RO/BOP

Check PZR Pressure

Check PZR Level BOP Control S/G levels to maintain 45-55%.

(Continuous)

May have been performed in BOP Check AE HV-038 - Closed OFN NB-030.

Check Reactor Power < 60%. Recognize CRS hold point in procedure.

Power Reduction in Progress. Rods have Termination Criteria:

automatically stepped in.

OP-TEST #1 SCENARIO #1 Page 13 of 13 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 6 Event

Description:

Main Feed Line break in Turbine Building.

Time Position Applicant's Actions or Behavior Notes Note and communicate level decreasing in BOP all four S/Gs.

BOP Acknowledge and communicate alarms RO/BOP Note S/G Levels are approaching Rx Trip CRS setpoint.

Direct a Rx Trip or respond to a Rx Trip CRS and enter EMG E-0.

Rod Bottom Lights Lit.

Rx Trip and Bypass Bkrs open.

Neutron Flux decreasing (Intermediate Range & Gamma metrics)

RO

Transfer NR-45 recorder to Intermediate Range

NB01 normal voltage / off site power.

Determine SI is NOT actuated.

Main Stop valves all closed.

BOP

Generator and exciter bkrs open.

RCS Press> 1830 PSIG

All S/G Press > 615 psig RO

Ctmt Press < 3.5 psig

RCS Subcooling > 30 degrees

PZR Level > 6%

OP-TEST #1 SCENARIO #1 Page 14 of 14 OPERATOR ACTIONS Event 6 (Continued)

CRS Ensure Immediate Actions complete.

Identify any immediate concerns.

Management Expectation is to NOT perform any other actions Secure all Condensate Pumps and Heater till the immediate actions are CRS/BOP Drain Pumps after Immediate actions are complete. With a feed break in complete. the Turbine Building it is expected to secure running secondary pumps.

CRS/RO Using procedure verify Immediate Actions BOP of EMG E-0 complete Direct Operator to Monitor CSFSTs and CRS Transition to EMG ES-02 from Step 4 RNO.

EMG E-0 Immediate Actions completed, Termination Criteria:

transition is made to EMG ES-02.

OP-TEST #1 SCENARIO #1 Page 15 of 15 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 7 and 8 Event

Description:

Loss of Heat Sink, failure of high head Injection.

Time Position Applicant's Actions or Behavior Notes Conduct Transition Brief for entry to EMG CRS ES-02.

RO Perform EMG F-0 for CSFST CRS/RO Monitor CSFST on NPIS computer screen BOP after 1st verification with the procedure.

(Continuous)

Note that AFW flow is zero to all S/Gs.

May attempt to open all AFW BOP valves.

Note and report that zero flow is indicated to all S/Gs.

After transition to FR-H1 the Recognize that entry conditions are met for crew will be watching for Fold CRS RED path on EMG FR-H1, Loss of Heat Out Page Criteria to go to the Sink. Transition to EMG FR-H1.

steps for Feed and Bleed.

Try to establish AFW Flow.

CRS Determine from Building reports that No AFW pump is available.

BOP Close all AFW valves Reduce heat input to RCS.

RO/BOP Stop all RCPs Turn off all PZR heaters (3)

Establish S/G pressure control.

BOP IF MSIVs are open, align Steam Dumps.

IF MSIVs are closed, then use ARVs.

OPERATOR ACTIONS Event 7/8 (Continued)

CRS Verify Condensate/Feedwater systems

OP-TEST #1 SCENARIO #1 Page 16 of 16 available.

Based on Building reports, determine the Main Feedwater header is unavailable.

Recognize to use the RNO and this places the crew in a loop from step 1 to step 7.

Conduct Quick Brief with crew.

CRS In a procedure loop till the Fold Out Page is met or meet a step criteria.

Monitor S/G WR levels. As level reaches Perform Step for Bleed and Crew 26% proceed to step 27 and initiate bleed Feed.

and feed.

RO/BOP Stop all RCPs May have already performed.

Turn off all PZR heaters RO Actuate Safety Injection Manually start A CCP.

RO Ensures Feed Path Established Checks BIT flow indicated on EM FI-(C) 917A.

ARM both Cold Overpressue Protection RO/BOP circuits. Ensures Bleed Path (C) Ensure Both Block Valves open. Established Open both PZR PORVs.

RO/BOP Verifies BOTH Block valves and BOTH PORVs are open.

Scenario may be terminated Bleed and Feed established per steps 27-Termination Criteria: anytime after bleed and feed 31 of EMG FR-H1.

has been established .

OP-TEST #1 SCENARIO #1 Page 17 of 17 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT Utilizing guidance in the ALR or OFN, CCW established to RCPs prior start a CW pump in the unaffected train RO/BOP to high temperatures meeting and transfer the service loop to the immediate RCP trip criteria.

running train.

Initiate SI and manually start A Bleed and Feed must be Safety Injection Pump to ensure a Feed RO/BOP established prior to S/G dry out.

path, ensure PORVs/Block valves (3 S/Gs < 8% WR) open for a bleed path.

OP-TEST #1 SCENARIO #1 Page 18 of 18 Booth Instructions Ensure batch file has been loaded into X:\Opensim\Batch folder in the Instructor Station Computer.

Initialize in IC 171 and go to RUN.

On the Expert screen load batch file: 2004SCN01.txt. After file loads FREEZE the simulator.

Hang DNO tags on the following:

AL HIS-31 and AL HIS-35 for A AFW pump suction

A AFW pump handswitch. Place handswitch in PTL.

A SI pump handswitch. Place handswitch in PTL.

Perform Simulator Ready checklist.

OP-TEST #1 SCENARIO #1 Page 19 of 19 BOOTH COMMUNICATIONS AND ACTIONS Unless otherwise directed, all events will be entered when cued from the floor.

When cued from the floor or when crew assumes the watch go to RUN.

WHEN cued after crew assumes the watch, enter EVENT 1.

When CRS contacts I&C or the Work Week Manager for Loop 2 Temperature instrument, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 2.

When CRS contacts I&C or the Work Week Manager for Steam Header pressure instrument, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 3.

When CRS contacts I&C or the Work Week Manager for PZR Spray Valve Failure, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 4.

When Aux watch is contacted to isolate B Train CCW, enter EVENT 8.

When Turbine watch is contacted to shutdown B diesel, enter EVENT 9.

When CRS contacts Shift Manager or Call Superintendent, acknowledge communications and respond: Well get back with you.

Wait approximately one minute then call back as Shift Manage and state: Ive talked with the Plant Manager and Vice President. Weather predictions indicate severe storms are heading towards the site. The decision has been made to commence a rapid shutdown at 1% per minute to put the plant in a safer condition.

When cued from the floor, enter EVENT 5.

After the reactor trip, page the Control Room as Turbine Building Watch and state: I saw large amounts of steam and water at the south end of the Turbine Building and have evacuated the building.

During the Main Feed Line Break and EMG FR-H1 the following communications MAY be required:

OP-TEST #1 SCENARIO #1 Page 20 of 20 If asked about break location respond: It appears to be in the main header area above the MFRVs. It does not appear safe to enter the\area.

If asked to investigate TDAFW pump, respond: There is still steam and hot water all around on the 2000 elevation, I will try to make it into the room as it clears.

When directed from the floor, FREEZE the simulator. DO NOT RESET till allowed by the NRC Chief Examiner.

Batch File:

> BAT 2004SCN01.TXT

>TAGOUT 'B' AFW PUMP IRF NALP01A 1 IRF NALP01AX 1 IRF RALH31 1 IRF RALH35 1

>TAGOUT A SI Pump IRF NEMP01A

>Loop two Thot Avg fails high IMF mRCS01B (1) 650 20

> AB PT-507 fails low IMF mMSS13 (2) 0 20

> "A" PZR Sray valve fails full open in Auto IMF mPRS03A (3) 100 30

>Bus Lockout on NB02 IMF mEPS06B (4)

> Main Feed Line break in Turb Bldg IMF mFWM20 (6) 1e+7 45

> Trip of TDAFWP tied to Rx Trip TRGSET 7 "JPPLP4" IMF mAFW02B (7 180)

> Intermediate Range Compensation failure IMF mNIS04A 1e-9.5

>Close EG HV16/54 CCW B to Service Loop TRGSET 8 TRG 8 SET regh16=0

>Local Shutdown of B EDG TRGSET 9 RDGS02B (98) 0 RDGS10B (9 5) 0 RDGS19 (9 15) 1

>End of File

SHIFT BRIEFING INFORMATION THIS FORM IS FOR TRAINING PURPOSES ONLY CONTROL ROOM TURNOVER CHECKLIST DATE : May 12, 2004 NIGHT SHIFT X DAY SHIFT MODE- 1 OFF-GOING: (PRINT) CRS ON-COMING: (PRINT) CRS RO RO BOP BOP SE SE ON-COMING CRS/SE/RO/BOP REVIEW EVOLUTIONS IN PROGRESS:

A Train Work Week Severe Thunderstorm Watch in effect for next four hours.

Maintenance is trying to complete all work due to weather.

MAINTENANCE IN PROGRESS:

A MD AFW Pump for bearing replacement.

A SI pump, jump up for oil change.

TESTING IN PROGRESS: NONE SIGNIFICANT LCOs IN EFFECT:

3.7.5 AFW, Condition B, 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months to restore.

3.5.2 ECCS, Condition A, 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months to restore.

REACTOR POWER 100 % RCS: 586.5 °F 2235 PSIG ROD CONTROL AUTO X MANUAL CONTROL BANK D 229 STEPS RCS BORON (Cb) 1028 PPM @ DATE/TIME Today/0400 LEAK RATE IDENTIFIED .02 UNIDENTIFIED .001 @ DATE/TIME Today/

(GPM): 0400 COND. AIR INLEAKAGE 13.8 scfm (IAW STN CH-020)

ESF STATUS PANELS AND REACTOR TRIP/BLOCK PANEL PANEL COMPONENT/TRIP/BLOCK REASON SA066X SI A SI and A MDAFW SA066X AFAS A MDAFW TRAINING ONLY ALARM WINDOW DESCRIPTION WINDOW NAME REASON WR/WO 018F NB01 BKR NOT A MDAFW pump 04-2083 OPEARBLE A SI pump 04-2650

INITIAL LICENSE EXAM OPERATING TEST #1 SCENARIO # 2 Revision 02 Week of May 10, 2004

OP-TEST # 1SCENARIO #2 Page 2 of 2 Facility: Wolf Creek NRC Scenario No.: 2 Op-Test No.: 1 Revision 02 Source:

New Bank - Significantly Modified X Bank - Initial Condition Change See page 3 for Examiner/student assignments Initial Conditions: 100% Power, MOL, Normal Charging Pump is OOS for bearing replacement.

Turnover: Maintain current plant conditions.

Event Malf. Event Event No. No. Type* Description 1 mPRS I PZR Pressure Channel Fails High T+1 01C 2 mMSS C C S/G ARV fails open in auto, manual available.

T+17 07C 3 mFWM C B S/G MFRV fails closed in auto, manual available.

T+25 03B 4

mNIS I Nuclear Instrumentation Channel NI-43 fails high.

T+31 03C 5 mRCS C SSE/OBE Earthquake causes SBLOCA.

T+40 07A 6 mRCS M SSE/OBE escalates to Loss of Offsite Power, LBLOCA.

T+46 06A 7 mDGS T+47 C Both EDGs fail to Auto Start.

02A/B 8 rBN881 A Train RWST suction to RHR fails to align during EMG ES-C T+68 2A 12, Transfer to Cold Leg Recirc

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

OP-TEST # 1SCENARIO #2 Page 3 of 3 Scenario # 1 Crew Assignments Session 1 Crew B Examiners Applicants E3: CRS: SRO-I2 E1: RO: RO3 BOP: Surrogate Session 2 Crew D Examiners Applicants E3: CRS: SRO-I4 E4: RO: RO5 BOP: Surrogate Session 3 Crew B Examiners Applicants CRS: Surrogate E4: RO: SRO-I1 BOP: Surrogate Session 4 Crew C Examiners Applicants E2: CRS: SRO-I3 E1: RO: RO4 BOP: Surrogate Session 5 Crew A Examiners Applicants E3: CRS: Surrogate E2: RO: RO2 BOP: RO1

OP-TEST # 1SCENARIO #2 Page 4 of 4 SCENARIO MISCELLANEOUS INFORMATION SCENARIO OBJECTIVE:

The objective of this scenario is to mitigate a large break LOCA with a failure in the automatic switchover of the Residual Heat Removal (RHR) pump suction to the containment sumps. Initial conditions have the Normal Charging Pump (NCP) out of service as distractor. The NCP has no affect on the scenario. The scenario contains a PZR pressure channel failure, failure of automatic control of a Main Feed Regulating Valve, and a Nuclear Instrument failure, all requiring operator action to prevent a reactor trip. The scenario also contains a failure of a S/G Atmospheric Relief Valve (ARV) as a board awareness issue affecting reactor power.

The SRO will evaluate Technical Specifications for the PZR pressure channel and the Nuclear Instrument failure. The S/G ARV should also be reviewed, however the valve is not inoperable.

The main event is an escalating earthquake. The first event exceeds the Operational Based Earthquake (OBE) causing a small break LOCA at 80 gallons per minute. The crew will enter the off normal procedures and estimate the leak rate. The second event then exceeds the Safe Shutdown Earthquake (SSE) resulting in a large break LOCA causing an automatic reactor trip, safety injection actuation and a loss of offsite power.

Post trip failures include both emergency diesels do not auto start and a failure during the automatic switchover of the RHR suction valves. The operator must start both diesels to not enter the loss of all AC contingency procedure. The switchover failure has the Refueling Water Storage Tank (RWST) suction valve to A train RHR fails to close. This is the worse case condition as described in the Wolf Creek Updated Safety Analysis Report (USAR). This results in an open path form the RWST to Containment. The required actions are to secure the A train pump and close the containment suction valve. The operators must realize the remaining train can meet all needs of the accident in progress.

The following is the expected major procedure flow path:

OFN SB-008, INSTRUMENT MALFUNCTIONS

Possibly OFN SG-003, NATURAL EVENTS

OFN BB-007, RCS LEAKAGE

EMG E-0, REACTOR TRIP OR SAFETY INJECTION

EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT

EMG FR-P1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK

EMG ES-12, TRANSFER TO COLD LEG RECIRCULATION CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance when the scenario is completed:

RCS Pressure and Temperatures

RWST Level

OP-TEST # 1SCENARIO #2 Page 5 of 5 OPERATOR ACTIONS TABLE NOTES:

1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2. Actions required throughout the event are indicated as "(continuous)" in the position column.

3. Shaded cells indicate procedural entry points.

OP-TEST # 1SCENARIO #2 Page 6 of 6 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 1 Event

Description:

PZR Pressure Channel Fails High Time Position Applicant's Actions or Behavior Notes Notes and communicates alarms for PZR RO PORV Open.

RO may select out the failed Places Master Pressure Controller in RO channel. Action must be taken Manual and decreases output.

in time to prevent a Rx Trip.

RO/BOP/ Monitor RCS pressure for entry into DNB T.S. 3.4.1, two hours to restore.

CRS Tech. Spec. at < 2220 psig.

As RCS pressure decreases to < 2220, the RO/BOP may change Digital CRS/RO crew may energize 2nd set of PZR back-up Display for Pressure heaters. Indication.

CRS Enter and direct OFN SB-008, Attach. K Identify BB PI-457 indicates high.

Select out failed channel.

RO Ensure system stable and return to automatic.

Monitor system response.

Contact Work Week Manager (WWM) and request I&C assistance to trip bi-stables and repair channel. 3.3.1 and 3.3.2 Review and comply with Tech Specs. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to place channel in 3.3.1 Reactor Trip System trip.

Table 3.3.1, Functions 6 and 8. 3.3.2, function 8.b. Verify P-11 CRS 3.3.2 ESFAS Instrumentation bi-stable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Table 3.3.2, Functions1.d and 8.b 3.3.4, Remote S/D, N/A 3.3.4/3.3.6/3.3.7 No Action 3.3.6, CPIS Instrumentation, Function 4 Required 3.3.7, CREVS Instrumentation, Function 4 Master pressure controller back in Auto Termination Criteria: with pressure between 2220 and 2250 psig. T.S. actions identified.

OP-TEST # 1SCENARIO #2 Page 7 of 7 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 2 Event

Description:

C S/G ARV fails open in auto, manual available.

Time Position Applicant's Actions or Behavior Notes The crew may notice the ARV CRS/RO Note and communicate RCS temperature right away and effects on plant BOP and pressure are decreasing.

parameters will not occur.

Note and communicate Rx power has RO increased.

Note that turbine load has decreased but BOP load set is stable.

CRS/RO Note that C S/G ARV is indicating open, BOP BOP take manual control and close the (Continuous) ARV.

If the ARV was closed quickly Diagnose indications as a steam leak. Enter the crew may not enter the off CRS and direct actions of OFN AB-041 normal. The T.S should still be Steamline or Feedline Leak.

reviewed.

Check Rx Power < 100%, if not:

Close AE HV-038.

If the crew has already closed CRS/RO

Reduce turbine load. the ARV, no action would be BOP Check S/G levels stable required.

Check Tavg/Tref mismatch <3 degrees Check Condenser Hotwell level.

Ensure S/G ARVs closed.

CRS/BOP BOP places ARV in manual/closed.

The ARV is still operable since Refer to T.S. 3.7.4.

CRS it is capable of opening and No action required.

closing.

Contact Work Week Manager (WWM) and CRS request assistance to troubleshoot/repair ARV.

C S/G ARV is in manual/closed. Rx Termination Criteria:

Power is stable at or below 100%.

OP-TEST # 1SCENARIO #2 Page 8 of 8 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 3 Event

Description:

B S/G MFRV fails closed in auto, manual available.

Time Position Applicant's Actions or Behavior Notes Notes and communicates B S/G level is BOP decreasing.

Notes and communicates annunciators 109B BOP and/or 109C, Steam Flow/Feed Flow Mismatch.

Places MFRV B in manual, matches feed Actions must be taken in time to BOP flow to steam flow and stabilizes S/G level. prevent a reactor trip.

Checks Secondary Panels and determines RO there is no instrument failure.

Enter and direct actions of Alarm Response CRS ALR 00-109B or 109C.

Verify Steam/Feed Mismatch.

CRS/BOP Verify NO instrument failures.

Verify NO Secondary transient.

Use manual control on B MFRV and BOP restore S/G level to program. (50%)

CRS/BOP Check for S/G Tube Leakage Contact Work Week Manager (WWM) and CRS request assistance to troubleshoot/repair B MFRV controller.

B S/G level stable at or trending to Termination Criteria: program (50%), with the controller in manual.

OP-TEST # 1SCENARIO #2 Page 9 of 9 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 4 Event

Description:

Nuclear Instrumentation Channel NI-43 fails high.

Time Position Applicant's Actions or Behavior Notes Notes and communicates to the crew rods RO stepping in.

Verifies and communicates, no loss of BOP load has occurred.

Rods must be placed in manual RO Places rod control in manual.

in time to prevent a Rx Trip.

Acknowledge communications and that rod CRS control is in manual.

RO Notes that NI-43 indication is high.

Enter and direct OFN SB-008, Instrument CRS Malfunctions, Attachment R. Steps R1 through R3 are already complete.

Bypass Failed Channel at the NI Cabinets.

At Detector Current Comparator Drawer:

Upper Section switch to N43 CRS/BOP

Lower Section switch to N43

Power Mismatch Bypass to N43

Rod Stop Bypass to N43 At Comparator and Rate Drawer:

Comparator Channel Defeat to N43.

Conduct Reactivity brief and withdraw control rods back to the parked position.

BOP Peer check rod motion. Management Expectation that CRS/RO all reactivity actions be peer Checks Tavg/Tref within 1 degree checked.

Place rod control in Automatic.

Monitor Rod Control System.

OPERATOR ACTIONS Event 4 Continued

OP-TEST # 1SCENARIO #2 Page 10 of 10 CRS/RO Check channel not used for recorders.

CRS/BOP Remove Control Power Fuses for N43.

Contact Work Week Manager (WWM) and request I&C assistance to trip bi-stables and repair channel.

Review and comply with Tech Specs.

T.S. 3.3.1 Function 2 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to place channel in trip and Perform SR 3.2.4.2 Functions 3 and 6 3.3.1 Reactor Trip System 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to place channel in CRS Table 3.3.1-1, Functions 2, 3 and 6. trip.

Table 3.3.1, Function18, Permissives. Function 18 P-7, P-8, P-9 and P-10 Verify bistable in proper state or be in Mode 2 in 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

Technical Requirements Manual TRM 3.3.17 TRM 3.3.17 Reactivity Alarms Perform AFD STS once per hr Conditions A and D Perform QPTR STS once/12 hrs Control Rods are in automatic and Termination Criteria: returned to the park position. Tech Spec time limit has been identified

OP-TEST # 1SCENARIO #2 Page 11 of 11 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 5 Event

Description:

SSE/OBE Earthquake causes SBLOCA. (80 gpm)

Time Position Applicant's Actions or Behavior Notes Notes and acknowledges Annunciators RO/BOP 098C, 98D and 98E earthquake. OBE earthquake.

CRS will enter OFN SG-003 or Enter and direct actions of OFN SG-003, perform the ALRs. In either CRS Natural Events or Alarm Response 98C, case the SBLOCA will escalate 98D or 98E. requiring entry to OFN BB-007, RCS Leakage.

Note and communicate RCS pressure is decreasing, Containment humidity is RO/BOP increasing. Monitor for entry to DNB T.S.

entry at < 2220 psig.

Enter and direct OFN BB-007 RCS CRS Leakage.

Checks PZR Level - decreasing.

RO should increase charging Increase charging flow.

flow and isolate letdown.

RO Isolate Letdown.

Provide estimate of RCS Leak Stabilize PZR Level.

rate at 80 gpm.

Estimate RCS leak rate.

Check Charging Pump Suction.

CRS/RO Check PZR pressure - stable.

Check S/G Tubes - intact.

CRS/BOP

Dispatch HP

Contact Chemistry.

Event 6 will occur when CRS begins checking Ctmt CRS Check Containment Conditions conditions, escalating leak size.

OFN BB-007 has been entered with leak Termination Criteria: rate identified.

OP-TEST # 1SCENARIO #2 Page 12 of 12 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 6 and 7 Event

Description:

SSE/OBE escalates to Loss of Offsite Power, LBLOCA.

Both Emergency Diesels Fail to Auto Start.

Time Position Applicant's Actions or Behavior Notes Notes and communicates annunciators 98A RO/BOP and 98B. SSE earthquake.

Notes and communicates rapidly decreasing PZR level and pressure.

RO Isolate Letdown.

Maximize Charging.

Automatic actuation will Direct Rx Trip and SI.

CRS probably occur before the crew Enter and direct actions of EMG E-0.

can take action.

RO/BOP Perform Immediate Actions of EMG E-0.

RO Verify Rx Tripped.

BOP Verify Turbine Tripped.

Check AC buses - At least one energized.

EVENT 6 RO Depress Start/Reset pushbutton for both Procedure requires starting (C) EDGs.

both EDGs.

Verify Buses energize.

RO Verify Safety Injection has actuated.

Ensure Immediate Actions complete.

CRS Identify any immediate concerns.

One person from the crew should recognize adverse containment values have been ALL exceeded and communicate this to the rest of the crew.

Termination Criteria:

OP-TEST # 1SCENARIO #2 Page 13 of 13 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 6 Continued Event

Description:

Continue through EMG network till Lo-Lo RWST level reached then execute EMG ES-12 Transfer to Cold Leg Recirc.

Time Position Applicant's Actions or Behavior Notes CRS/RO Check if SI is required - YES Perform EMG E-0 Attach. F for Automatic CRS/RO Signal verification.

Verify AFW > 270 klbm/hr.

Close AC HIS-134 CRS/BOP Reduce AFW to 270 klbm/hr Establish S/G Pressure Control Check PORV/Block Valves.

Check PZR Spray Valves.

CRS/BOP Check PZR Safety Valves.

Check if RCPs should be stopped.

Monitor Critical Safety Function Status CRS/BOP Trees using EMG F-0.

Check if S/Gs are not faulted.

Check if S/G Tubes are intact.

CRS/RO

Dispatch HP Check S/G levels - controlled increase Check if RCS Intact in Containment NO CRS/RO Ensure BIT inlet and outlets open.

Transition to EMG E-1 At some point a Red Path on Integrity due to This may occur before or after CRS/BOP the large cooldown. The CRS should transition to EMG E-1.

transition to EMG FR-P1.

Enter and exit EMG FR-P1, Response to CRS Imminent Pressurized Thermal Shock.

At step one determine RHR flow > 500gpm CRS/RO and exit procedure.

CRS Enter and Direct EMG E-1, Loss of Crew will begin working

OP-TEST # 1SCENARIO #2 Page 14 of 14 Reactor or Secondary Coolant. Conduct through EMG E-1 till Transition Brief with Crew. Annunciator 047D, RWST Lev Lo-Lo 1 alarms.

CRS/RO Monitor Fold Out Page for Cold Leg BOP Recirculation Criteria. RWST Level <

(Continuous) 36%, Annunciator CRS/RO Check if RCPs should be stopped.

Check if S/Gs not faulted.

CRS/BOP Check if S/G Tubes are intact.

Reset SI.

CRS/ RO Reset CIS-A.

Reset CIS-B Annunciator 047D, RWST Level Lo-Lo 1 Termination Criteria: alarms and the Crew transitions to EMG ES-12.

OP-TEST # 1SCENARIO #2 Page 15 of 15 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 8 Event

Description:

EMG ES-12 is entered; RWST Suction Valve BN HV-8812A fails to automatically re-align.

Time Position Applicant's Actions or Behavior Notes Enter and direct action of EMG ES-12. No The first ten steps of EMG ES-transition brief is desired or required.

CRS 12 are critical to establish cold CRS/RO will perform procedure while the leg recirc.

BOP monitors the rest of the plant.

CRS/RO Reset All SI signals.

(C) SIS and RWST Switchover.

Ensures CCW pump running in both trains.

CRS/RO Ensures both CCW to RHR HX valves open.

CRS/RO Ensure CCW to SFP HX valves closed.

Checks Red Train Switchover.

Note that BN HV-8812A is open.

CRS/RO Additional critical action to Perform RNO.

(C) isolate the A Train.

Stop A RHR pump.

Close EJ HV-8811A.

CRS/RO Checks Yellow Train Switchover.

CRS/RO Close both Hot Leg Recirc valves. Operators should realize they (C) Ensures B RHR pump running. should not start A RHR.

Close both SI pump mini-flow valves.

CRS/RO Using the Power Lockout, close SI pump (C) recirc to RWST Open both RHR to CCP/SI suction valves.

CRS/RO Open both CVCS to SI suction valves.

(C) Close both RWST to SI suction valves.

Close both RWST to CCP suction valves.

Resume monitoring Critical Safety CRS Functions.

Cold Leg Recirculation is aligned with Terminate Scenario Termination Criteria:

A RHR pump secured.

OP-TEST # 1SCENARIO #2 Page 16 of 16 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT RO Start both Emergency Diesels by At least one AC Emergency bus pressing the Start/Reset pushbuttons. is powered from its associated diesel generator before transition to EMG C-0, Loss of All AC.

Although only one is required from a Critical Task standpoint, procedure EMG E-0 directs starting any stopped diesel.

CRS/RO Establish Cold Leg Recirc. A RHR pump secured and the Isolate A Train RHR pump. RWST suction valve closed.

Remaining ECCS pumps on both trains are aligned for suction from B RHR pump.

OP-TEST # 1SCENARIO #2 Page 17 of 17 Booth Instructions Ensure batch file has been loaded into X:\Opensim\Batch folder in the Instructor Station Computer.

Initialize in IC 176 and go to RUN.

On the Expert screen load batch file: 2004SCN02.txt. After file loads FREEZE the simulator.

Hang DNO tags on the following:

NCP Handswitch BG HIS-3 and place in PTL.

Perform Simulator Ready checklist.

OP-TEST # 1SCENARIO #2 Page 18 of 18 BOOTH COMMUNICATIONS AND ACTIONS Unless otherwise directed, all events will be entered when cued from the floor.

If at any time the crew makes contact with the Shift Manager or Call Supt., simply acknowledge their report and respond you will get back with them.

When cued from the floor or when crew assumes the watch go to RUN.

WHEN cued after crew assumes the watch, enter EVENT 1.

When CRS contacts I&C or the Work Week Manager for PZR instrument failure, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 2.

When CRS contacts I&C or the Work Week Manager for C ARV, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 3.

When CRS contacts I&C or the Work Week Manager for B MFRV failure, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 4.

When CRS contacts I&C or the Work Week Manager for NI-43 failure, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 5.

WHEN cued from the floor, enter EVENT 6.

During events 5 and 6 the CRS will contact Chemistry and HP, simply acknowledge the requests.

When directed from the floor, FREEZE the simulator. DO NOT RESET till allowed by the NRC Chief Examiner.

OP-TEST # 1SCENARIO #2 Page 19 of 19 Batch File:

>Bat 2004SCN02.txt

>Tag Out NCP IRF NBGP04 1

>Controlling PZR Press channel fails high IMF mPRS01C (1) 2500 30

>FAIL Open OF "C" S/G ARV IMF mMSS07C (2) 100 20

>"B" MFRV fails in Auto IMF mFWM03B (3) 0 60

>NIS Channel 43 fails high IMF mNIS03C (4) 120 10

>Earthquake occurs causing a SBLOCA TRGSET 5 (0)

IMF ANN-E098 (5 5) 0 IMF ANN-D098 (5 10) 0 IMF ANN-C098 (5 12) 0 IMF mRCS07C (5 15) 80 60

>Earthquake escalates to LOCA/LOSP TRGSET 6 (0)

IMF ANN-B098 (6 5) 0 IMF ANN-A098 (6 10) 0 IMF mRCS06C (6 10) 80000 180

>LOSP tied to Rx Trip/Both EDG's Fail to auto start TRGSET 7 "JPPLP4" IMF mEPS01A (7 20)

IMF mEPS01B (7 30)

IMF mDGS02A IMF mDGS02B

>Failure of BN HV-8812A to close on RWST Lo-Lo TRGSET 8 "JD047A" IRF rBN8812A (8) 1

>End of File

SHIFT BRIEFING INFORMATION THIS FORM IS FOR TRAINING PURPOSES ONLY CONTROL ROOM TURNOVER CHECKLIST DATE : Today NIGHT SHIFT X DAY SHIFT MODE- 1 OFF-GOING: (PRINT) CRS ON-COMING: (PRINT) CRS RO RO BOP BOP SE SE ON-COMING CRS/SE/RO/BOP REVIEW EVOLUTIONS IN PROGRESS:

MAINTENANCE IN PROGRESS: NCP OOS for Bearing Replacement.

TESTING IN PROGRESS:

SIGNIFICANT LCOs IN EFFECT:

REACTOR POWER 100% % RCS: 586.5 °F 2235 PSIG ROD CONTROL AUTO X MANUAL CONTROL BANK D 229 STEPS RCS BORON (Cb) 1028 PPM @ DATE/TIME Today/0400 LEAK RATE IDENTIFIED .02 UNIDENTIFIED .01 @ DATE/TIME Today/

(GPM): 0400 COND. AIR 13.1 INLEAKAGE (IAW STN CH-020)

ESF STATUS PANELS AND REACTOR TRIP/BLOCK PANEL PANEL COMPONENT/TRIP/BLOCK REASON TRAINING ONLY ALARM WINDOW DESCRIPTION WINDOW NAME REASON WR/WO

INITIAL LICENSE EXAM OPERATING TEST # 1 SCENARIO # 3 Back Up Revision 02 Week of May 10, 2004

OP-TEST #1 SCENARIO #3 Page 2 of 2 Facility: Wolf Creek NRC Scenario No.: 1 Op-Test No.: 1 Revision 02 Source:

New X Bank - Significantly Modified Bank - Initial Condition Change See page 3 for Examiner/student assignments Initial Conditions: Chemistry hold at 30% power, Ready to Enter Gen 00-004 Turnover: Prepare to continue power increase to 100%

Event Malf. Event Event No. No. Type* Description 1 mFWM I C S/G Controlling Level Channel fails high.

02C4 T+1 2 mCVC1 C Normal Charging Pump Trips 3C T+11 3 MCVC0 C Excessive Seal Leak Off A RCP.

6A T+18 4 mRCS0 M S/G Tube Rupture develops on A S/G requiring Rx Trip/SI.

2A T+46 P19019 B&

5 C Both ESW pumps fail to auto start on Safety Injection.

P19028 T+47 B

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

OP-TEST #1 SCENARIO #3 Page 3 of 3 Scenario # 3 Crew Assignments Session 1 Crew A Examiners Applicants E1: CRS:

E2: RO:

E3: BOP:

E4:

Session 2 Crew B Examiners Applicants E1: CRS:

E2: RO:

E3: BOP:

E4:

Session 3 Crew C Examiners Applicants E1: CRS:

E2: RO:

E3: BOP:

E4:

Session 4 Crew D Examiners Applicants E1: CRS:

E2: RO:

E3: BOP:

E4:

OP-TEST #1 SCENARIO #3 Page 4 of 4 SCENARIO MISCELLANEOUS INFORMATION SCENARIO OBJECTIVE:

The objective of this scenario is to mitigate a Steam Generator Tube Rupture (SGTR) using the guidance provided in the EMGs. Initial conditions have the unit in a hold at 30% power for S/G chemistry following a start up from a forced outage. The scenario contains a failure of the controlling level channel for C S/G, requiring operator action to prevent a reactor trip. Following is a trip of the Normal Charging Pump (NCP), which leads to a failure of the A RCP seal. The crew establishes proper conditions, then trips the A RCP.

The SRO will evaluate technical specifications associated with the S/G level channel failure and the loss of an operable reactor coolant loop. Technical Specifications do not allow power operation with less than all four loops operable. The CRS needs to recognize the unit has to be shutdown.

The major event is a SGTR. After the RCP is tripped a SGTR develops on the idle A S/G.

The rupture starts small and gradually increases leading to a manual Reactor Trip and Safety Injection (SI). Both Essential Service Water (ESW) Pumps fail to auto start on the SI requiring manual operator actions. The crew must determine target conditions and successfully cooldown the unit to the target conditions without overcooling which could cause entry into a different mitigation procedure. The scenario is terminated once the crew has stabilized at or below the target.

The following is the expected major procedure flow path:

OFN SB-008, INSTRUMENT MALFUNCTIONS

OFN BB-005, RCP MALFUNCTIONS

OFN BB-007 or 07A during the Steam Generator Tube Leak.

EMG E-0, REACTOR TRIP OR SAFETY INJECTION

EMG E-3, STEAM GENERATOR TUBE RUPTURE CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance when the scenario is completed:

S/G C level

S/G A level

Core Exit TCs

S/G pressures

CCW and RCP temperatures.

OPERATOR ACTIONS TABLE NOTES:

OP-TEST #1 SCENARIO #3 Page 5 of 5

1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2. Actions required throughout the event are indicated as "(continuous)" in the position column.

3. Shaded cells indicate procedural entry points.

OP-TEST #1 SCENARIO #3 Page 6 of 6 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 1 Event

Description:

C S/G Controlling Level Channel fails high.

Time Position Applicant's Actions or Behavior Notes Notes and communicates annunciator 00-110B, and that C MFRV is going closed.

BOP Takes manual control of C MFRV and stabilizes level at program level (50%).

Acknowledges communications, enters and CRS may enter OFN SB-008 CRS directs Alarm Response (ALR 00-110B) directly.

Notes and communicates that level RO indicator AE LI-553 is failing high.

Manually controls MFRV to establish S/G level at program.

BOP Select out failed channel.

Returns MFRV controller to auto.

Enter and direct actions of OFN SB-008, CRS Instrument Malfunctions, Attach. F.

Confirms failed channel, channel has been selected out, monitors S/G level to ensure BOP proper control.

Contact Work Week Manager (WWM) to have I&C troubleshoot and trip bi-stables.

CRS Recognize channel does affect AMSAC.

OPERATOR ACTIONS

OP-TEST #1 SCENARIO #3 Page 7 of 7 Event 1 Continued Refer to and comply with T.S. Actions.

Table 3.3.1-1 Function 14 All are 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to trip bi-CRS T.S. 3.3.1, Condition E stables.

Table 3.3.2-1, Functions 5b and 6d.

T.S. 3.3.2, Conditions I and D Review Attach. S, determine instrument CRS does not affect T.S. 3.3.3 or 3.3.4 for Post Accident or Shutdown Monitoring.

S/G level stable or trending to 50%.

Termination Criteria: MFRV back in auto and Tech Specs identified.

OP-TEST #1 SCENARIO #3 Page 8 of 8 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 2 Event

Description:

Normal Charging Pump Trips Time Position Applicant's Actions or Behavior Notes Notes and communicate annunciator 042E /

042A and other alarms.

RO Determine and communicate that the Normal Charging Pump has tripped.

Acknowledge communications. Enter and CRS Crew may go to ALR 042A.

direct Alarm Response (ALR 00-042E)

Reports charging flow is < 45 gpm and no charging pump is running.

B CCP is aligned to the Closes Letdown Orifice Isolations.

normal charging header.

RO Makes plant announcement and starts B Starting A CCP would CCP.

require additional actions.

Manually control BG FCV-121 to control charging flow.

Direct RO to establish 120 gpm letdown CRS flow using ALR.

Place Letdown HX Outlet Pressure Control in Manual (BG PK-131) and Open between 90% and 100%

Open two Letdown Orifice Isolation Valve(s). If ALR 00-042A was entered, RO Adjust Letdown HX Outlet Pressure these steps will be performed Control to establish Letdown HX Outlet using the system procedure.

Pressure between 340 psig and 360 psig.

Place Letdown HX Outlet Pressure Control in Auto Adjust PZR Master Level Controller to RO stabilize PZR level or establish a trend towards program level.

Termination Criteria:

OP-TEST #1 SCENARIO #3 Page 9 of 9 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 3 Event

Description:

Excessive Seal Leak Off A RCP.

Time Position Applicant's Actions or Behavior Notes Notes and communicates alarm 072A.

RO Checks seal leak off A RCP @ 6 gpm.

Acknowledges communication. Enters and May enter OFN BB-005, RCP CRS directs ALR 00-072A. Malfunctions, directly.

Determines RCP A seal leakoff > 5.7.

CRS/RO Transition to OFN BB-005.

Enter and direct OFN BB-005, RCP CRS Malfunctions.

Enter Turn on Code BB3 on the plant RO/BOP computer NPIS screen.

Check RCP Parameters:

1 Seal temperature < 230 degrees RO/BOP Motor bearing temperature < 195 degrees Stator Winding temperature < 299 degrees Cue from evaluator:

Check RCP vibration readings. All frame vibrations < 2 BOP (Located in back panels) All shaft vibrations < 10 All appear steady.

Check Seal leak off < 6 gpm.

RO NO CRS Use RNO and go to Attach. E Determine from Attach. E:

Seal leak off > 6 gpm CRS Total #1 seal flow > 8 gpm Shutdown RCP using Attach. B Direct actions of Attach. B CRS Rx critical at < 48% power.

OP-TEST #1 SCENARIO #3 Page 10 of 10 OPERATOR ACTIONS Event 3 Continued Prepare S/G for RCP S/D Place A MFRV in manual and feed A BOP S/G to 70% narrow range.

(Continuous) When RCP is stopped then place MFRV back in Auto Stop A RCP Place A Spray Valve controller in manual and zero output.

CRS/RO Defeat Tavg and Delta T inputs for Loop A.

Between 3-5 minutes after RCP S/D, close Seal water outlet isolation for A RCP.

Reference T.S. 3.4.4, RCS Loops in Modes All 4 loops required.

CRS 1 and 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to Mode 3.

RCP A is stopped with Seal Leak Off Termination Criteria: isolated, T.S required Shut Down identified.

OP-TEST #1 SCENARIO #3 Page 11 of 11 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 4 Event

Description:

S/G Tube Rupture develops on A S/G requiring Rx Trip/SI.

(Leak ramps in from 50 gpm to 250 gpm.)

Time Position Applicant's Actions or Behavior Notes CRS/RO Note and communicate RCS pressure is BOP decreasing.

Monitor RCS pressure for entry into DNB CRS/RO Tech. Spec. at < 2220 psig.

BOP T.S. 3.4.1, two hours to restore.

As RCS pressure decreases, may energize RO PZR B/U heaters.

Note and communicate that PZR level is RO decreasing.

May enter OFN BB-007 for RCS Leakage There is a delayed reaction of or OFN BB-07A for S/G Tube Leakage, CRS the off gas radiation monitor depending on indications observed. Initial due to securing A RCP.

actions are the same.

Unit in Modes 1, 2 or 3.

CRS/RO PZR Level >17%

PZR Level stable or increasing - NO Maximizing Charging from B CCP.

RO Monitor PZR level.

(Continuous) When level continues to decrease, Then isolate letdown Note and communicate GE RE-92, CRS/RO Condenser Air Discharge Rad Monitor in BOP alarm.

Diagnose S/G tube leak based on:

GE RE-92 in Alarm.

CRS/RO No indications of leak in Containment or Auxiliary Building.

OPERATOR ACTIONS Event 4 Continued Fold Out Page criteria is met when charging is maximized, letdown isolated and PZR CRS/RO level continues to decrease.

OP-TEST #1 SCENARIO #3 Page 12 of 12 Direct a Reactor Trip and Initiate Safety CRS Injection.

Determined the leak is in excess of the Termination Criteria: capacity of one charging pump, Rx trip and Safety Injection actuated.

OP-TEST #1 SCENARIO #3 Page 13 of 13 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.s: 5 and 6 Event

Description:

During Crew response for immediate actions of EMG E-0, the Main Turbine fails to trip automatically, both ESW pumps fail to Auto Start.

Time Position Applicant's Actions or Behavior Notes Enter and Direct actions of EMG E-0, CRS Reactor Trip or Safety Injection.

RO/BOP Perform Immediate Actions of EMG E-0.

Rod Bottom Lights Lit.

Rx Trip and Bypass Bkrs open.

Neutron Flux decreasing (Intermediate Range & Gamma metrics)

Transfer NR-45 recorder to RO Intermediate Range

Both NB buses - normal voltage /

off site power.

Determine SI is actuated.

Annunciators 30A and 30B are lit.

Recognize Turbine did not trip.

Manually trip Turbine BOP should trip before a Main BOP

Main Stop valves all closed. Steam Line Isolation occurs.

Generator and exciter bkrs open.

At completion of Immediate Actions CRS determine if there are any immediate concerns.

RO Reports both ESW pumps failed to start.

CRS Direct RO to start both ESW pumps.

RO Makes plant announcement and starts (C) both ESW pumps.

OP-TEST #1 SCENARIO #3 Page 14 of 14 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 5 (Continued)

Event

Description:

Continuation of the SGTR using EMG E-0 at step 5 and EMG E-3.

Time Position Applicant's Actions or Behavior Notes Check if SI is required.

CRS Recognize SI was manually initiated.

Perform Attach. F to verify automatic actions.

If ESW pumps were not previously started, BOP Attach. F will provide guidance to start them. Ops expectations, per AP 15C-003 though, requires starting ESW/CCW at the end of Immediate Actions.

RO Monitor A S/G level and isolate AFW (Continuous) when Level is > 6% Narrow Range.

Check Plant:

AFW > 270,000 lbm/hr RCS Cold Leg Temperature Stable CRS/RO Place Steam Dumps in Stm Press Mode Check PORVs/Block Valves Check Spray valve/Safeties Closed Check if RCPs should be stopped - NO Direct monitoring of Critical Safety CRS Function Status Trees(CSFST)

BOP Perform EMG F-0 for CSFST CRS/RO Monitor CSFST on NPIS computer screen BOP after 1st verification with the procedure.

(Continuous)

Check S/Gs not faulted.

CRS/RO Check S/Gs Tubes intact:

GE RE-92 normal - NO

OP-TEST #1 SCENARIO #3 Page 15 of 15 Operator Actions Event 5 Continued Ensure BIT is not isolated.

CRS/RO Transition to EMG E-3 BOP (Attach. F of EMG E-0 must be completed prior to transition.) A transition brief is not required nor desired.

Monitor RCS pressure for RCP trip CRS/RO criteria.

BOP Does not apply once the cooldown is (Continuous) started.

Identify and isolate ruptured S/G by:

A S/G level increasing uncontrolled.

A ARV set at 1125 and closed.

CRS/BOP Dispatch operator to close low point drain.

Blowdown/Sampling isolated.

Close A MSIV and ensure bypass closed.

Feed flow isolated if level > 6% NR.

CRS/BOP Steam Dumps in Steam Pressure Mode.

Verify ruptured A S/G is isolated.

CRS Do NOT continue till it is.

CRS/RO Check ruptured S/G press > 275 psig.

BOP Block Low Steam Line Pressure SI.

RO Monitor RCS and perform when pressure is (Continuous) less than 1970 and prior to 1830 psig.

Initiate RCS Cooldown Setting the controller directly Determine Target Temperature.

to the target setpoint could Cooldown using Steam Dumps/ARVs.

cause a Main Steam Line CRS/BOP Per Ops Expectations, AP 15C-003, the Isolation requiring the use of steam dump controller should be lowered (C) the ARVs.

slowly such that only group 1 valves open. If the main steam line has Once Tavg is below 550 degrees the low isolated, the cooldown must be temperature interlock is by-passed and the performed on the ARVs.

controller is set at Target Setpoint.

Control AFW flow to maintain intact S/G CRS/BOP levels between 29 and 50%.

OP-TEST #1 SCENARIO #3 Page 16 of 16 Operator Actions Event 5 Continued Check PORVs/Block Valves.

Check PZR Safeties closed.

Steps are performed Reset SI CRS/RO concurrently with the Reset CISA and CISB.

cooldown.

Establish Instrument Air to Containment.

Stop the RHR pumps.

CRS/RO Monitor RCS pressure for RHR restart if (Continuous) pressure decrease to < 300 psig.

Stop the RCS Cooldown.

Ensure Steam Dumps close as target CRS/BOP temperature is approached.

(C) Adjust steam dump controller as required to maintain RCS temperature at or below target but greater than 350 degrees.

RCS cooldown is terminated with Termination Criteria:

temperature stable at or below target.

OP-TEST #1 SCENARIO #3 Page 17 of 17 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT CRS/RO Start both Essential Service Water ESW is required to ensure (ESW) Pumps. cooling to safety related components that have actuated during an accident response. At least one train must be started prior to the end of the scenario.

CRS/BOP Conduct the RCS Cooldown during a Max rate cooldown conducted to SGTR to the target conditions. target conditions. When stable at Stabilize at or slightly below the target. target; RCS subcooling >50 degrees and core exit TCs > 350 degrees.

OP-TEST #1 SCENARIO #3 Page 18 of 18 Booth Instructions Ensure batch file has been loaded into X:\Opensim\Batch folder in the Instructor Station Computer.

Initialize in IC 172 and go to RUN.

On the Expert screen load batch file: 2004SCN03.txt. After file loads FREEZE the simulator.

Provide copy of GEN 00-004 for the CRS with Initial Conditions signed off.

Perform Simulator Ready checklist.

OP-TEST #1 SCENARIO #3 Page 19 of 19 BOOTH COMMUNICATIONS AND ACTIONS Unless otherwise directed, all events will be entered when cued from the floor.

When cued from the floor or when crew assumes the watch go to RUN.

WHEN cued after crew assumes the watch, enter EVENT 1.

When CRS contacts I&C or the Work Week Manager for C S/G Level instrument failure, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 2.

If CRS contacts the Work Week Manager for the NCP, respond:

I will assemble a team.

WHEN cued from the floor, enter EVENT 3.

When the CRS contacts the Shift Manager or Call Supt about the RCP seal leak off, acknowledge the report and state you will contact management.

When the CRS contacts System Ops about the unit shutdown, acknowledge the report.

WHEN cued from the floor, enter EVENT 4.

During EMG E-3 and possibly OFN BB-007/07A, the CRS will contact Chemistry and HP for assisatance in determining the SGTR. Acknowledge their request.

When directed from the floor, FREEZE the simulator. DO NOT RESET till allowed by the NRC Chief Examiner.

OP-TEST #1 SCENARIO #3 Page 20 of 20 Batch File:

>BAT 2004SCN03.txt

> "C" S/G Level channel fails high IMF mFWM02C4 (1) 100 20

>Normal Charging pump trips IMF mCVC13C (2)

>Excessive seal leakoff "A" RCP IMF mCVC06A (4) 9.5 180 5.7

> SGTR develops on "A" S/G IMF mRCS02A (5) 250 200 50

> Main Turbine fails to Auto Trip IMF mTUR08C

>Both ESW pumps fail to auto start IOR P19019B 0 IOR P19028B 0

>END OF FILE

OP-TEST #1 SCENARIO #3 Page 21 of 21 SHIFT BRIEFING INFORMATION THIS FORM IS FOR TRAINING PURPOSES ONLY CONTROL ROOM TURNOVER CHECKLIST DATE : Today NIGHT SHIFT X DAY SHIFT MODE- 1 OFF-GOING: (PRINT) CRS ON-COMING: (PRINT) CRS RO RO BOP BOP SE SE ON-COMING CRS/SE/RO/BOP REVIEW EVOLUTIONS IN PROGRESS: Borating 100 gallons every 30 minutes to hold power.

MAINTENANCE IN PROGRESS: None TESTING IN PROGRESS:

SIGNIFICANT LCOs IN EFFECT:

REACTOR POWER 30 % RCS: 566.5 °F 2235 PSIG ROD CONTROL AUTO X MANUAL CONTROL BANK D 171 STEPS RCS BORON (Cb) 1360 PPM @ DATE/TIME Today/0400 LEAK RATE IDENTIFIED .02 UNIDENTIFIED .01 @ DATE/TIME Today/

(GPM): 0400 COND. AIR (total) )

INLEAKAGE 13.8 (IAW STN CH-020)

ESF STATUS PANELS AND REACTOR TRIP/BLOCK PANEL PANEL COMPONENT/TRIP/BLOCK REASON TRAINING ONLY ALARM WINDOW DESCRIPTION WINDOW NAME REASON WR/WO 78B/78C PWR RANGE N/A UPR/LWR FLUX Current power level.

DEV 103D FW HTR DUMP N/A VALVE OPN Current power level.

103E HTR DRN TANK N/A DUMP Current power level.

OP-TEST #1 SCENARIO #3 Page 22 of 22

ML042080207

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