Text

Draft - Section a Operating Exam (Folder 2)
	ML083040108
Person / Time
Site:	Nine Mile Point
Issue date:	09/01/2008
From:	; NRC Region 1
To:	;
	Hansell S
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NRC JPM RO COO1 Constellation Energy Group NINE MIILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Perform Control Room System Lineup Verification Revision: NRC 2008 Task Number: N/A Approvals :

g L 4, 6 N/A - Exam Security General Supervisor Date Operations Training (Designee)

Operations (Designee)

NIA - Exam Securitv Configuration Control Date Performer:

(RO)

Trainer/Evaluator :

Evaluation Method: Perform Evaluation Location: Simulator Expected Completion Time:

15 minutes Time Critical Task No Alternate Path Task No Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature:

Date:

NRC 2008 RO ADMIN JPM COO1 October 2008

Recommended Start Location: Simulator Simulator Set-up: IC-187 (100% power IC with the following overrides)

Place 60-1 8B EC Makeup LCV 12 in MAN Verify open Containment Spray Suction Valve 122. Hang red clearance on switch indicating that the valve should be closed.

Place Containment Spray Pump 122 control switch in PTL with a red clearance tag applied.

Activate remote CS06 for Core Spray 40-3 1 BRK STATUS RACK IN (K Panel red light is ON)

Directions to the Instructor/Evaluator:

Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, o'btain specific SM / CSO permission.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plart equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas Pass/Fail.

2. During Evaluated JPM:

0

3. During Training JPM:

0 0

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. N1 -PM-DO02 Attachment 1

2. WA 2.1.3 1 (4.2) Ability to locate control room switches/controls and indications and to determine that they are correctly reflecting the desired plant lineup.

NRC 2008 RO ADMIN JPM COO1 October 2008

Tools and Equipment:

1. None.

Task Standard: Perform the panel K checks of N1-IM-D002, Control Switch Lineup Verification, attachment 1, and identify incorrect lineups.

Initial Conditions:

1. The plant is operating at 100% power.

2. You are the oncoming day shift RO.

3. N1-PM-D002, Control Switch Lineup Verification, attachment 1 is in progress.

4. Ask the operator for any questions.

Initiating cue:

(Operators name), complete the panel K checks of N1 -PM-D002, Control Switch Lineup Verification, attachment 1.

1. Provide repeat back of initiating cue.

Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME

2.

3.

4.

Obtain a copy of the reference procedure and reviewhtilize the correct section.

Proceed to K Panel to continue lineup.

Record Attachment 1 lineup verifications, starting with section 1.2 and evaluates plant status.

NRC 2008 RO ADMIN JPM COO1 Proper communications used for repeat back Sat/Unsat (GAP-OPS-0 1)

N1 -PM-DO02 obtained and Attachment 1 reviewed SatAJnsat Proceeds to K Panel to perform panel lineup checks SaWnsat 0 Performs checks for Liquid Poison system Sat/Unsat Performs checks for Emergency Cooling Sad Unsat system 0

Identifies LC-60-18B EM CONDSR PasdFail MAKEUP LCV 12 in manual October 2008

Identifies CONT SPRAY SUCTION Pass/Fail ISOLATION VALVE 122 is open with a red clearance tag applied requiring the valve to be closed 0 Performs checks for Core Spray system Identifies 40-3 1 CORE SPRAY VENT ISOLATION VALVE 121 position lights are ON, indicating its circuit breaker is in the wrong position.

S at/Un sat Pass/Fail

5. For abnormal switch and/or indications detected which are not expected, the Control Room Supervisor shall be immediately informed. No attempt shall be made to correct the condition prior to obtaining permission from the Control Room Supervisor, and the expected response of such actions is completely understood.

6. Reports completion of section 1.2 to SRO.

0 Immediately reports out of position Sat/Unsat switches and components to CRS.

Does not attempt to correct these Pass/Fail conditions prior to obtaining permission from the CRS.

0 Reports completion of section 2.2 SaWnsat Terminating Cue: The panel K checks of N1 -PM-D002, Control Switch Lineup Verification, attachment 1, are complete and all discrepancies have been reported io CRS.

RECORD STOP TIME:

NRC 2008 RO ADMIN JPM COO1 October 2008

Initial Conditions :

1. The plant is operating at 100% power.

2. You are the oncoming day shift RO.

3. N1 -PM-D002, Control Switch Lineup Verification, attachment 1 is in progress.

Initiating cue:

(Operators name), complete the panel K checks of N1 -PM-D002, Control Switch Lineup Verification, attachment 1.

NRC 2008 RO ADMIN JPM COO1 October 2008

Approved by:

N. F. Conicella NINE MILE POINT NUCLEAR STATION PREVENTIVE MP,INTENANCE PROCEDURE N 1 -PM-DO02 REVISION 00 CONTROL SWITCH LINEUP VERIFICATION THIS PROCEDURE PARTIALLY SUPERSEDES PROCEDURE S-PM-DO01 4/27/2007 Effective Date:

Paqe No.

Change No.

Coversheet.

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ii....

iii....

1....

2....

3....

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5....

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LIST OF EFFECTIVE PAGES Page No.

Chanqe No.

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20....

Page i Page No.

Change No.

N 1 -PM-D002 Rev 00

LIST OF EiFFECTlVE PAGES TABLE OF CONTENTS SECTION PAGE 1. 0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 PURPOSE........................................................................................................................................

1 REFERENCES AND COMMITMENTS............................................................................................

1 GENERAL TEST METHODS...........................................................................................................

2 PRECAUTIONS AND LIMITATIONS................................................................................................

3 PREREQUISITES............................................................................................................................

3 PROCEDURE..................................................................................................................................

4 RETURN TO NORMAL....................................................................................................................

4 ACCEPTANCE CRITERIA...............................................................................................................

5 RECORD REVIEW AND DISPOSITION..........................................................................................

5 ATTACHMENT 1: CONTROL ROOM SYSTEM L.INEUP VERIFICATION CHECKLIST...............................

6 ATTACHMENT 2: RADWASTE CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST........ 15 ATTACHMENT 3: TEST PERSONNEL SIGNATURE AND INITIAL LOG...................................................

20 Page ii N1-PM-DO02 Rev 00

1.o 1.I 2.0 2.1 2.2 2.2.1 2.2.2 2.2.3 2.3 2.3.1 2.3.2 2.3.3 2.3.4 2.4 PURPOSE To provide instructions to verify proper s,ystem configuration from indications available in the Control Room and Radwaste Control Room to support system operability and plant operation.

Frequency This procedure shall be performed once each shift unless waived by the SM.

REFERENCES AND COMMITMENTS Technical Specifications None Policies, Programs, and Procedures GAP-OPS-01, Administration of Operatims GAP-OPS-02, Control of Hazardous Energy and Configuration Tagging Operations Manual Technical Information DER 1-98-0851, Valve 80-1 18 Found Open DER 2003-41 56, Self Assessment Report LER 98-04, Containment Isolation Valve Left Open in Violation of Technical Specifications Due to Personnel Error.

SE 98-021 Draft B rev 0, Appendix R highllow pressure and inventory loss flow path isolation for the Core Spray System injection high point vent lines.

Commitments Sequence Commitment Number Number Descri 2tion None Page 1 N1 -PM-DO02 Rev 00

3.0 GENERAL TEST METHODS 3.1 System Operability 3.1.1, Control Room System Lineup Verification is used to verify that certain key control room switches an8 indications conform to normal operating lineup requirements to support system operability and overall plant operation.

3.1.2 Satisfactory completion of this procedure does not in itself verify complete system operability, since only certain key control room indications are checked. The respective Operating Procedure shall be utilized to determine full system lineup requirements and overall operability.

3.2 Completion of Attachments 1 & 2 3.2.1 Attachments 1 & 2 are divided into critical parameters and panels. Each panel covers switches and indications for a control room panel.

3.2.2 During periods of peak control room activities such as plant startups and shutdowns, personnel are normally assigned to higher priority tasks. Performance of this procedure may be waived by the SM under these circumstances and procedure performance resumed as soon as the plant activity level permits.

3.2.3 Switch positions and/or indications that differ from the Normal Position identified in Attachments 1 & 2 due to Clearances, Control Tags, or other evolutions in progress should be noted in Remarks.

3.2.4 Normal Positions identified in Attachments 1 & 2 reflect normal, full power plant operation. When performing this procedure during plant shutdown conditions, or less than full power operating conditions, it is expected that certain discrepancies will exist. Discrepancies identified for such conditions should be noted in Remarks.

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3.2.5 For abnormal switch and/or indications detected which are not expected, the Control Room Supervisor shall be immediately informed. No attempt shall be made to correct the condition prior to obtaining permission from the Control Room Supervisor, and the expected response of such actions is completely understood.

3.26 Unless otherwise specified in Attachments 1 & 2, the normal position of all switches designed to spring return to Neutral, Auto, Auto-Start, etc., shall be the spring return position. Green/Red flag conditions will also correspond to switch position, unless otherwise stated.

Page 2 N1 -PM-DO02 Rev 00

4.0 PRECAUTIONS AND LIMITATIONS 4.1 Failure to notify the Control Room Supervisor (CRS) immediately whenever a procedural step cannot be completed as stated, or if any unexpected system lineup discrepancies are detected during the test, may result in a Technical Specification violation.

4.2 An unexpected plantkystem response may occur if an attempt is made to re-position or otherwise correct an out of normal systemlcomporient condition. Obtain permission from the Control Room Supervisor prior to re-positioning any equipment.

5.0 PREREQUISITES 5.1 Specify the reason for test performance.

(4 Routine Performance

(-)

Other (specify) 5.2 Verify that personnel responsible for thc performance of this procedure have reviewed the procedure in its entirety, a i d thoroughly understand it's content.

5.3 Notify SM that procedure is to be perfomed.

PLANT IMPACT:

NONE 5.4 Notify CSO that procedure is to be performed Initials Page 3 N1-PM-DO02 Rev 00

6.0 PROCEDURE 6.1 Observe panel switches and/or indications listed in Attachments 1 & 2, and determine whether they conform to the Normal Position specified. Check "Yes" or "No" column as applicable.

If switch positions and/or indications differ from the Normal Position identified in Attachments 1 & 2 due to expected conditions such as Clearances, Control Tags, or other evolutions in progress, include a note in the RemarksSection V

6.2 6.3 If unexpected discrepancies are identified between actual switch positions and/or indications, and the Normal Position identified in Attachments 1 & 2, immediately notify the Control Room Supervisor (CRS) of the condition. Do NOT attempt to correct the condition prior to obtaining CRS permission.

6.4 Upon identification of any abnormal switch position or indication;

a.

the CRS shall coordinate corrective action to restore the system to normal, including a pre-assessment of expected response prior to manipulating any equipment.

b.

initiate a CR to document the occurrence, and to determine operability and reportability.

7.0 RETURN TO NORMAL Initials Verify all personnel performing this procedure have signed and initialed, TEST PERSONNEL SIGNATURE AND INITIAL LOG.

Page 4 N1-PM-DO02 Rev 00

8.0 ACCEPTANCE CRITERIA 8.1 All test documentation completed.

0630-1 830 1830-0630

(-)

SAT

(-)

UNSAT

(-)

SAT

(-)

UNSAT Remarks:

I I

Completed by CRSlSM Date Completed by CRS/SM Date 8.2 Second Review All test data reviewed AND documentation completed.

9.0 9.1 9.2 9.3 STNSRO Signature Date Time RECORD REVIEW AND DISPOSITION The following records generated by this procedure shall be maintained by Records Management for the Permanent Plant File in accordarce with Procedure NIP-RMG-01, Records Management:

0 None The following records generated by this procedure are not required for retention in the Permanent Plant File:

0 The completed procedure The permanent record for the completion of this procedure will,e a log entry for both Attachments 1 & 2. Retention of the coripleted procedure is not required.

Page 5 N l -PM-DO02 Rev 00

ATTACHMENT 1 Page 1 of 9 1.1 PANEL-L CAD CHANNEL 11 RPS BY-PASS CAD CHANNEL 12 RPS BY-PASS CONTAINMENT MONITOR SYS 11 SAMPLE STREAM DW I TORUS CONTAINMENT MONITOR SYS 12 SAMPLE STREAM

- DW I TORUS NORMAL NORMAL WHITE AND BLUE LIGHTS CYCLE ON/OFF WHITE AND BLUE LIGHTS CYCLE ONlOFF 201.7-01 & 201.7-02 CONTAINMENT MONITOR SYS 11 OPEN DRYWELL SAMPLE ISOL VLVS TORUS SAMPLE ISOL VLVS 201.2-1 10 & 201.2-1 11 CONTAINMENT MONITOR SYS I 1 OPEN 201.2-109 & 201.2-1 12 CONTAINMENT MONITOR SYS 11 OPEN TORUS RETURN ISOL VLVS

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TORUS SAMPLE ISOL VLVS

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201.2-23 & 201.2-24 CONTAINMENT MONITOR SYS 12 OPEN 201.2-29 & 201.2-30 CONTAINMENT MONITOR SYS 12 OPEN DRYWELL SAMPLE ISOL VLVS RANGE RANGE ANALYZER RANGE CONTAINMENT MONITOR SYS 11 OXYGEN ANALYZER 0 - 5%

CONTAINMENT MONITOR SYS 12 OXYGEN ANALYZER 0 - 5%

CONTAINMENT MONITOR SYS 11 HYDROGEN 0 - 5%

I CONTAINMENT MONITOR SYS 12 HYDROGEN CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST 0630-1830 1830-0630 IN NORMALCONDITION (J) COLUMN NORMAL SYSTEWCOMPONENT DESCRIPTION POSITIOWCONDITION YESIN0 YESINO J I i

/

Remarks:

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Page 6 Nl-PM-DO02 Rev 00

Page 2 of 9 LIQUID POISON EXPL VALVE 11 CONTINUITY WHITE LIGHT ON I

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ATTACHMENT 1 (CONT)

CONTROL ROOM SYSTEiM LINEUP VERIFICATION CHECKLIST 0630-1 830 1830-0630 IN NORMALCONDITION (4)

COLUMN NORMAL SYSTEWCOMPONENT DESCRIPTION --

POSlTlON/CONDlTlON YESlNO YESlNO I

EM VENT EXHAUST FAN 11 INLET FCV 202-53

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EVS FAN 11 EM VENTILATION LOO P 11 COOLING BV, and I AUTO1 I

I Remarks:

Page 7 N1-PM-DO02 Rev 00

CONTROL ROO VALVE 11 05-03R EM COND VENT TO MN STM ISOLATION ATTACHMENT 1 (CONT) il SYSTEM LINEUP VERIFICATION CHE I

I OPEN NORMAL I

I I

05-04R EMERG COND VENT ISOLATION VALVE 121 05-12 EMERG COND VENT ISOLATION VALVE 122 OPEN I

I 05-05 EC VENT TO TORUS BV 11 CLOSED I

I 05-07 EC VENT TO TORUS BV 12 CLOSED I

I I

I 60-13 EMERGENCY CONDENSER MAKEUP TIE VALVE 1 OPEN

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I I

LC-60-18B EM CONDSR MAKEUP LCV 12 AUTO1 CLOSED

- VALVE 12 OPEN

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- LC-60-17B EM CONDSR MAKEUP LCV 11 AUTO1 CLOSED

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_____ 04 EMERGENCY CONDENSER MU TANK FILL V 11 CLOSED Page 3 of 9 60-03 EMERGENCY CONDENSER MU TANK FILL V 12 CLOSED OPEN OPEN OPEN OPEN KLlST I

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i I

I

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0630-1830 1830-0630 IN NORMALCONDITION (4) COLUMN SYSTEWCOMPONENT DESCRIPTION POSITION/CONDITION YESlNO YES/NO 1 05-02R EM COND VENT TO MN STM ISOLATION I OPEN I

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Remarks:

Page 8 N1-PM-DO02 Rev 00

ATTACHMENT 1 (CONT)

CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST Page 4 of 9 NORMAL 063 0-1 830 183 0-0630 IN NORMALCONDITION (4)

COLUMN SYSTEWCOMPONENT DESCRIPTION POSlTlOWCONDlTlON YESlNO YES/NO I

93-26 OPEN h-74,93-27 CONT SPRAY RAW WTR 122 I N T E R T Y 93-74 CLOSED, I

93-27 OPEN I

CONT SPRAY SUCTION ISOLATION VALVE 11 1 OPEN

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I CONT SPRAY SUCTION ISOLATION VALVE 112 OPEN I

CONT SPRAY SUCTION ISOLATION VALVE 121 OPEN

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I CONT SPRAY SUCTION ISOLATION VALVE 122 OPEN I

80-1 14 CONT SPRAY TO RAD WASTE IV 1 1 I

80-1 15 CONT SPRAY TO RAD WASTE IV 12 I

TORUS MAKEUP VALVE 1 CLOSED

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CLOSED CLOSED Remarks:

Page 9 N1-PM-DO02 Rev 00

ATTACHMENT 1 (CONT)

Page 5 of 9 CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST NORMAL 0630-1830 1830-0630 IN NORMALCONDITION (J) COLUMN SYSTEIWCOMPONENT DESCRIPTION POSITION/CONDITION YEWNO YES/NO 11.3 PANEL-H I

Remarks:

Page 10 N1 -PM-DO02 Rev 00

AlTECHMENT 1 (CONT)

CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST WOTOR FEEDWATER PUMP HIGH LEVEL TRIP B\\r=

'UMP 11

?UMP 12 FEEDWATER ISOLATION VALVE 12 KOTOR FEEDWATER PUMP HIGH LEVEL TRIP BYPASS FEEDWATER ISOLATION VALVE I I FEEDWATER PUMP I I BLOCKING VALVE FEEDWATER PUMP 12 BLOCKING VALVE FEEDWATER PUMP I I RECIRC v I I I 29-23 FEEDWATER PUMP 1 I RECIRC v I 12 29-51 FEEDWATER PUMP 12 RECIRC v 121 29-24 FEEDWATER PUMP 12 RECIRC V 122 29-52 FW LVL SETPOINT SETDOWN EMC-29-156 FWP 11 VALVE CONTROL, andlor RMC-29-157 FWP 12 VALVE CONTROL RMC-29-498 FWP 1 I BYPASS VALVE RMC-29-50B FWP 12 BYPASS VALVE Page 6 of 9 NORMAL I

NORMAL I

I OPEN I

OPEN

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I OPEN I

OPEN

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I CLOSED I

CLOSED I

CLOSED

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I NORMAL CLOSED FOR FW PMP I

OFF I

MANUAL, CLOSED I

MANUAL, CLOSED

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NORMAL GREEN LIGHTS ON CLOSED, BLUE AND 0630-1830 1830-0630 IN NORMALCONDITION (4)

COLUMN I

SYSTEWCOMPONENT DESCRIPTION --

POSlTlON/CONDlTlON YESlNO YES/NO NR-I08C ERV 121 NR-108D ERV 122 I

GREEN LIGHTS ON

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CLOSED, BLUE AND I

GREEN LIGHTS ON CLOSED, BLUE AND NR-108B ERV 112 NR-108F ERV 123 I

GREEN LIGHTS ON

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CLOSED, BLUE AND I

NR-108E ERV 11 3 I GREEN LIGHTS ON I

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I I I -___

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I Remarks:

'age 11 N1 -PM-DO02 Rev 00

AllACHMENT 1 (CONT)

Page 7 of 9 CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST 0630-1830 1830-0630 IN NORMALCONDITION (4)

COLUMN NORMAL SYSTEWCOMPONENT DESCRIPTION POSlTlON/CONDlTlON YES/NO YESlNO B.U. SCRAM S.D.V. VENT & DRAIN GROUP 5 ATWS. CH 11 REACTOR HI PRESS CH. 11 -1 & 11 -2, and RED LIGHT ON ALL RED LIGHTS O F

REACTOR LO-LO LVL CH. 11-1 & 11-2 ARI INITIATION CH. 11 CHANNEL 12 SCRAM SOLENOID GROUPS 1-4, and RED LIGHT OFF ALL WHITE LIGHTS ON, B.U. SCRAM S.D.V. VENT & DRAIN GROUP 5 ATWS-ARI VALVE POSITION SOVI113-229A RED LIGHT ON GREEN LIGHT ON, RED LIGHT OFF GREEN LIGHT ON, RED LIGHT OFF ATWS-ARI VALVE POSITION SOVII 13-229B ARI OVERRIDE KEYLOCKED NORMAL, RED LIGHT OFF ALL RED LIGHTS OFF ATWS. CH 12 REACTOR HI PRESS CH. 12-1 & 12-2, and I 55-05 DEMIN WATER SUPPLY TO CRD SYS BLOCKING VALVE CRD FLOW CONTROL VALVE 11 TRANSFER, VALVE 11 OR VALVE 12 I CRD FLOW CONTROL VALVE 12 TRANSFER; AND I SELECTED, VALVE VALVE I 1 VALVE 12 THROTTLED SCRAM DISCH VOL HLD TANK DISCHARGE BV 67-30 CLOSED I

I I

I 1 1.5 E CONSOLE I

I SPDS COMPUTER SCREEN SPDS ON D l S P W I

I MECHANICAL PRESSURE REG YELLOW LIGHTOFF

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I I

BYPASS OPENING JACK YELLOW LIGHT OFF

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ELECTRICAL PRESSURE REG YELLOW LIGHT ON

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Re marks :

Page 12 N1 -PM-DO02 Rev 00

ATTACHMENT 1 (CONT)

- SYN SELECTOR R1032 MAN I

I R1032 OPEN I

I 1.9 PANEL-A6

_ _ _ _ _ ~

Page 8 of 9 TAP CHGER CONT 101 N TAP CHGER CONT 101 S RECLOSING SELECTOR R915 CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST

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AUTO I

I I

I AUTO sc I

I 0630-1830 1830-0630 IN NORMALCONDITION (4)

COLUMN NORMAL SYSTEWCOMPONENT DESCRIPTION POSlTlON/CONDlTlON YES/NO YES/NO AUTO RECLOSING R915 ON AUTO RECLOSING R925 ON 7

PANEL-A4

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I I

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I 1.8 PANEL - A5 RECLOSING SELECTOR R925 AUTO RECLOSING R10 AUTO RECLOSING R40 sc I

I ON I

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Remarks:

Page 13 N1-PM-DO02 Rev 00

ATTACHMENT 1 (CONT)

Page 9 of 9 CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST 0630-1830 1830-0630 IN NORMALCONDITION (4)

COLUMN NORMAL POSlTlONlCONDlTlON YESiNO YESlNO SY STEWCOMPONENT DESCRl PTlON 1.13 PANEL-N Shift Turnover Checklist Completed by Reactor Operator I

Signature Time Signature Time All discrepancies discussed with CRS and noted in remarks section Signature Time Signature Time I

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Remarks:

Page 14 N1-PM-DO02 Rev 00

ATTACHMENT 2 A 0 85-489 WCF DRAIN BV CLOSED OPEN IF FILTER IN Page 1 of 5 I

I RADWASTE CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST A 0 85.1-266 FDF OUTLET BV A 0 85.1-270 FDF PRECOAT INLET BV A 0 85.1-347 FDF PRECOAT OUTLET BV A 0 85.1-348 FDF BACKWASH BV A 0 85.1-343 FDF INLET BV A 0 85.1-267 FDF VENT BV A 0 85.1-268 FDF DOME DRAIN BV A 0 85.1-360 FDF AIR BUMP BV NORMAL SERVICE I

I CLOSED I

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I CLOSED OPEN IF FILTER IN SERVICE I

I CLOSED I

I I

I CLOSED

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AUTO-PUMP RUNNING

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-~

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~-

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0630-1830 1830-0630 IN NORMALCONDITION (4)

COLUMN FDF RECYCLE PUMP FILTER AID PUMP SYSTEMKOMPONENT DESCRIPTION -_

POSlTlONlCONDlTlON YESlNO YES/NO IF FILTER IN SERVICE I

I OFF I

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I 2.1 WASTE COLLECTOR FILTER PANEL SERVICE CLOSED 85-459 WCF OUTLET BV 85-493 WCF PRECOAT INLET BV A 0 85-486 WCF PRECOAT OUTLET BV CLOSED 85-487 WCF BACKWASH BV CLOSED OPEN IF FILTER IN CLOSED AUTO-PUMP RUNNING IF FILTER IN SERVICE I

I NEUTRAUOFF I

-___ I OFF

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FLOOR DRAIN FILTER PANEL I

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CLOSED OPEN IF FILTER IN Remarks:

Page 15 N1 -PM-D002 Rev 00

ATTACHMENT 2 (CONT)

WASTE BLDG VENT EXHAUST FAN 11 Page 2 of 5 OFF RADWASTE CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST WASTE BLDG VENT EXHAUST FAN 12 WASTE BLDG VENT EXHAUST DlSCH B.V. 11 0630-1830 1830-0630 IN NORMALCONDITION (J) COLUMN NORMAL SYSTEWCOMPONENT DESCRIPTION POSlTlONlCONDlTlON Y ESlNO YESlNO OPEN FOR FAN O N

I WASTE BLDG VENT SUPPLY SUCTION B.V. 12 WASTE COLLECT. TK. CONDUCTIVITY REACTOR BLD EQ DR TANK CLOSED LOOP COOLING WASTE COLLECTOR TANK CLOSED LOOP COOLING OFF NORMAL OPEN OPEN DISCHARGE STORAGE ROUTE WASTE COLLECTOR P 11 WASTE COLLECTOR P 12 WASTE COLLECTOR PUMPS 11 & 12 CONDUCTIVITY WASTE COLLECTOR PUMPS DISCH BV WASTE SURGE PUMP INLET BV WASTE SURGE PUMP WASTE SURGE PUMP DISCH ROUTE DRYWELL EQUIP DR TKS INSIDE ISOL VALVE 11 DRYWELL EQUIP DR TKS OUTSIDE ISOL VALVE 12 WASTE COLLECTOR F DISCH BV WASTE COLLECTOR F INLET BV 1 WASTE DISPOSAL BLDG EXHAUST INLET B.V. 1 I I CLOSED FOR FAN OFF CLOSED NEUTRAUSTOP N EUTRAUSTOP OFF OPEN NEUTRAUCLOSED N EUTRAUSTOP OFF OPEN OPEN OPEN IF FILTER IN-SERVICE OPEN IF FILTER IN SERVICE MANUAL, THROTTLED

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WASTE BLDG VENT EXHAUST DlSCH B.V. 12 WASTE DISPOSAL BLDG EXHAUST INLET B.V. 12 I FAN ON AND I FAT WCF FLOW CONTROL VLV A 0 WASTE DEMINERALIZER INLET BV WASTE DEMINERALIZER DlSCH BV I WASTE BLDG VENT SUPPLY FAN 11 I OFF IF FILTER IN SERVICE OPEN OPEN WASTE BLDG VENT SUPPLY FAN 12 I OPENiTHROTTLED FOR I WASTE BLDG VENT SUPPLY SUCTION B.V. 11 I ECLOSED FOR FAN I 85-100 OPEN, 85-99 I

Remarks:

Page 16 Nl-PM-DO02 Rev 00

ATTACHMENT 2 (CONT)

CLOSED OPEN IF FILTER IN Page 3 of 5 I

I RADWASTE CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST I

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SERVICE OPEN IF FILTER IN NORMAL I

0630-1830 1830-0630 IN NORMALCONDITION (J) COLUMN PUMP INLET BYPASS BV UTILITY COLLECTOR PUMP

- UTILITY COLLECTOR PUMP DISCHARGE SELECT SYSTEWCOMPONENT DESCRIPTION POSITION/CONDITION Y ES/NO YES/NO I

I NEUTRAUCLOSED I

I NEUTRAUSTOP

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OFF I

I

~

DEMINERALIZED WASTE ROUTE WASTE SAMPLE PUMP 11 WASTE SAMPLE PUMP 11 RECIRCULATION BV WATE SAMPLE PUMP 11 FILTER BACKWASH BV-WASTE SAMPLE PUMP 11 DlSCH BV WASTE SYSTEM TELL TALE BV WASTE SAMPLE PUMP 12 WASTE SAMPLE PUMP 12 RECIRCULATION BV WASTE SAMPLE PUMP 12 FILTER BACKWASH B WASTE SAMPLE PUMP 12 DlSCH BV DEMINERALIZED WASTE TO SAMPLE TKS SELEF DISCHARGE FLOW CONTROL RMC 85-523 DISCHARGE FLOW BV SELECT 85-79 AND 85-27 FLOOR DRAIN FILTER INLET BV FLOOR DRAIN FILTER DlSCH BV FLOOR DRAINS TO SAMPLE TANKS SELECT FLOOR DRAIN SAMPLE PUMP 11 INLET BV FLOOR DRAIN SAMPLE PUMP 1 I FLOOR DRAIN SAMPLE PUMP 11 RECIRC BV FLOOR DRAIN SAMPLE PUMP 12 INLET BV FLOOR DRAIN SAMPLE PUMP 12 FLOOR DRAIN SAMPLE PUMP 12 RECIRC BV UTILITY COLLECTOR TK AGITATOR CONCENTRATOR FEED PUMPS 11 & 12 INLET B UTILITY COLLECTOR PUMP INLET BV UTILITY COLLECTOR PUMP WASTE NEUTRALIZ' Remarks:

Page 17 N1-PM-DO02 Rev 00

ATTACHMENT 2 (CONT)

Page 4 of 5 RADWASTE CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST 0630-1830 1830-0630 IN NORMALCONDITION (4)

COLUMN NORMAL SYSTEWCOMPOhENT DESCRIPTION POSlTlON/CONDlTlON YESlNO YES/NO I MANUAL,THROTTLED 1

Remarks:

Page 18 Nl -PM-D002 Rev 00

AllACHMENT 2 (CONT)

Page 5 of 5 RADWASTE CONTROL ROOM SYSTEM LINEUP VERIFICATION CHECKLIST 0630-1 830 1830-0630 IN NORMALCONDITION (4)

COLUMN NORMAL SYSTEWCOMPONENT DESCRIPTION --

POSlTlON/CONDlTlON YESlNO YESlNO CONC WASTE TK 12 DlSCH BV CONC WASTE TK 12 FLUSH BV CONC WASTE PU 12 INLET BV CONC. WASTE PUMP #I2 NEUTRAUSTOP CONC WASTE PU 12 DISCH BV NEUTRAUCLOSED CLOSED CLOSED CLOSED KEYLOCKED, OFF, 57-72 AND 57-73 FILTER SLUDGE TRUCK FILL BV STEAM FLOW TO CONC #I 2 FCV OFF,45-153 AND 45-289 CONC #12 WASH SELECTOR SWITCH FLOOR DRAIN SAMPLE TANK #11 BV FLOOR DRAIN SAMPLE TANK #12 BV WASTE NEUTRALIZER TANK INLET BV CONC. FEED PUMP #I2 INLET SELECT CLOSED CONCENTRATOR FEED PUMP #I2 N EUTRAUSTO P CONCENTRATOR FEED PUMP #I2 DlSCH BV NEUTRAUCLOSED CONCENTRATOR CIRC. PUMP #I2 NEUTRAUSTOP CONC WASTE TK 12 LCV MANUAL, CLOSED CONC #I2 DENSITY SETPOINT CONTROL VARIES CONCENTRATOR #I2 DlSCH ROUTE BV VARIES RECIRC, 45.4-51 OPEN, CONC. WASTE TRANSF. PU. #I2 DlSCH ROUTE CONC. #I2 WASTE TRANSFER PU. #I2 CONCENTRATED WASTE TRANSFER PU. INLET CONCENTRATOR #12 FLUSH BV WASTE BLDG. (EXT) EXHAUST FAN #13 WASTE BLDG. (EXT) EXHAUST FAN #I4 WASTE BLDG. (EXT) EXHAUST DlSCH BV #I 3 WASTE BLDG. (EXT) EXHAUST SUPPLY BV #I3 WASTE BLDG. (EXT) EXHAUST DlSCH BV #14 WASTE BLDG. (EXT) EXHAUST SUPPLY BV #I4 CONC. #I2 DISTILLATE ROUTING RMS45-284 CLOSED 1 FAN ON AND 1 FAN OPEN FOR FAN ON, CLOSED FOR FAN OFF LO,45-266 OPEN,45-267 CLOSED Remarks:

Page 19 N 1 -PM-D002 Rev 00

ATTACHMENT 3: TEST PERSONNEL SIGNATURE AND INITIAL LOG NOTE: Completing this attachment signifies that each person has reviewed the applicable portions of this procedure.

?

PRINTED NAME T o n y

% I !

SIGNATURE

/;c^&T4, INITIALS mbf Page 20 N1-PM-DO02 Rev 00

NRC JPllll RO/SRO COO2 Constellation Energy Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Determine Personnel Overtime Availability [AW GAP-FFD-02 Revision: NRC 2008 Task Number: N/A N/A - Exam Security

/

General Supervisor Date Operations Training (Designee)

Operations (Designee)

N/A - Exam Securitv I

Configuration Control Date TrainerEvahator:

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time:

20130 minutes Time Critical Task:

No Alternate Path Task:

No (ROJSRO)

Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature:

Date:

NRC 2008 ADMIN JPM COO2 October 2008

Recommended Start Location: Classroom Simulator Set-up: None Directions to the InstructorEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not a.vailable and that additional / concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional I concurrent verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as P'ass/Fail.

2. During Evaluated JPM:

0

3. During Training JPM:

0 0

Self verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. GAP-FFD-02 Tools and Equipment:

1. Calculator NRC 2008 ADMIN JPM COO2 October 2008

Task Standard:

Determine Personnel Availabilily for Overtime IAW GAP-FFD-02.

Initial Conditions:

1. The plant is shutdown.

2. In order to support critical path work required far startup, personnel overtime will be required for the night shift on October 26 from 1830-0630.

3. All the overtime hours will be spent performing (ROs) or supervising (SROs) field activities.

Initiating Cues:

1.

2.

3.

From the provided list of personnel working hows, determine who is eligible to work a complete 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of overtime beginning at 1830 on October 26 without requiring an Overtime Deviation Request IAW GAP-FFD-

02.

If an Overtime Deviation Request would be required for individual(s), state the work hour limit(s) which would be exceeded IAW GAP-FFD-02.

SROs ONLY - Complete the appropriate sections of an Overtime Deviation Request Form for all individuals who would need a deviation approved to cover the shift.

EXAMINER NOTE: FOR ROs - Provide Attachments A & C.

FOR SROs - Provide Attachments A, B & D, and Blank Overtime Deviation Request Form.

Performance Steps Standard Grade -

1.

Provide repeat back of initiating cue.

Proper communications used for repeat back Sat/Unsat Evaluator Acknowledge repeat back providing correction ifnecessary.

(GAP-OPS-0 1 /Operations Manual)

RECORD START TIME

2.

Obtain a copy of the reference procedure and reviewhtilize the correct section of the procedure.

GAP-FFD-02 obtained Sat/Unsat NRC 2008 ADMIN JPM COO2 October 2008

3.

FOR ROs - Reviews work hours for Reactor Operators 1 thru 3 ROs - Determines the following:

RO #1 - Eligible Pass W a i 1 RO #2 -Not Eligible - would exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 day period RO #3 - Not Eligible -would exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period FOR SROs - Reviews work hours for Reactor Operators 1 thru 3 and Senior Reactor Operators 1 and 2 SROs - Determines the above limitations plus the following:

SRO #1 - Eligible SRO #2 - Not Eligible - would exceed 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

4.

FOR SROs - Completes Overtime Deviation Request Form Completes Columns 1 and 2 of Part 1 of GAP-FFD-02 Attachment 1, per attached key Pass/Fail Completes Columns 3 and 4 of Part 1 of GAP-FFD-02 Attachment 1, per attached key Sat/Unsat Completes Part 2 of GAP-FFD-02 Attachment 1, per attached key Sat/Unsat TERMINATING CUE: FOR ROs, JPM Attachment C completed. FOR SROs, JPM Attachment D and GAP-FFD-02 Attachment 1 completed RECORD STOP TIME NRC 2008 ADMIN JPM COO2

- 4 -

October 2008

ATTACHMENT A - ROS 1011 9 1830-0642 (includes 12 minutes of turnover time)

I RO #I 10120 10/21 10123 10124 10/25 10126 1830-0642 1830-0706 12 (includes 12 (includes 36 minutes of minutes of turnover time) turnover time) 1830-0642 (includes 12 minutes of turnover time)

OFF RO #2 I

1830-0642 1830-0630 1830-0642 1830-0654 1830-0642 1830-0642 (includes 12 (includes 0 (includes 12 (includes 24 (includes 12 (includes 12 minutes of minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time) turnover time)

I 10119 I

10120 I

10/21 I

10/29:

1 10/23 I

10/24 I

10/25 I

10/26 I

10/19 1830-0642 (includes 12 minutes of turnover time) 10/20 1 012 1 10122 10123 10124 10125 10126 1830-0630 1830-0648 1830-0642 1830-0642 1830-0742 (includes 0 (includes 18 (includes, 12 (includes 12 (includes 12 minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time)

I RO #3 I

NRC 2008 ADMIN JPM COO2 October 2008

ATTACHMENT B - SROS 1011 9 (includes 12 minutes of turnover time) 1830-0642 10120 1 012 1 10/2i!

1 0123 10124 (includes (includes (includes 12 minutes OFF 65 minutes OFF 12 minutes of turnover of turnoter of turnover time) time) time) 1830-0642 1830-0735 1830-0642 10125 1011 9 1830-0720 (includes 50 minutes of turnover time) 10120 1 012 1 1012i:

1 0123 10124 1 0125 10126 10126 OFF 1830-0642 (includes 12 minutes of turnover time) 1830-0630 1830-0648 1830-0642 0630-1 830 (includes 0 (includes (includes (includes 0 minutes of 18 minutes 12 minutes OFF minutes of OFF turnover of turnover of turnoter turnover time) time) time) time) 0500-1200 (includes 0 minutes of turnover time)

NRC 2008 ADMIN JPM COO2 October 2008

ATTACHMENT C - RO Answer Sheet Eligible to work without an Overtime Deviation Request?

If No, what work hour limit@)

would be exceeded IAW GAP-RO #1 RO #2 RO #3 NRC 2008 ADMIN JPM COO2 October 2008

ATTACHMENI' D - SRO Answer Sheet Eligible to work without an Overtime Deviation Request?

(Yes/No)

RO #1 RO #2 If No, what work hour limit(s) would be exceeded IAW GAP-FFD-02?

~~

RO #3 SRO #1 NRC 2008 ADMIN JPM COO2 October 2008

Initial Conditions:

1. The plant is shutdown.

2. In order to support critical path work required for startup, personnel overtime will be

3. All the overtime hours will be spent plxforming (ROs) or supervising (SROs) field required for the night shift on October 26 fi-om 1830-0630.

activities.

Initiating Cues:

1. From the provided list of personnel working hours, determine who is eligible to work a complete 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of overtime beginning at 1830 on October 26 without requiring an Overtime Deviation Request IAW (GAP-FFD-02.

2. If an Overtime Deviation Request would be required for individual(s), state the work hour limit(s) which would be exceeded IAW GAP-FFD-02.

3. SROs ONLY - Complete the appropriate sections of an Overtime Deviation Request Form for all individuals who would need a deviation approved to cover the shift.

NRC 2008 ADMIN JPM COO2 October 2008

Nine Mile Point Nuclear Station Stat ion Ad nn in ist rat ive Proced u re GAP-FFD-02 CONTROL OF WORKING HOURS Revision 01 700 50.59 Review Tech Spec.

INFORMATION USE Applicable To:

Nine Mile Point Nuclear Station, Units 1 and 2 Sponsor: Director-Licensing (NMP)

Approval Authlority: Plant General Manager

CONTROL OF WORKING HOURS GAP -FF D-02 Revision 01 700 Page 2 of 10

SUMMARY

OF ALTERATIONS Revision Change Summary of Revision or Change 01 7 00 Reworded Section i5.3.A Section 7: Added yidance for retention of monthly overtime reports.

GAP -F F D-02 CONTROL OF WORKING HOURS Revision 01700 Page 3 of 10 TABLE OF CONTENTS SECTION TITLE PAGE 1. 0 2.0 3.0 4.0 5.0 6.0

7.0 INTRODUCTION

4 1.2 Scope/Applicability:.......................................................................................................

4 1. 1 Purpose........................................................................................................................

4 REFERENCES.............................................................................................................................. 4 2.1 Developmental References.......................................................................................... 4 2.2 Performance References..............................................................................................

4 DEFINITIONS...............................................................................................................................

4 RESPONSIBILITIES.....................................................................................................................

5 PROCESS..................................................................................................................................... 5 Work Hour Limits..........................................................................................................

5 5.1 5.2 Exceeding Work Hour Limits........................................................................................

6 5.3 Review of Overtime Work'ed / Independent Review.....................................................

9 BASES..........................................................................................................................................

9 RECORDS.................................................................................................................................... 9. OVERTIME DEVIATION REQUEST...............................................................................lO

CONTROL OF WORKING HOURS GAP -F FD-02 Revision 01 700 1.O INTRODUCTION 1.1 Purpose A.

To establish administrative controls necessary for the implementation of technical specification requirements on individual working hours.

B.

To ensure Station Personnel are physically/mentally fit for duty to perform job duties during extended working hour periods.

1.2 ScopelApplicability

A.

The work hour limits specified in Section 5.1.B of this procedure apply to all station and non-station personnel workin'g at NMP.

B.

The documentation requirements of Section 5.2.E apply only to personnel who perform or directly supervise those who perform safety-related functions, specially:

0 Licensed senior reactor operators, reactor operators, and non-licensed operators.

0 Chemistry, Radiation Protection, and Reactor Analyst Technicians.

0 Key Maintenance per:sonnel as defined in Section 3.B.

0 Personnel who perform inspections, examinations, or tests on safety-related Structures, Systems c r Components. [NO031

2.0 REFERENCES

2.1 Developmental References A.

B.

C.

Unit 1 Technical Specificatioris, Section 6.2.2, Unit Staff Unit 2 Technical Specificatioris, Section 5.2.2, Unit Staff Unit 2 USAR, Section 1.I

.O, Position on NUREG-0737 - I.A.1.3, Shift Manning 2.2 Performance References None 3.0 DEFINITIONS A.

7 Day Period A seven calendar day rolling period beginning at 0000 hours0 days 0 hours 0 weeks 0 months on the first day and ending at 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months on the seventh day. [ NO021

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01 700 Page 5 of 10 3.0 (Continued)

B.

Key Maintenance Personnel 4.0 5.0 5.1 Those personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of safety-related structures, systems, and components, and those personnel who are performing or immediately supervising the performance of such activities (reference GL 83-14).

RESPONSIBILITIES The following individuals and organizations are assigned responsibilities within this procedure:

A.

Plant General Manager B.

ManagerdDirectors C.

General Supervisors/Supervisors D.

PROCESS Work Hour Limits Individuals who work in excess of the limitations stated in Section 5.1 of this procedure NOTE Work hour limits are established to ensure that individuals performing activities that directly impact personnel safety and the safe and reliable operation of the plant are not overly fatigued such that their mental alertness and decision-making ability might be impaired.

A.

ManagerdDirectors shall ensure adequate shift coverage is maintained without routine heavy use of overtime. The (objective shall be to have operati ng personnel work a normal 8-12 hour day, nominal 40-hour week while the facility is operating.

B.

However, when circumstances dictate working beyond scheduled working hours, the following limitations apply:

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01 700 Page 6 of 10 5.1 (Continued)

NOTE For criteria in Section 5.1 B.1 below, turnover time should NOT be included. Turnover time of greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for any individual tour of duty is not exempted from individual overtime hours.

The below periods are consecutive mlling periods and are not based on calendar work weeks.

1.

Individuals identified i n Section 1.2 should not be permitted to work more than:

a.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight

b.

c.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period

d.

Work in excess of these limits shall NOT be routinely authorized.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period

2.

C.

There should be a break in an individuals work schedule of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a work period for which work goes beyond the limitations in Step 5.1.B.

D.

The requirements and limits specified in Steps 5.1.B and 5.1.C apply to all hours worked if any portion of an individuals total work time is spent performing or supervising field activities.

E.

Individuals working a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift schedule, who, as a result of transition in and out of daylight savings time, will exc:eed the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period guideline, are authorized to deviate from the guideline for the one hour transition period. No Overtime Deviation Request is required to be completed for this deviation.

5.2 Exceeding Work Hour Limits A.

It is recognized that deviations from the Work Hour Limits may occasionally occur. The use of overtime should be limited to circumstances where essential work must be done on an accelerated schedule and, except during extended shutdown periods, should be considered on an individual basis and not for the entire staff on a shift.

CONTROL OF WORKING HOURS GAP -FFD-02 Revision 01 700 Page 7 of 10 5.2 (Continued)

B.

Circumstances that may warrant deviating from the guidelines of Section 5.1 include, but are not limited to:

0 To respond to a Limiting Condition for Operation (LCO).

0 To complete a work activity where it is safer to complete than to secure.

0 To complete work affecting critical path during a shutdown.

a To complete work on a problem immediately affecting nuclear or industrial safety.

0 Absenteeism 0

Weather-related extension of work periods.

C.

All paid overtime should be approved by authorized supervision before the overtime is worked.

D.

The following are the requirements applicable to personnel who do NOT perform or directly supervise those who perform safety-related functions. Refer to Section 5.2.E for additional guidance.

1.

Personnel shall track their work hours and notify their supervisors if they expect to reach the limits of Section 5.1.

2.

Prior to exceeding ariy of the work hour limits in Section 5.1, personnel shall obtain verbal approvial from their Supervisor, General Supervisor, Director, or Manager. Approval shall be given only if the following conditions are met:

0 The work activity is necessary to support safe and reliable operation of the plant.

AND 0

Other personnel cannot reasonably be made available to perform the work activity.

3.

Personnel shall generate a Condition Report if work hour limits were exceeded without obtaining prior approval.

4.

Supervisors shall:

a.

Ensure personnel are fit for duty at all times.

b.

Make more frequent direct observations of personnel exceeding work hour limits.

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01 700 Page 8 of 10 5.2 (Continued)

NOTE The following personnel are required to complete Overtime Deviation Requests :

0 Operations - Personnel below General Supervisor level (except OPS Support)

Maintenance - Personnel below General Supervisor level Chemistry - Supervisors and below Rad Protection - Supervisors and below Radwaste - Supervisors and below Personnel who perform inspection of safety related equipment including:

0 0

0

- Quality Inspection Plsrsonnel

- lnservice Inspection and Test Personnel

- Contract Inspection Personnel [NO041 E.

The following are the requirements applicable to personnel who perform or directly supervise those who perform safety-related functions.

1.

Except as allowed in Section 5.2.D, Supervisors of personnel who expect to exceed the limitations of Section 5.1 shall complete Attachment 1, Overtime Deviation Request.

a.

The supervisor shall sign the Overtime Deviation Request form. The signature attests that the supervisor has verified:

0 No one! will work greater than 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months , exclusive of turnover time, in a 7-day period.

0 Personlnel will be periodically monitored to assess their fitness for duty, and to take action as appropriate, to ensure worker fatigue does nlDt jeopardize nuclear or personnel safety.

b.

Except for unu sua1 and unanticipated circumstances, overtime should be planned in advance. Blanket overtime deviations will not be approved.

[NO0011

2., Overtime Deviation Request shall be forwarded to the applicable Department Manager or Director for review and concurrence.

3., Overtime Deviation Request shall be approved in advance of exceeding limits by the Plant General Manager or higher level of management.

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01700 5.2 (Continued)

4.

Completed Attachment 1's shall be forwarded to the Administrative Assistant to the Plant General Maiiager.

5.3 Review of Overtime Worked / Independent Review A.

The Director of Human Resources (HR) shall ensure that overtime is reviewed on a monthly basis. The scope of monthly review shall include personnel identified in Section 1.2.B of this procedure to assure excessive hours have not been worked. It will be documented in a monthly report and supplied to the Plant General Manager.

B.

If the review determines that excessive hours of overtime have been assigned then a Condition Report shall be initiated.

6.0 BASES

[NO011

[NO021

[NO031

[NO041 NCTS 503524-10, NMPC will review all department's methods of overtime control and tracking.

DER (2-95-31 90 Provide definition for 7-day period.

DER C-91-Q-0464 Ensure overtime controls are applicable to personnel who perform s'afety-related functions (including contractors) as expressed in NRC Inf'ormation Notice 91-36.

DER NM-2001-1737 Apparent reliance on the excessive use of overtime deviations to cclmplete RF016.

7.0 RECORDS Completed Attachment 1 's, Overtime Deviation Request, shall be retained by the Administrative Assistant to the Plant General Manager for one year and then may be discarded.

Completed monthly independent Over time Report shall be maintained by the Hum an Resources Department for one year and then may be discarded.

LAST PAGE

CONTROL OF WORKING HOURS Name of Personnel (List Names Individlually) 1 GAP-FFD-02 Revision 01 700 TYPE OF TIME PERIOD OF DEVIATION OVERTIME DEV. (1-5) FROM (DATERIME) To (DATERIME)

~~

Page 1 of 1 Attachment I,O\\fERTIME DEVIATION REQUEST OVERTIME DEVIATION REQUEST I

6. Method to monitor employee physicallmental fitness Supervisor (Print/Signature)*

IDate Manager (PrintlSignature)

[Date Note: Ensure deviation is approved by the Plant General Manager before scheduling overtime.

Upon signing, the Supervisor has verified :1) that no one will work greater than 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months , exclusive of turnover time, in a 7-day period. AND 2) that personnel will be periodically monitored to assess their fitness for duty, and to take action as appropriate, to ensure worker fatigue does not jeopardize nuclear or personnel safety.

PART 3 -Additional Actions Plant General Manager Approval

/Date Approved Overtime Deviation request forms to be retained in the Plant General Manager's Office in accordance with NIP-RMG-01.

NRC: JPM RO EC Constellation Energy Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Task Number: N/A Perform Daily Thermal Limit Surveillance Revision: NRC 2008 Date gLyk@d'- N/A - Exam Security General Supervisor Operations Training (Designee)

Operations (Designee)

N/A - Exam Securitv Configuration Control Date Performer:

(RO)

Trainer/Evaluator :

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time:

20 minutes Tinie Critical Task:

No Alternate Path Task:

No Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature:

Date:

NRC 2008 RO ADMIN JPM EC October 2008

Recommended Start Location: Classroom Simulator Set-up: N/A Directions to the Instructor/Evaluator:

1. Must have 3D Monicore cases from two conseculive days. The cases must be for four loop operation, with

2. Must have N1-RESP-1 completed up to section 9.2.

the MAF'RAT correction factor incorrectly set to 1.000.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasdFail.

2. During Evaluated JPM:

0 3. During Training JPM:

0 0

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. N1-ESP-1

2. N1-OP-16, Att.4 3. 3D Monicore Cases Tools and Equipment:

1. None NRC 2008 RO ADMIN JPM EC October 2008

Task Standard: Daily thermal limit surveillance completed in accordance with N1-RESP-1, section 9.2, with all discrepancies identified.

Initial Conditions:

1. The plant is operating at approximately 100% power.

2. No change in power or control rod movement has occurred since the current 3D Monicore case was generated.

3. Recirc Pump 14 is secured and isolated for maintenance on the MG set.

4. The following data is provided:

Computer Point A-390 reads 349 degrees F Computer Point A-392 reads 352 degrees F LEFM Flow correction factor process computer point 5385 reads 0.99900 LEFM Flow correction factor process computer point 5386 reads 0.99070 LEFM Flow correction factor from CRC Book - West = 0.99900 LEFM Flow correction factor from CRC Book - East = 0.99070

5. Ask the Candidate if they have any questions.

Initiating cue:

(Operators name), perform the Daily Thermal Limit Surveillance in accordance with N1 -RESP-1, section 9.2.

EXAMINER NOTE: Provide copies of N1-RESP-1 and 3D monicore case edits (current and previous day). DO NOT provide N1-OP-16, Att.4 unless the procedure is requested

1. Provide repeat back of initiating cue.

Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME -

2. Obtain a copy of the reference procedure and reviewhtilize the correct section.

3. Complete N1-RESP-1, section 9.2.

Note: Refer to KEY for completed surveillance.

Cue: If asked how to proceed at step 9.2.5 with the incorrect MAPRAT correction factor, state that Reactor Engineering has corrected the MAPRAT correction factor to 0.98 and all other numbers on the 3D Monicore case have been verified correct. Direct the candidate to continue at step 9.2.5 with the values listed on the 3D Monicore case.

NRC 2008 RO ADMIN JPM EC Proper communications used for repeat back (GAP-OPS-0 1)

N1-RESP-1 and 3D Monicore casess obtained N1-RESP-1 completed per the key The following discrepancies are identified:

Step 9.2.4 - MAPRAT CORRECTION FACTOR = 1.OO on the 3D monicore case, it should = 0.98 with 4 loop operation.

Step 9.2.15 - West Feedwater temperature (Pt A-390) is < 351 degrees F. Per N1-OP-16, Att.4, the minimum required temperature is 349.9 degrees F.

Step 9.2.16 - Notifies Operations to restore feedwater temperature to within specification and inform Reactor SatAJnsat SaWnsat SaWnsat Pass/Fail Pass/Fail Passmail October 2008

TERMINATING CUE: Daily thermal limit surveillance completed in accordance with N1 -ESP-1, section 9.2, with all discrepancies identified.

RECORD STOP TIME NRC 2008 RO ADMIN P M EC October 2008

Initial Conditions:

1. The plant is operating at approximately 100% power.

2. No change in power or control rod movement has occurred since the current 3D Monicore case was generated.

3. Recirc Pump 14 is secured and isolated for maintenance on the MG set.

4. The following data is provided:

Computer Point A-390 reads 349 degrees F Computer Point A-392 reads 352 degrees F LEFM Flow correction factor process computer point J385 reads 0.99900 LEFM Flow correction factor process computer point 5386 reads 0.99070 LEFM Flow correction factor from CRC Book - West = 0.99900 LEFM Flow correction factor from CRC Book - East = 0.99070 Initiating cue:

(Operators name), perform the Daily Therrnal Limit Surveillance in accordance with Nl -RESP-1, sectim 9.2.

NRC 2008 RO ADMIN JPM EC October 2008

NIAGARA MOHAWK POWER CORPORATION N I N E M I L E P O I N l NUCLEAR STATION U N I T 1 REACTOR ENGINEERING SURVEILLANCE PROCEDURE 111 -RESP-1 RIIVISION 04 DAILY THERMAL L I M I T SURVEILLANCE A p p r o v e d by:

q-zd y&

M. A. B a l d u z z i D a t e T H I S PROCEDURK SUPERSEDES N1-REP-18 T H I S I S A FULL REVISION 1 O/07 / 9 6 E f f e c t i v e D a t e : __

TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE.

1 2. 0 REFERENC ES AND COMMITMENTS 1

3. 0 DEFINITIONS 3

4

. 0 RESPONSIBILITIES 3

5. 0 TEST EQUIPMENT. SPECIAL TOOLS. AND MATERIALS 4

6. 0 PRECAUTIONS.

4 1J. 0 LIMITATIONS AND ACTIONS.

4 8.0 PREREQUISITES.

4 9. 0 PROCEDURE.

5 9. 1 Preliminary Actions 5

9. 2 Thermal L i m i t V e r i f i c a t i o n.

5 9.3 APRM Readings V e r i f i c a t i o n.

8 9.4 This step deleted 9.5 Power t o Flow Determination a t < 25% CTP.

10a 10.0 RETURN TO NORMAL 11

'11.0 ACCEPTANCE CRITERIA.

11 12.0 RECORD REVIEW AND DISPOSITTON.

11 ATTACHMENT 1 : Thi s attachment deleted ATTACHMENT 2: POWER FLOW RATIO DE-TERMINATION.

13 Page 11 N1-RESP-1 Rev 04

2. 1. 2 2.1.3 2. 2 2. 2. 1 2. 2. 2 2.2.3 2. 2. 4 2.2.5 2. 2. 6 2. 2. 7 2.2.8 2. 3 2.3.1

'.3.2 2.3.3 2.3.4 2.3.5 (Cont Table I

istr,umentation t h a t Initiates Control Rod Withdrawal Block, APRPI Limitins Condition for Oper-ation Section 3.1.7a. Average Planar Linear Heat Generation Rate Section 3.1.7b, Linear' Heat Generation Rate (LHGR)

Section 3.1.7c, Minimm Critical Power Ratio (MCPR)

Section 3.1.7e. Partiel Loop Operation Section 3.6.2(b), Protective Instrumentation, Core Maximum Fraction of Limiting Power Density Pol i ci es, Proqrams, and Prccedures N1-REP-31, Manual Monitor N1-REP-8, Core Thermal Powehr N1-REP-18, Power Flow R a t i o N1-REP-12, APRM Gain Adjustment N1-REP-12a. APRM Gain Adjwtment During 3 Loop Operation N1-TDP-DES-001, Computer Sciftware Control N1-REP-30, 3D Monicore Date bank Changes N1-OP-16, Feedwater System Booster Pump t o Reactor Technical Information Station Nuclear Engineering Manual, Volumes l A, 1B and 2, NEDE-24810 and 3D Moni core Monitor ancl Predictor Manual NEDE-31307P-F C1 ass I I I Nine Mi 1 e Point Process Computer, Operations and Maintenance Instructions, GEK 27782D, CiE 3D Monicore System, Operation and Maintenance Instructions, GEK-97237 Core Operation Limits Report (COLR) 10CFR 50.46 Notification letter 2003-05 Draft B May 11, 2004.

(APLHGR)

Secti on 3.1.7d, Power F1 ow Re1 at.i onshi p Duri ng Operati on Page 2 N1-RESP-1 Rev 04

4.2 4.3 5.0 6. 0 7. 0 7. 1 7.2 7.3 7.4

. 5 7. 6 8.0 8.1 13.1.1 Reactor Analyst Technician 3r Reactor Operator The Reactor Analyst Technician or Reactor Operator shall Complete this procedure Shi f t Technical Advisor (STA)

The STA shall :

0 0

Verify Technical Specification compliance.

Review completed Survei 11 ance.

TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS None PRECAUTIONS None LIMITATIONS AND ACTIONS The Reactor Engi neeri ng Supervi sor (or a1 ternate) must be noti fi ed immediately whenever a procedural step cannot be completed as stated or i f any other problem dekelops during the surveillance.

For reportable problems encountered ( i.e. Thermal Limit exceeded) during the survei 11 ance, contact the SSS and the Reactor Engineering Supervisor (or alternate) immediately and upon com letion of Certain steps in Sections 51.3 and 9.4 may be marked not applicable (N/A) when APRMs do not require adjustment.

If feedwater temperature i:, less t h a n the values listed i n Table 1, while reactor power is greciter t h a n 80%. then reduce ower t o less Table 1.

Sections 9. 2 thru 9. 4 are only required t o be erformed when Core Thermal Power (CTP) is 225%.

CTP is < 25%.

T.S. 4. 1. 7. d.

If the process com uter CT!) calculatim (OD-3) i s calculating CTP from the process computer performs a normal heat balance.

surveillance. Submit a Debpiation Event Report (DE Fi >.

t h a n 80% rated power or restore temperature t o allowa g le values per Section 9.5 shal ? only be performed when This section has been added t o assure compliance w i t h APRMs, adjusting A G RMs wil I invalidate the CTP computer point until PREREQUISITES Initials P1 a n t Condi t i ons Verify no recirculation flow changes or control rod movements have occurred dui-i ng d a t a acquisition (i. e., during 30 Monitor 01-manual d a t a collection).

mtt.

Page 4 N 1 - RESP - 1 Rev 04

I n i t i a l s m:

When completing the N1-RESP-1 Surveillance, compare the previous days limiting parameters w i t h the current days parameters.

changes i n therm? 1 1 i ini t va 1 ues, thei r core location (including AXIAL), OR heat balance parameters ( i.e. Feedwater Temperature) should be brought t o the attention of the STA and/or a Reactor Engi neEr.

Significant 9. 2. 1 IF core thermal power has changed by 10 MWth or control rods have been moved since the last 3D Monicore edit, THEN obtain a new 3D case before proceeding.

t M NOTES :

1.

The 3D Monic:ore case (Periodic Log) OR Computer Point H305, C-TP 10 MIN SMOOTHED MWTH, may be used for step 9.2.2.

2.

Do NOT use C;D Monicore (Periodic Log) i f 3D Monicore is calculating Core Thermal Power based on APRMs.

51.2.2 Record POWER MWT and CORE POWER ( % ).

IBY6.3 MWth 019.9 (5 1850 MWth)

(5 1cw-9. 2. 3 Record FLOW MLBlHR and COREI FLOW (%I, Mlblhr 537.7 (5 67.5 Mlb/hr)

(5 10Olg-Page 5a KEY N1-RESP-1 Rev 04

9.2.8 9. 2. 9 U/SI 9.2.10 9.2.11

[TIS1 9.2.12 9.2.13 I n i t i a l s NOTE: corrects t o t a l core flow i n p u t t o PFR determination when recirc loops are out of service and unisolated. If Core Flow 2 90%, this correction i s not necessary because PFR will equa.1 Fraction of Rated Power ( i.e. PFR -.999 a t 99.9% rated power. )

IF reactor recirc pumps are out of service and unisolated AND Core Flow < 90% of rated. THEN perform for Power t o Flow Ratio (PFR) determination w i t h corrected total core flow.

Step is N/A.

(4 Record Power t o Flow Ratio (PFR) from 3D Monicore or.

E:

PFR will equal 1. 0 0 i f CMWT = 1850.

(and reci rc fl ow >85%)

IF operating without a backup Pressure Regulator AND Core Thermal Power i s between 45% and 90% RTP, THEN obtain adjusted MFLPD limits from Core Operating Limits Report.

Record actual CMFL.PD value AND verify t h a t value is less t h a n or equal t o adjusted MFLPD limit.

Adjusted LHGR limit.

Current va I ue Ind. Verif.

Step i s N / A.

(d)

Record Maximum Fraction o f Linear Heat Generation Rate (MFLPD) and location ( L O C I.

(< 1. 0 0 )

Location 0.923 2 3 - 3'1-S Record Full Power Adjusted Power Density Ratio (FPAPDR)

FPAPDR =

0 0 qaq

('i 1.C) nzw I F FPAPDR > 1. 0 THEN the acceptance criteria will be met if APRM's are adjusted per Section 9.3.4.b.

Step i s N/A.

(4 Paae 7 N1-RESP-1 Rev 04

In1 ti a1 s 9. 3 9. 3. 1 NOTE :

(C2) 9.3.3 APRM Readinqs V e r i f i c a t i o n Section i s N/A, CTP i s < 25%

(->

I F 3 loop operation THEN N/A remainder o f Section 9.3 and Section 9.4 and Perforrr N1-REP-12A OR N1-OP-43A (Attachment 8), APRM GAIN ADJUSTMENT DURING 3 LOOP 0PE:RATION THEN continue w i t h Secti on 1 0. 0.

Step i s N/A

(-1 Record each As Found APRPI reading.

11 12 13 14 15 16 17 18 Immediately n o t i f y the SSS i f any APRM FCTR Card does not have Curve Set #O selected OR i f the INOP STATUS LED i s not b a c k l i t GREEN (i

.e. It displays RECl o r 2linking RED).

Verify Curve Set #O i s disp1laye-j. and INOP STATUS LED indicates GREEN f o r each APRM FCTR Card.

Use a ( J ) t o indicate v e r i fi c a t i on.

14 13 -~

11 12 15 16 17 18 Determi ne requi red APRM r e t d i ngs as f o l lows :

Mark N/A the step t h a t does not apply.

Refer t o N1-OP-38C.

a.

IF:

F u l l Power AdjListed Power Density Ratio (FPAPDR) 5 1. 0 THEN:

Required APRM settings equal Core Power Core Power +2%

Core Power (-0%, +2%)

Step i s N/A b.

IF:

F u l l Power Adjuzted Power Density Riltio (FPAPDR) > 1. 0 THEN :

CORE POWER X FPAPDR Requi red APRM :,etti ngs equal (from Step 9.2.12) h

% X -

-O

( +2% )

Step i s N/A 0

Ind. V e r i f.

Page 8 N 1 - RESP-1 Rev 04

This page deleted Page 10 N 1 - RESP-1 Rev 04

1 0. 0 RETURN TO NORMAL 1 0. 1 Notify SSS and CSO t h a t procedure i s complete sss cso 11.0 11.1 11.2 11.3 11.4 12.0 ACC E PTAN C E C R ITER I A Thermal Limits i n Section 9.2 meet their acceptance cri teri a.

Satisfactory c

Unsatisfactory c

Not Applicable (CTP <25%)

APRMs readings are left w i t h i n the required setting determined i n 9. 3. 4 or per N1-REP-12 or N1-REP-12a; Satisfactory D

Unsatisfactory ci Not Appl i cab1 e (CTP <25%)

This step deleted PFR Determination a t < 25 CTP i n Section 9.5 meets ITS Acceptance Cri teri a.

Satisfactory n

Unsatisfactory n

Not Applicable (CTP 225%)

RECORD REVIEW AND DISPOSITIU Satisfactory. (Record comments if any i n Remarks Unsatisfactory.

Immediately notify Station S h i f t (Record expl a n a t Reactor Engineering Si1 ervi sor.

corrective actions i n g ernarks.)

Person Notified:

Supervisor and on and Rema r ks :

Shi f t Technical Advisor Date Reactor Engi neeri ng Superv-i sor or Designee Date Page 11 N1 -RESP-1 Rev 04

ATTACHMENT 2 POWER FLOW RATIO DETERMINATION I n i t i a1 s 1. 0 Record Indicated Reci rc F1 ows Bel ow. (Meter readi ngs may also be used i f computer points are not available.)

Cmputer P t.

Desc.

Value :Klb/Hr)

Requi rement (Note 1)

A430 Ch. 11, Loop 11

~ 1 6, 8 8 0

~16,880 A467 C h. 12, Loop 11 A434 Ch. 11, Loop 12

<16,880

<16,880 6301 C h. 12, Loop 12 A438 Ch. 11, Loop 13

~16,880

<16,880 E335 Ch. 12, Loop 13 P.442 Ch. 11, Loop 14

<16,880

~16,880 E1369 Ch. 12, Loop 14 A446 C h. 11, Loop 15

<16,880 E3403 Ch. 12, Loop 15

~16,880

<67,500 A447 C h. 12, Total Flow

<67,500 Note 1: Non-Operating loop flow should indicate approximately 200 Klb/Hr through the 2" bypass 1-ine.

2. 0

_ _ _ ~

F\\445 C h. 11, Total Flow

_ _ _ _ ~

Calculate Core Flow by sumriing the operating loop flows and using (-200 Klb/Hr) for idle loo s w i t h the 2" bypass LOWEST flow from CHANNEL l:l or CHANNEL 12 for each operating 1 oop.

open (or 0 Klb/Hr i f loop has PO bac i: flow. Record the K1 b/Hr

+

-t-

-1 l o o p 2 -3

-4 E O v 5 Klb/Hr / 1000 =

M1 b /Hr Core t low 3.0 Multiply the Core Flow of '5tep 2.0, by 100 and divide by 67.5 t o 1,btain % recirc flow Mlb/hr

100/67.5 =

Ind. Verif.

Page 13 N1-RESP-1 Rev 04

CORE PARAMETERS POWER MWT POWER MWE

'LOW MLB/HR

'PAPDR SUBC BTU/LB PR PSIa CORE MWD/sT CYCLE MWD/sT MCPR 1848.3 628.4 60.570 0.924 25.13 1039.34 23618.2 7240.0 1.659 NMP-1 CYCLE 20 3DM/P11 PERIODIC LOG AUTOMAT1 C CALC RESULTS Kef f 1.. 0032 XE WORTH %

-;!.22 XE /RATED

-.01 AVE VF 0.394 PFR 0.999 PAGE 1

SEQUENCE NO 7 20-MAY-2008 06:59 CALCULATED 20-MAY-2008 09:17 PRINTED CASE ID FMLD1080520065939 RESTART FMLD1080520064724 LPRM SHAPE - FULL CORE LOAD LINE

SUMMARY

CORE POWER 99.9%

CORE FLOW 89.7%

LOAD LINE 107.3%

CORRECTION FACTORS: MFLCPR= 1.000 MFLPD:: 1.000 MAPRAT= 1.000 OPTION: PRE ARTS 4 LOOPS ON MANUAL FLOW MCPRLIM= 1.390 MOST LIMITING LOCATION!; (NON-SYMMETRIC)

LOC MAPRLT LOC PCRAT LOC MFLCPR LOC MFLPD 0.838 25-18 0.923 23 5 0.92'1 25 5 1.004 9 4 0.813 11-22 0.914 21 5 0.904 23 5 1.002 33 5 0.809 23-20 0.905 25 5 0.90:.

9 5 1.001 43 4 0.798 13-20 0.892 9 5 0.896 23 5 1.001 7 4 9 4 7 5 0.787 9-20 0.871 11 5 0.879 11 5 0.783 23-14 0.867 13 5 0.8711 11 5 1.000 11 6 0.776 9-24 0.865 23 5 0.869 23 5 1.000 11 6 0.775 25-22 0.862 25 5 0.86'1 11 5 1.000 27 6 0.774 13-24 0.861 9 5 0.864 11 5 1.000 31 6 1.001 1.000 0.794 21-20 0.877 11 5 0.894 21 5 06 M

D 0 0 0 0 C

06 0 6 0 0 SEQ. B-1 C=MFLCPR D=MFLPD MzMAPRAT P=PCRAT *=MULTIPLE CORE AVE AXIAL 51 NOTCH REL PW LOC L

00 0.133 24 47 02 0.238 23 04 0.481 22 43 06 0.621 21 L

00 0.722 20 10 0.815 19 3 9 12 0.876 18 A

5 14 0.902 17 L

16 1.035 16 31 18 1.107 15 20 1.148 14 27 2 2 1.212 13 L

P 24 1.275 12 23 26 1.305 11 28 1.316 10 19 30 1.347 09 L

32 1.364 08 15 34 1.356 07 36 1.406 06 11 38 1.423 05 L

40 1.366 04 07 42 1.237 03 44 0.978 02 03 46 0.338 01 L

L L

L 02 06 10 14 18 22 26 30 34 38 42 46 50 CORE AVERAGE RADIAL POWER DISTRIBUTION REL PW 0.997 1.227 1.177 1.212 1.213 1.136 0.529 RING #

1 2

3 4

5 6

7 00 46 06

PAGE 2

NMP-1 CYCLE 20 INSTRUMENT READINGS/STATUS SEQUENCE NO 7 CALIBRATED LPRM READINGS 20-MAY-2008 06:59 CALCULATED 20-MAY-2008 09:17 PRINTED 4 9D 18.4 21.9 15.3 CASE ID FMLD1080520065939 C

31.8 34.1 23.9 LPRM SHAPE - FULL CORE B

38.8 38.2 26.4 A

35.1 31.0 22.1

OF TIPS REJECTED: 1 4 1D C

B A

33D C

B A

2 5D C

B A

17D C

B A

09D C

B A

18.6 25.2 51.4 57.3 51.1 56.OD 38.4 44.9 19.7 26.3 24.7 33.7 0.0 44.3 41.3 64.2 54.4 37.8 63.8 52.4 20.9 26.9 24.9 34.9 48.5 43.4 40.0 59.5 51.7 34.4 54.7P 49.1 15.6 23.8 27.0 26.3 45.0 45.7 23.4 57.6 55.0 28.3 58.6 56.7 15.6 23.9 26.0 44.6 31.7 56.9 26.8 58.0 28.4 22.6 15.3 48.8 39.2 26.7 59.2 51.0 33.0 55.6M 47.7 28.1 29.3 25.0 24.2 50.4 45.2 46.4 60.6 55.4 60.0 60.2 50.8 60.6 28.6C 25.4 24.7 46.4 44.6 47.1 51.9 53.5 58.7 46.8 47.9 54.5 30.3 25.5 21.1 0.0 42.4 40.6 63.0 53.9 53.9 63.3 46.8 0.0 27.3 21.3 49.1 38.7 59.8 50.4 53.9 47.1 FAILED SENSORS:

LPRM (

3 SIGNALS FAILED)

LPRM (

0 PANACEA REJECTED]

OTHER SENSORS (

5 TOTAL) 1233C 2817C 441744 FDWTR FLOW, #1, EAST FDWTR FLOW, #1, WEST RECIRC FLOW #5, (ALT)

RECIRC FLOW #5, (PRI)

RECIRC PUMP 5 POWER SUB RODS NONE T = TIP RUN RECOMMENDED C = MFLCPR LOCATION M = MAPRAT LOCATION D = MFLPD LOCATION P = PCRAT LOCATION

= MULTIPLE LIMIT 04 12 20 28 36 44 CORE

SUMMARY

IRE POWER 99.9%

CALC SUB FLOW 90.3%

DP MEAS PSI 13.500

-ORE FLOW 89.7%

OPER SUB FLOW

-1.5%

DP CALC PSI 16.040 LOAD LINE 107.3%

FLOW BASIS MEANS FEEDWTR FLOW MLB/HR 7.29 APRM CALIBRAT [ON 11 12 13 14 15 16 17 18 READ I NG 99.6 100.6 99.0 100.0 98.9 99.6 100.0 98.8 AGAF 1.003 0.994 1.009 0.999 1.010 1.003 0.999 1.012 APRM - %CTP

-0.3 0.6

-0.9 0.1 -1.0

-0.3 0.1

-1.2 T I P RUNS RECOMMENDED STRINGS :

NONE

CORE PARAMETERS POWER MWT POWER MWE

'LOW MLB/HR SUBC BTU/LB PR PSIa CORE MWD/sT CYCLE MWD/sT MCPR 2APDR 1848.3 624.8 60.442 0.928 25.18 1039.22 23599.7 7221.5 1.659 NMP-1 CYCLE 20 3 DM/ Pl1 PERIODIC LOG AUTOMAT1 C CALC RESULTS K e f f 1,0032 XE WORTH %

-2.22 XE/RATED 1.01 AVE VF 0,394 PFR 0.999 PAGE 1

SEQUENCE NO 5 19-MAY-2008 06:59 CALCULATED 20-MAY-2008 09:26 PRINTED CASE ID FMLD1080519065943 RESTART FMLD1080519061459 LPRM SHAPE - FULL CORE LOAD LINE

SUMMARY

CORE POWER 99.9%

89.5%

CORE FLOW LOAD LINE 107.5%

CORRECTION FACTORS: MFLCPR= 1.000 MFLPD= 1.000 MAPRAT= 1.000 OPTION: PRE ARTS 4 LOOPS ON MANUAL FLOW MCPRLIM= 1.390 MFLCPR LOC MFLPD LOC m p w r LOC PCRAT MOST LIMITING LOCATIONS (NON-SYMMETRIC) 0.838 25-18 0.927 23 5 0.920 25 5 1.021 0.817 11-22 0.918 21 5 0.907 23 5 1.020 0,814 23-20 0.899 25 5 0.898 21 5 1.017 0.803 13-20 0.883 11 5 0.892 23 5 1.016 0.800 21-20 0.873 13 5 0.885 11 5 1.015 0.784 9-20 0,870 9 5 0.881 11 4 1.015 0.783 9-24 0.869 21 5 0.878 9 5 1.014 0.781 23-14 0.866 11 5 0.863 23 5 1.011 0.779 25-22 0.863 25 5 0.861 13 5 1.010 0.771 13-24 0.861 23 5 0.856 11 5 1.009 LOC 41 4 41 4 27 4 21 5 11 4 33 5 9 5 9 4 21 4 43 4 06 M

D 0 0 0 0 C

06 0 6 P

0 0 00 46 06 SEQ. B-1 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT *=MULTIPLE CORE AVE AXIAL 51 NOTCH REL PW LOC L

00 0.133 24 47 02 0.239 23 43 06 0.623 21 L

08 0.724 20 39 10 0.819 19 12 0.882 18 3

14 0.906 17 L

16 1.038 16 31 18 1.109 15 20 1.150 14 27 22 1.215 13 L

24 1.276 12 23 26 1.305 11 28 1.314 10 19 30 1.343 09 L

32 1.355 08 15 34 1.345 07 36 1.392 06 11 38 1.415 05 L

40 1.368 04 07 42 1.245 03 44 0.984 02 03 46 0.339 01 04 0.482 22 L

L L

L 02 06 10 14 18 22 26 30 34 38 42 46 50 CORE AVERAGE RADIAL POWER DISTRIBUTION RING #

1 2

3 4

5 6

7 REL PW 0.996 1.228 1.180 1.211 IL.212 1.135 0.530

NMP-1 CYCLE 20 INSTRUMENT READINGS / STATUS CALIBRATED LPRM READINGS 4 9D C

B A

18.8 22.2 16.5 33.6 34.6 24.9 41.1 38.8 27.4 37.0 31.5 22.8 4 1D 19.2 25.2 29.2 22.7 15.5 C

37.6 45.6 48.1 39.6 26.9 B

51.7 58.1 58.3 51.8 32.9 A

50.4 56.6D 56.3M 47.6 28.2 33D 19.5 25.7 25.6 28.6 25.0 23.6 c 33.7 0.0 45.9 49.0 43.5 45.2 B 41.1 62.6 55.2 59.6 53.7 57.4 A 38.2 65.0 54.7 61.2 49.4 58.2P 25D 20.5 27.0 25.4 29.6C 25.8 27.8 C 34.8 49.2 43.1 47.4 43.5 50.6 B 40.1 57.9 51.3 50.4 54.4 59.6 A 34.9 56.3 48.9 48.3 46.2 49.6 17D 15.2 24.2 27.3 30.4 25.4 21.2 C 26.3 44.7 44.0 0.0 42.3 40.0 B 28.2 57.8 55.8 63.1 53.4 54.1 A 23.3 58.9 55.9 65.2 46.3 0. 0 09D 15.7 23.8 26.2 21.4 C

26.1 44.5 46.0 38.1 B

31.5 58.0 56.0 50.4 A

26.9 57.7 52.6 46.4 04 12 20 28 36 4 4 CORE

SUMMARY

)RE POWER 99.9%

CALC SUB FLOW

90.

CORE FLOW 89.5%

OPER SUB FLOW

-1.

E l %

LOAD LINE 107.5%

FLOW BASIS MEAS APRM CALIBRAT1:ON 11 12 13 14 PAGE 2

SEQUENCE NO 5 19-MAY-2008 06:59 CALCULATED 20-MAY-2008 09:26 PRINTED CASE ID FMLD1080519065943 LPRM SHAPE - FULL CORE FAILED SENSORS:

LPRM (

3 SIGNALS FAILED)

LPRM (

0 PANACEA REJECTED)

OTHER SENSORS (

5 TOTAL) 1233C 2817C 4417A FDWTR FLOW, #1, EAST FDWTR FLOW, #1, WEST RECIRC FLOW #5, (ALT)

RECIRC FLOW #5, (PRI)

RECIRC PUMP 5 POWER SUB RODS NONE T = TIP RUN RECOMMENDED C = MFLCPR LOCATION M = MAPRAT LOCATION D = MFLPD LOCATION P = PCRAT LOCATION

= MULTIPLE LIMIT DP MEAS PSI 13.481 DP CALC PSI 15.992 FEEDWTR FLOW MLB/HR 7.29 15 16 17 18 READ I NG 100.2 101.2 99.2 99.3 99.1 100.3 100.2 98.5 AGAF 0.997 0.987 1,007 1.006 1.008 0.996 0.997 1.014 APRM -. %CTP 0.3 1.3

-0.7 -0.6 -0.8 0.4 0.3

-1.4 TIP RUNS RECOMMENDED STRINGS :

NONE

NRC JPM RO EP Constellation Energy Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Perform Actions for a Medical Emergency with an Injured, Contaminated Person Revision: NRC 2008 Task Number: NIA Approv-NIA - Exam Securitv I

Date General Supervisor Date dperations-Training (Designee)

Operations <Designee)

NIA - Exam Security I

Configuration Control Date Performer:

-(RO)

TrainerIEvaluator :

Evaluation Method: X Perform Simulate Evaluation Location: -Plant X Sirriulator Expected Completion Time:

15 minutes Time Critical Task No Alternate Path Task:

No Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments :

Evaluators Signature :

Date:

NRC 2008 RO ADMIN JPM EP October 2008

Recommended Start Location: (Completion time based on the start location)

Simulator Simulator Set-up (if required): N/A Directions to the Instructor/Evaluator:

Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, ok'tain specific SM / CSO permission.

Directions to Operators:

Read Before Every JPM Performance:

For-the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability io perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested..

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independendpeer verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as P:ass/Fail. All steps are sequenced critical unless denoted by a

2. During Evaluated JPM:

3. During Training JPM:

( 6 9 9 0

0 0

0 Self verification shall be demonstrated.

Self verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. EPIP-EPP-04 and Attachment 1

2. NUREG 1123,2.4.39 (3.9)

Tools and Equipment:

1. None NRC 2008 RO ADMIN JPM EP October 2008

Task Standard: Complete the CSO actions for a medical emergency with an injured, contaminated person in the plant in accordance with EPIP-EPP-04.

Initial Conditions:

1. The Plant is operating at 100%.

2. You are the CSO.

3. You have just received a report that a Mechanic has passed out on Reactor Building elevation 261 near the RWCU pumps.

4. The Mechanic is bleeding from the left arm and respiration is shallow.

5. Ask the Operator for any questions.

Initiating Cues:

(Operators name), perform the required actions for the medical emergency as the CSO.

Performance Steps Standard Grade

1. Provide repeat back of initiating cue.

Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME

2. Obtain a copy of the reference procedure and reviewhtilize the correct section of the procedure.

3. Place the GAItronics in the Merge Mode.

4. Notify the Fire Brigade.

Cue:

As the Fire Brigade Leader reply that, The Fire Brigade is on the way to Reactor Building 261 and I will report on the situation as soon as I arrive on the scene.

5. Notify the SM.

Cue:

As the SM, acknowledge the Candidates report.

Cue: As the Fire Brigade Leader, report, The Mechanic is still unconscious and is potentially contaminated.

Request Radiation Protection assistance. Also request an ambulance for transport to Oswego Hospital.

NRC 2008 RO ADMIN JPM EP Proper communications used for repeat back (GAP-OPS-0 1 )

Obtains a copy of EPIP-EPP-04.

References Section 3.1 and Attachment 1.

Places the GAItronics in the MERGE mode by placing the switch on the Communications Console in the Control Room to the MERGE position.

Sounds the Station Alarm and directs the FIRE BRIGADE to report to Reactor Building elevation 261 to evaluate the situation.

SatAJnsat SatAJnsat SatAJnsat Passmail Notifies the SM of the reported situation.

Pass/Fail October 2008

Performance Steps Standard Grade

6. Contact Radiation Protection.

Cue:

As the RP Tech, acknowledge the request and state that an RP Tech is on the way.

7. Contact Oswego County 91 1 Center.

Cue:

As the 911 Center Operator, acknowledge the request and that the person for transport is contaminated.

State that an ambulance will be on the way shortly.

8. Contact Security Shift Supervisor.

Cue: As the Security Shift Supervisor, acknowledge the request.

9. Contact the Oswego Hospital.

Cue:

As the Oswego Hospital Representative, acknowledge the report of the situation and state that the REA will be setup.

Cue:

As the Fire Brigade Leader, report that the RP Tech will need to accompany the ambulance to the hospital.

10. Arrange for the RP Tech to accompany the ambulance.

Cue: As the SM, give permission for the RP Tech to accompany the ambulance.

Cue: As the RP Tech, acknowledge permission to accompany the ambulance.

Cue:

As the RP Supervisor, acknowledge report and state that you will meet the ambulance at the hospital.

Cue:

As the SM, state that you will evaluate staffing levels.

NRC 2008 RO ADMIN JPM EP Contacts Radiation Protection AND requests

<:hat they report to the scene of the medical emergency.

Contacts OSWEGO COUNTY 91 1 CENTER and requests an ambulance be sent to the

'NINE MILE POINT CONSTELLATION ENERGY SECURITY CHECKPOINT, 350 LAKE ROAD.

fm Via land telephone line at 343-1313.

m Informs the 91 1 Center that the person for transport is potentially contaminated.

Contacts the SECURITY SHIFT SUPERVISOR and requests a security force member be sent to the scene of the medical

'emergency AND informs them of the impending ambulance arrival.

Contacts the OSWEGO HOSPITAL.

Via land telephone line at 349-5522.

Informs them that ONE contaminated injured person will be transported to them.

Requests that setup the RADIATION EMERGENCY AREA (REA).

Requests permission fi-om the SM for the RP Tech to accompany the ambulance.

Informs Rp Tech at the scene that they have SM permission to accompany the ambulance.

Informs the RP Supervisor of the incident and directs them to the hospital Informs the SM that an evaluation of required staffing should be performed Pass/Fail Passmail Pass/Fail Passmail SaWnsat SaWnsat SaWnsat SaWnsat October 2008

Performance Steps Standard Grade 1 1. Request SM contact Plant General Manager.

Cue: As the SM, acknowledge the request.

incident.

Requests SM contact Plant General Manager and provide details within one hour of SatAJnsat

12. Request Security Shift Supervisor to contact Requests Security Shift Supervisor to contact Supervisor, Communications and provide details of the incident SatAJnsat Supervisor, Communications Cue: As the Security Shift Supervisor acknowledge the request.

Cue:

As the Fire Brigade Leader, inform the Candidate that the contaminated injured person has left the site and is proceeding to Oswego Hospital in the ambulance.

13. Inform the SM of the termination of the Informs the SM that the emergency is emergency.

terminated.

Cue: As the SM, acknowledge the Candidates report.

14. Announce termination of medical emergency.

SaWnsat Sounds the Station Alarm and announces that the medical emergency has been terminated.

SatAJnsat Terminating Cue:

The medical emergency has been terminated.

RECORD STOP TIME NRC 2008 RO ADMIN JPM EP October 2008

Initial Conditions :

1. The Plant is operating at 100%.

2. You are the CSO.

3. You have just received a report that a Mechanic has passed out on Reactor Building

4. The Mechanic is bleeding fiom the left arm and respiration is shallow.

elevation 261, near the RWCU pumps.

Initiating Cues:

(Operators name), perform the required actions for the medical emergency as the cs0.7 NRC 2008 RO ADMIN JPM EP October 2008

NAME:

ATTACHMENT 1: CSO MEDICAL EMERGENCY CHECKLIST DATE:

UNIT: 0 1 0 2 TIME OF NOTIFICATION LOCATION OF MEDICAL EMERGENCY ComDleted NOTE:

If making emergency announcements via GAltronics, always place in Merge mode.

1.

Notify the Fire Brigade by Gai-Tronics................................................................................................... 0 0

Sound the Station Alarm......................................................................................................................... 0 0

Attention, attention all personnel, This is (a D/jI/ an actual event), the Fire Brigade is directed to report to in response to a medical emergency.

I repeaf this is (a drill / an actual event).................................................................................................. 0 Repeat the station alarm and the announcement...................................................................................

Leave in Merge Mode until event termination.

2.

Notify the SM........................................................................................................................................... 0

3.

Take ANY of the following actions, IF requested by the Fire Brigade Leader:

A.

IF Radiation Protection assistance is required, THEN contact RP and request that they report to the scene of the medical emergency.......................................

0 0

B.

IF an ambulance andlor rescue is required (refer to attachment 4), THEN:

1.

Contact Oswego County 911 Center at 343-1313 and request an ambulance andlor rescue vehicle be sent to the Nine Mile Point Constellation Energy Security Checkpoint, 350 Lake Road.......................................

0 IZI NOTE: IF patient is contaminated OR potentially contaminated, THEN inform 91 1 Center of this.

2.

Contact Security Shift Supervisor (2404 or 2591) and request a security force member to respond to the event location AND inform them of the impending ambulance amval...............................................

0 0

3.

WHEN the Fire Brigade Leader has requested setup of the Hospital Radiation Emergency Area (REA),

OR WHEN the patient is contaminated or potentially contaminated, THEN:

a.

Contact Oswego Hospital at 349-5522.........................................................

0

b.

Inform them of the number of patients......................................................... 0 0

C.

Request setup of the REA............................................................................

0 Pa!]e 9 EPIP-EPP-04 Rev 15

ATTACHMENT 1 (Cont)

E.

F 7

NOTE: If hospital requests patient status DR extent of injuries AND this information is known, it may be given to the hospital.

IF transportation by NMP vehicle is requested, THEN request that the SM notify the injured persons supemisor to obtain the necessary vehicle and driver.........................................................................................................................................

0 If it is necessary for the RP Technician to accompany the ambulance, THEN

1.

2.

3.

4.

Request permission from the SM for the RP Technician to accompany the ambulance..................................................................................................................

Contact the RP Supervisor, inform him of the incident and direct them to the hospital.............................................................................................................

0 Inform the SM that an evaluation of required staffing should be performed Transmit that permission to the RP Technician at the incident scene........................

and, if necessary, action taken to restore staffing levels............................................

0 IF the incident requires transportation by ambulance THEN request Shift Manager contact Plant General Manager and provide details within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of incident..................

IF the incident involves a contaminated injury/illness AND requires transportation, THEN: Direct Security Shift Supervisor to contact Supervisor, Communications and provide details of the incident............................................................................................

WHEN the patient has left the site OR when the Fire Brigade Leader indicates the emergency is terminated, THEN inform the SM that the emergency is terminated...........................................................

0 WHEN notified that the emergency is twrninated, IF an announcement was made indicating a medical emergency was in progress THEN sound station alarm and announce medical emergency has been terminated............Cl 0

0 17 Page 10 EPIP-EPP-04 Rev 35

NRC JPM SRO COO1 Constellaltion Energy Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Task Number: N/A Perform Time to Boil Calculation for Reactor Coolant System Revision: NRC 2008 Approvals:

I f/dL?Mf NIA-Exam Security I

Date General Supervisor Date Ohrations Training (Designee)

Operations (Designee)

N/A - Exam Security I

Configuration Control Date TrainerEvaluator :

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time:

25 minutes Time Critical Task:

No Alternate Path Task:

No Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature:

Date:

October 2008 NRC 2008 SRO ADMIN JPM COO 1

Performance Steps Standard Grade Recommended Start Location: (Completion time based on the start location)

Classroom Simulator Set-up:

None Directions to the InstructorEvahator:

None Directions to Operators:

Read Before Everv JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as P:ass/Fail.

2. During Evaluated JPM:

0

3. During Training JPM:

0 0

Self verification shall be demonstrated.

No other verification shall be demonstrated.

References:

I. N 1 -0DP-OPS-0 108 Tools and Equipment:

1. Calculator NRC 2008 SRO ADMIN JPM COO 1 October 2008

Task Standard:

Perform a Time to Boil calculation for the Reactor Coolant System in accordance with N1-ODP-OPS-0108.

Initial Conditions:

1.

2.

3.

4.

5.

6.

7.

8.

The plant has been shutdown for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

A loss of Shutdown Cooling has occurred.

Reactor Coolant Temperature = 150°F.

Reactor Water Level = 72 inches.

RBCLC Temperature on TI-70-23C = 80°F.

One (1) Spent Fuel Pool Cooling Loop is in Service.

Reactor Engineering reports the following infortnation for burned bundles in the core:

Bundles 1X = 160

Bundles 2X = 164

Bundles 3X = 148

Bundles 4X = 60 Instructor to ask for any questions.

Initiating Cues:

(Operators name), perform a Time to Boil calculation for the Reactor Coolant System in accordance with N 1 -0DP-OPS-0 108.

EXAMINER NOTE: Provide applicant a blank copy of NI -0DP-OPS-0 108 Attachments 1 & 2 and Table 1.

EXAMINER NOTE: Refer to KEY for specifics of c:alculations.

Performance Steps Standard Grade

1.

Provide repeat back of initiating cue.

Evaluator Acknowledge repeat back providing correction $necessary.

RECORD START TIME

2.

Obtain a copy of the reference procedure and reviewhtilize the correct section of the procedure.

3.

Calculates DHPcore (Line 103 of Att. 2)

4.

Calculates DHP (Line 9 of Att. 1)

NRC 2008 SRO ADMIN JPM COO 1 Proper communications used for repeat back (GAP-OPS-0 UOperations Manual)

Sat/Unsat N1-ODP-OPS-0 108 obtained.

SaWnsat DHPcore = 38.1 192 MBTU/HR SatAJnsat Note: To account for differences in rounding, the acceptable range for this value is 38-38.2 MBTU/HR.

DHP = 38.1192 MBTU/HR Pass/Fail Note: To account for differences in rounding, the acceptable range for this value is 3 8-3 8.2 MBTU/HR.

- 3 -

October 2008

Grade Performance Stem Standard

5.

6.

7.

8.

Calculates DHRsdc (Line 58 of Att.1)

Calculates DHR (Line 64 of Att. 1)

Selects Thermal Capacity (K) for specific condition applicable (Line 74 of Att. 1)

Calculates Time to Boil = [2 12°F -

SFP/Cavity Temp] / (DHP - DHR) / K (Line 82 of Att. 1)

DHR sdc = 0 MBTU/HR

9.

Reports results DHR = 0 MBTU/HR K = 0.557 MBTU/F Time to Boil = (2 12 - 150)

(38.1 192-0)/ 0.557

=0.906 hours0.0105 days 0.252 hours 0.0015 weeks 3.44733e-4 months (or 54.36 minutes)

Note: To account for differences in rounding, the acceptable range for this value is 0.900-0.910 hours0.0105 days 0.253 hours 0.0015 weeks 3.46255e-4 months (or 54.0-54.6 minutes)

Proper communications used (GAP-OPS-0 UOperations Manual)

Terminating Cue:

Time to Boil Calculation is complete.

RECORD STOP TIME SatlUnsat Passmail Passmail Passmail SatLlnsat NRC 2008 SRO ADMIN JPM COO1 October 2008

Initial Conditions:

1. The plant has been shutdown for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. A loss of Shutdown Cooling has occumed.

3. Reactor Coolant Temperature = 150°F.

4. Reactor Water Level = 72 inches.

5. RBCLC Temperature on TI-70-23C = 80°F.

6. One (1) Spent Fuel Pool Cooling Loop is in Service.

7. Reactor Engineering reports the following information for burned bundles in the core:

Bundles 1X = 160

Bundles 2X = 164

Bundles 3X = 148

Bundles 4X = 60 Initiating Cues:

(Operators name), perform a Time to Boil calculation for the Reactor Coolant System in accordance with Nl-ODP-OPS-0 108.

NRC 2008 SRO ADMIN JPM COO 1 October 2008

Approved by:

N. F. Conicella NINE MILE: POINT NUCLEAR STATION UNIT 1 OPERATIONS A D ~ ~ I ~ I S T ~ A T I V E PROCEDURE

__I_

Nl -OD P-OPS-0108 REWSION 14 SI 1UTDOWN OPC3ATION8 PEOTECTION

TABLE OF CONTENTS SECTION PAGE 1.O

................. 1 PURPOSE,....,................._.....,................. =.........................,......,................

2.0 PRIMARY RESPONSlBlLlTlES

.....,,..,.................~..~..~..........~.~.~~......~..~.~......~~...~....

t 3.0 PROCEDURE..............,..I,..........1...........~.......,,..I,..tl..................................1...........14....I...~..~.....1......

1 Reductions in Decay Heat Removal - Time to Heat Up Calculation....l.........~...............I....

I Loss of Decay Heat Removal...,..,..................~................,.........

.......................................... 2 3.1 3.2 4.0 DEFINITIONS.,,.,...,..........,..,........~......~.~~~.~.~.....,............,.................,.,.........,.........,.........................

2

5.0 REFERENCES

AND C ~ M ~ I T ~ E ~ S I..I....................................

3 6.0 RECORDS REVIEW AND DlSPOSlTlOhl....................,~................,...................................,..............

3 A ~ A ~ H ~ E N ~

1: TIME TO BOlVTlME TO HEATUP CALCULATION FOR SFP AND/OR REACTOR CAVITY..,..,.,.

l l (. L 1.........,........................,...,.....

I................,......,.................................... 4 A ~ A C H M E ~ T 2: CALCULATION OF DECAY HIEAT PRODUCTION (CORE AND/OR SFP).................... 6 TABLE 1: DECAY HEAT PER BUNDLE AFTER SHUTDOWN.,...,..........,.....,,,.......,.

+.II.I....l..l....l...............

7 TABLE 2: SFP DECAY HEAT FROM RF019 TCl RF~20.......,.,...................~.........,....................................

8 1

Page i Nl -ODP-OPS-01 OS Rev 14

1.0 PURPOSE To provlde the necessary direction for the Nine Mils Unlt 1 Operations Department to calculate

'Time To EbiP and Time To Heat-Up to a given temperature to support Maintenance and unplanned events with decay heat removal systems.

I This guideline applies to all outages, bo* planned and forced, and to all condjfions lor Spefit Fuel Pool Coating.

2.0 PRIMARY RESPOtJSI81LiTiES 73s Operations Branch has overall responslbllity for maintaining the station in a safe condition within the license requirements and the following specific responsibitiiies:

2.1 The Manager Operations has the following r ~ s ~ n s ~ b l l ~ e s :

e Ensuring that any planned maintenance on a Decay Heat Removal System is supported by a calculation and/or mlingency plan.

2.2 The Shift Manager has tbe following rC?SpDnSibilitieS:

0 Operating the plant within the licensing Bases.

e M ~ ~ m i z ~ n g the level of shutdwr safety by carefully assessing work against time available before decay heat warms the weier above allowable procedural limits.

Ensuring the required Operation:; Oepartment contingency plans are In place.

3.0 PROCEDURE 3.1 Reductions in Decay Heat Removal - Time to Heat UD Calculation

1.

Determine the appropriate temperature iimit using the fdlowing table:

Spent Ftlel Pool - - - - - - - - l4OF (design limit)

Spent Fuel Pool - - - - - - - - 125F (operating limit)

Cavity Flooded- - - - - - - - - 14OF (design limit)

Cavity Flooded- - - - - - - 0 125F (operating limit)

Reactor Vessel - - - - - - - - - 212f: (tech spec limit for Cold Shutdown or Refueling)

Note: If fuel moves are in progress, contact Reactor Engineering to determine exact status of fuol bundle location {Le, how many Once Burnt bundles are in the SFP, etc).

Page 1 N1-ODP-OPS-0108 Rev 14

3.1 (Cont)

2.

Calculate Decay Heat Production of Reactor and I or SFP using Attachment 2.

3.

Calculate Decay Heat Removal c4 SDC and I or SFP Cooling using Attachment 1.

4.

Select the Thermal Capacity for the appropriate configuration.

5.

Calculate the time to the limit per Attachment 1.

6.

7.

If calculation assumptions changls, then a revised calculation shall be performed.

Planned Maintenance should not exceed 50% of the available time to the calculated temperature limit. If the planned maintenance exceeds 50% of the available time to temperature, then an Approved Cbntingency Plan shall be in effect to restare cooling prior ta exceeding the specified limit.

I

8.

Engineering shall be contacted via an Engineering Setvice Request (ESR) if a refined calculation is desired.

3.2 Loss of Bcav Heat Remaval 3.2.1 NI -SOP-& 1, Loss of SFPmX Cavity L e v e W y Heat Removal provides guidance to plant Operations on recovery from loss of Decay Heat Removal during shutdown conditions.

3.2.2 A Time-to-Boil I Time-@Heat Up estimal on should be performed using Attachment 1 if any of the following conditions exist:

a, The Safety Assessment Level for h a y heat removal is cN OR

b.

The temperature of the fuel pod or reactor unexpeciedly increases >lPF in any 24-hour period The temperature of the fuel pwl or reactor is projected to exceed 1 2SnF (based upon actual temperature measurements).

OR

c.

4.0 DEFINITIONS 4.1 Decay Heat Removal Capability - Ths $ability to maintain the reactor mlant system temperature and pressure and spent fuel pool temperature below specified limits following a shutdown.

I 4.2 OARS - Days after reactor shutdown Page 2 N1-ODP-OPS-0108 Rev 14

5.O 5.1 5.2 5.3 5.4 5.5 6.0 6.1

6.2 REFERENCES

AND COMMITMENTS NIP-OUT-01 Shutdown Safety.

UFSAR Chapter X Section t.l SPENT FUEL STORAGE POOL FILTERING AND COOLING SYSTEM.

Ni -0P-6, Spent Fuel Pool Cooling System S22,1-XX-C065NF, Rev. 0, NMP1 Cycle 17 and RF019 Decay Meat DCP N1-06-016, NMPl Reload 191Cycte 18 Core Design RECORDsREVlEW AND DISPOSITION The following records generated by this procedure shall be maintained by Records Management for the Permanent Plant File in accordance with NIP-RMG-01, Records Management:

None The following records generated by this powedure are not required for retention in the Permanent Plml file; Time to boil calculations LAST PAGE Page 3 N1-OOP-OPS-0108 Rev 14

ATTACHMENT 1:

TIME TO BOWTIME TO HEATUP CALCLJIATION FOR SFP AND/OR REACTOR CAVITY Dateflime General EquatiMl Time To Target Temp

= parget Temp, I: - C m t Temp, F]

[DWI'

DI IR] t K K = Heat Capacjty of SFP and/or Cam DHP Decay Meat Production DHR = Decay Heat Removal Llne I

1 Target Temp

= Final SFPICavity T m p Record Deslrsd (Target) SFPlCsVity Temp F

2 SFPtCaVity Temp = Initial SFP/Cavity Temp Record Actual Initial SFPlCaviiy Temp F -

3 DHP = Decay Heat Produc(ior, ftom an Fuef 4

DHP =

DHPcore +

DHPsfp I

I Note: use DW values eppropriata to situation s ~ 1

-tion cf Mi.

DHP wre = Decay Heat Production from Core (From Attachment 2, line 103)

MBTUIHR I DHP sfp = Decay Heat Production frcm SF 2 (From Attachanent 2, line 116)

MBTUIHR I 7

QHP =

DHP core

+

DHP sfp Note: if gates are tn, Galcutate for only one location 8

DHP =

(Ilne5)

+

(ltne6) -

9 DHP =

+

DHP =

MBTUMR 10 Calc. By 11 verified By 12 13 DHR = Dmy Heat Removal of SFPC and SDC Enter zerro(s) for complete 106s of coding.

14 DHR =

DHRsfp

+

DHWsdc DHR sfo = DWY Heat Removal of SFP coding

=Nloapssf$ X 0.226 X SFP DeltaT F

I 18 RBCLC Temp = From Panel Dndicatw TI-70-23C SFP aalta 7 =

SFP Temp - RBCLC Temp F

I 20 SFPDeItaT

( l i ~ 1 7 )

(lkml8)

I 2 1 SFPOeRaT =

F -

F SFP Delta T =

F talc. By 22 23 Venfiad By 24 N loops sfp Enter Numbsr of SFP CooIing Laops in Service

( 0,l or 2 )

Loops 25 26 27 DHRsfp = Nloopssfp X

0.228 X

SF'PDJlaT 28 DHRsfP =

(Iins24)

X 0.226 X

(8ine21)

=

29 DHRsfp =

X DHR sfp MBTURIR 0,226

&IC.

By 30 31 32 Verified By Page 4 N1-ODP-OPS-0108 Rev 14

ATTACHMENT 1 (Cont) 33 DHR sdc = Decay Heat Removal of Shutdown cooling Not to be used for SFP 34 35 31 37 38 42 43 44 45 46 47

$8 49 Lio 51 52 53 54 55 56 57 58 59 60 61 9OC Delta T =

RxTemp

- RBCLCTamp Rx Temp = SDG inlet Temp from Panel indicator TR 38-146 Iorefwfed)

RBCLC Temp = From Panei Indicator TI-70-23C SDC, neita 7 = RxTemp SRC Delta T =

(line 35)

(line 42)

SDC Delta 7 =

F -

F RBCLCTemp - -

Cab. By Venfted By N lwrps sdc SDC constant Enter Number of SDC Loops in Service Wed SM: Capability wnstanl N loops sdc SDC constan'.

0 0

1 0.1954 2

0.3909 3

0.5364 DHR sdc =

SDC constant X SDC Delta T DWRsdc =

(Iine53)

X (line45) -

DWRsdc =

X Calc. By verified By F

F:

SW: Delta T =

F

( 0.9, 2 or3)

LOOPS SDC constant =

I OHR sdc NBTUMr 82 DHR =

DHR sfp

+

DHR sdc (Use appmpriato system if gates are Instalk&)

63 DHR =

(line29)

+

(line58) 64 65 66 67 88 Thttrnial Capadty uf SFP arltl Io1 CEtvily 69 SFP ONLY gates installed K =

2,250 MBTUIF

/U SFP and Cavity gates removed K =

BOgD MBTUIF 71 Cavity oniy (gates installed) Level a1 339 K =

2.620 MBTUIF 72 Vessel only (gates instalifid) Level at Vessel Flange K =

0.681 MBTUIF 73 Vessel only (gates installed) Level at 72" K =

0,557 MBTUIF 74 Select Thermal Capactty for specific condition applicable.

K

=

MBW I F 75 76 Time To Bo# (Time to 140F)

=

[212 (490) F - SFPICwity Tamp]

DWR =

MBTUlHR DHR =

Cak. By Verifiad By 77

[DtlP - DHR] I K 78 79 80 81

= [ 212 (or 140) F -

(llne2) F]

I F

Fl

[ (line Q)

- (line &I)]

i {ilno 74) 1

- -Jip VerifiedBy Page 5 N1-ODP-OPS-OIO Rev 14

A ~ A C ~ ~ E N T 2: CALCULAYION OF DE1;AY HEAT PRODUCTION (CORE AND/OR SFP) 93 DHP caw Calculation 94 95 96 9'7 98 99 100 101 3 02 103 Obtain from Rx Eng (preferftrd) or Estimate the number $of Once, TiuiCe, 3X,at7d 4X burned bundles in the ora at this time (ii estimate is used for number of bundles, Vicsn repeat caiculalion once an accurate count Is obtained)

(Will not add up to 532 if any bund-have bean OFfloaUed

$# Bundles 1x

Bundtes W

Bundles 3X-

Bundles 4X Fmm Table 1 Record Demy Heat PIX Bundle for each type (IX, 2X, 3X & 4x1 (MBTUIHr) bassd on OARS 1X (MBTUkir) 2X (MBTUIHrI-3X (MBTUlHr)

Multiply the # Bumites of each Iype times Demy Heat par bundle for that type X

line 94 (1x1 Line 9 ( ~

(IX)

IX ~utxlic PmGr X

line 99 (2X) tine 96 (2x1 W BuMtEe POM&

line 94 (3x1 Line w (3x1 3~ ~ u n d ~ e PoGk X

x

__I_-

=

line 94 (4X) line 96 (4x) 4Xbundle pow; DIIPmre =

+

l X (Ime W) 2x (Iiw $9) -

3x (the 100) 4XfMBTU1 Hrf

+

4 x (fine 101)

DHPcore =

MBTUfHr Calc. By Vttrified By 104 DHPsfp CalculaUon 105 106 107 108 109 110 111 112 113 114 115 116 Note: The SFP Decay Heat Production is the sum of the Frashly offloaded f w d plus tho "old" fuel.

Obtain from Rx Eng or Estimate fhe number of Once, Twice, 3X and 4X bwntad bundles from w m t core thet have been offnoadad into the SfP. (if @@timate is us& for number of bundles, Won repeat c&ulatbn once arwmta count is obtained)

If Care Shuffle Is complete, Skmply look up DHPsfp i r m Table 2 and enter In Line ?I$

belaw.

In SFP (There will be 148 3X bum& a b r RFO 10 Shuffle cumplates)

I

Bundles 1X

Bundies 2X

Bundles 3- # Bundles 4X From Table 1 Record Decay Heat Per Bundle for each type (IX, 2X, 3X & 4X) (MBTUIHr) based on DARS

'IX (MBTWHr)

W (MRTUktr) 3X (MBTU/Wrr 4X{MBTUIHr)

Multiply the # Bundles of each type times Decay Weal psr bundle for that type X

line 105 (IX)

Line 107 flX)

X 1 X Bundle Pouzr (of freshly oMoaded bundles in the SFP) line 105 (W)

Llne 107 (2x1 2% Bundle Povg (of freshly offioadeU buM1es in the SFP) 3X Bundle Potgr [of freshly offloaded bundles io me SFP)

I X Bundle pwkr (of freshley offboded bundles in the SFP)

DHPfresh

4.

+

X line 105 (3X)

Line 107 {a)

X lino 105 (4X) line 107 (4x1 I x {ltne 109) 2~ (tine I 10j-3X (line 11 1) 4X (line3 12)

P OHPfresh MBTUlHr cfecay Heat for previously offloaded "old" fuel (assumml conslant) 1.41

+

MBTUlHr d.41 -

DHPsfp (line 114)

(line 1115)

DHPsfp (directly from table 2 if shuffte mrnplete).

Page 6 FJl-ODP-OPS-0108 Rev 14

TABLE 1 : DECAY HEAT PER B UNDLE AFTER S H ~ ~ O W N DARs 0.00 0.25 0.50 0 75 100 1.25 1.50 1.75 2.00 2.25 2.50 2.75 3.00 3.25 3.50 3.75 4.00 4.25 4.50 4.75 5.00 5.25 5.50 5.75 6.00 6.25 6.50 6.75 7.00 7.25 750 7.75 8.00 850 9.00 9 25 9 50 9.75 1u.w 10.50 11.00 11.50 12.00 12 50

a. 25 8.75

_I PlX 16-7251 0,1568 0.1234 0.1082 0.0996 0.4)938 0 M91 0.0851 0.0815 0.0783 0.0753

0. om 0 0701 0.0879 0.06%

0,0639 0.082t 0.0605 0.0590 0 0576 0.0563 0.0551 0.0539 0.0529 0.05 19 0.Q510 0.0502 0.0494 0.0486 0.0479 0.0472 0.0466 0.0460 0.0454 0.0449 0.0443 0.0433 0.0434 0 0429 0,0425 0.0421 0.0413 0.0405 0.0398 0.0392 0.0386 -

MSTWhr n aPer Btg PZX 12.fo52 0.2205 00952 0.0833 0.077 1 0.0727 0.069 1 0.0661 0.0874 0.0609 0.0587 0.0566 0.0547 0.0530 0.051 4 0.05oO 0.0488 0.0474 0.0462 0.0452 0.0442 0.0433 0,0424 0.041 6 0.0409 0.0402 0.0395 0.0389 0.0384 0.0378 0.0373 0.0368 0.0384 0.0359 0.0355 0.0351 0.0347 0,0344 0 0340 0.0337 0.0334 0,0322 0.0317 0.0312 0,0328 o,wr -

e Basls P3x 9.1625 0.0874 0.0691 0.0607 0.0561 0.0529 0.m3 0,0481 0.0461 0.0.444 0.0427 0.0413 0.0399 0.0307 0,0375 0.0365 0.0355 0.0346 0.0338 0.0330 0,0323 0.0316 0.m10 0.0305 0.0299 0.0294 0.0289 0.0,"85 0.0281 0,0277 0.0273 0.0270 0.0287 0.0263 0.0260 0.0258 0.0255 0.0252 0.0250 0.0247 0,0245 0,0241 0.0237 0.0233 0. m 0.0226 P4x 3.30433 0.031 9 0.0253 0.M23 0.0206 0.01 $5 0.01 85 0.01 70 0.01 64 0.01 58 0.01 53 0.01 48 0,OI 43 0.01 39 0.01 36 0.01 32 0.01 29 0.01 26 o.ot23 0,0221 0.03 18 0.01 16 0.01 14 0.01 12 0.01 10 0.0108 0.0107 0.0105 0.0104 0.0103 0.0101 0.0100 0.0099 0,0098 0.0097 0.0096 0.0095 0.01494 0.0093 0.0092 0.0091 0.0089 0.0088 0.0087 0.0085 0.01 7a TOWS M87Uhr Pinccm G314.12 59.70 47.10 41.3!5 38.13 35.9 I 34.l!i 32°C) 31.28 30.013 28.41 27.W 26.4) 26.13 E5,3!j 24.62 23.91 23.31 22.24 21.7!5 21.a) 20.63 20.913 20.1 I

'19.77 19.41 t9.14 18.83 18.5'3 18.53 18.0'3 17.86 17.6'5 17.41 17.21 17.D; 16,&3 16.71 16.5l 16.S3 16.08 15,811 15 58 15 311 15.07 2277 DARS t3.00 13.50 14.00 14 50 15.00 15.50 13.00 16.50 17,00 17.50 18.50 19.00 20 00 21 00 22.00 2300 24,OO 25.00 26.00 27.00 28.00 29.00 30.00 31.00 32.00 33.00 311.00 35.00 36.00 37.00 38,oo 38.00 40.00 41.00 42.00 43.00 44.00 45.00 96.00 47.00 48.00 49.00 50.00 55.00 60.00 I am Page 7 Plx 0.0380 0.0374 0.0369 owfib 0.m9 0.0354 0.0350 0.0345 0.0341 0.0337 0,0333 0.0329 0.0325 0.0318 0.031 1 0.0305 0.02%

0.0292 0.0286 0.0281 0.0276 0.027U 0. m 0.0261 0.0256 0.0252 0.0248 0.0244 0.0240 0.0236 0.0232 0.0229 0.m 0.0222 0.0219 0.0216 0.0213 0.0210 0.0208 0.0205 0.0203 0.0200 0.01 98 0.01%

0.0185 0.0175 -

anapere P2x 0.0303 0.0299 0.0294 0.0291 0.0287 0.0283 0.0280 0.0276 0.0273 0.@70 0.0267 00264 0.0261 0.02!%

0.0250 0.0245 0.0240 0.0235 0.0231 0 0227 0.0223 O.U,2l9 0.021 5 0.021 2 0.0208 0 0205 0.om 0.01w 0.0196 0.0183 0.0190 0.0187 0.018rj 0.0182 0.0180 0.0178 0 OW5 0.0173 0.0171 0.0189 0.0107 0.0165 0.0163 0.0162 0.01 53 0.0146 m

0.0223 0. m 0.0217 0.0214 0.021 1 0.0209 0,0206 0.0204 0.0201 0.01 99 0.01 97 0 01 95 0.01 93 0.01 89 0.01 81 0.0178 00174 0.0171 00168 O,OX&

0.0162 O.Of60 0.0157 0.0155 0.0152 0.0150 0 0148 0 0145 0.01 43 0.01 41 0.0139 0.01 30 0.01 36 0.01 34 0.01 32 0.0131 0.0129 0.0128 0.01%

0.0125 0.0123 0 0122 0.0121 0.0115 0.01 10 0.01 a5 P4x 0.0084 0.0083 0.0082 0.0081 O.Oo80 0.0079 0.0078 0.0077 0.0077 0.0076 0.0075 0 0074 0.0074 0.0072 0.0071 0.0069 0.0068 0.0067 0.00156 O.oDfi3 0,0064 0'0063 0,0062 0,0061 O.OO60 0.0059 0.KW 0.0057 O.OO!%

0.0056:

0.0055 0.0051 0.0054 0.0053 0.0052 0.0052 0.0051 0.0051 0.0050 0.0049 0.0049 0.0048 0.0048 0.0048 0.0045 0.0044 Nl-ODP-OPS-0103 Rev 14 Totals MBfWfrr Pinem 14.85 14.64 14.43 14.24 14.06 8 3.88 13.71 13.54 13.38 13.22 13.07 12.93 12.78 12.51 12.24 11.99 t 1 '75 11.53 f 1.31 11.10 10.90 10.70 10.52 10.34 10.17 10.00 4.84 9.69 9.54 9.40 9.26 9,13 9.00 8.88 8.64 8.53 8.42 8.32 8.22 8.12 8.03 793 7.85 7.44 7.09 8.76

TARLE 2: SFP DECAY HEAT FROM RFO19 TO RFO20 (Assumes 172 discharged bundles in RFOIQ)

Shutdown data 3J18107 Page 8 NI-ODP-OPS-0108 Rev 14

NRC JPM ROlSRO COO2 Constellalion Energy Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Determine Personnel Overtime Availability [AW GAP-FFD-02 Revision: NRC 2008 Task Number: N/A NIA -Exam Security I

General Supervisor Date Operations Training (Designee)

Operations (Designee)

NIA - Exam Security I

Configuration Control Date Performer:

(RO/SRO)

TrainerlEvaluator :

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time:

20/30 minutes Tim e Critical Task:

No Alternate Path Task:

No (ROISRO)

Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature:

Date:

NRC 2008 ADMIN JPM COO2 October 2008

I Recommended Start Location: Classroom Simulator Set-up: None Directions to the InstructorEvahator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identifj the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability LO perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested I Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as P:iss/Fail.

2. During Evaluated JPM:

0

3. During Training JPM:

0 0

Self verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. GAP-FFD-02 Tools and Equipment:

1. Calculator NRC 2008 ADMIN JPM COO2 October 2008

Task Standard:

Determine Personnel Availability for Overtime IAW GAP-FFD-02.

Initial Conditions:

1. The plant is shutdown.

2. In order to support critical path work required for startup, personnel overtime will be required for the night shift on October 26 from 1830-0630.

3. All the overtime hours will be spent performing (ROs) or supervising (SROs) field activities.

Initiating Cues:

1.

2.

3.

From the provided list of personnel working hours, determine who is eligible to work a complete 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of overtime beginning at 1830 on October 26 withc'ut requiring an Overtime Deviation Request IAW GAP-FFD-

02.

If an Overtime Deviation Request would be required for individual(s), state the work hour limit(s) which would be exceeded IAW GAP-FFD-02.

SROs ONLY - Complete the appropriate sections of an Overtime Deviation Request Form for all individuals who would need a deviation approved to cover the shift.

EXAMINER NOTE: FOR ROs - Provide Attaclhments A & C.

FOR SROs - Provide Attachments A, B & D, and Blank Overtime Deviation Request Form.

Performance Steps Standard Grade -

1.

Provide repeat back of initiating cue.

Proper communications used for repeat back Sat/Unsat Evaluator Acknowledge repeat back providing correction if necessary.

(GAP-OPS-0 1 /Operations Manual)

RECORD START TIME

2.

Obtain a copy of the reference procedure and reviewhtilize the correct section of the procedure.

GAP-FFD-02 obtained SatAJnsat NRC 2008 ADMIN JPM COO2 October 2008

3.

FOR ROs - Reviews work hours for Reactor Operators 1 thru 3 ROs - Determines the following:

RO #1 - Eligible Passmail RO #2 -Not Eligible - would exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 day period RO #3 - Not Eligible -would exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period FOR SROs - Reviews work hours for Reactor Operators 1 thru 3 and Senior Reactor Operators 1 and 2 SROs - Determines the above limitations plus the following SRO # 1 - Eligible SRO #2 - Not Eligible - would exceed 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

4.

FOR SROs - Completes Overtime Deviation Request Form Completes Columns 1 and 2 of Part 1 of GAP-FFD-02 Attachment 1, per attached key Passmail Completes Columns 3 and 4 of Part 1 of GAP-FFD-02 Attachment 1, per attached key S a m nsat Completes Part 2 of GAP-FFD-02 Attachment 1, per attached key Sat/Unsat TERMINATING CUE: FOR ROs, JPM Attachment C completed. FOR SROs, JPM Attachment D and GAP-FFD-02 Attachment 1 completed RECORD STOP TIME NRC 2008 ADMIN P M COO2 October 2008

ATTACHMENT A - ROS 10/19 10120 1 012 1 10122 1 0123 10124 1 0125 10126 I

1 1830-0642 (includes 12 minutes of urnover time) 1830-0642 1830-0730 1830-0542 1830-0642 1830-0706 (includes 12 (includes 60 (includes 12 (includes 12 (includes 36 minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time)

NRC 2008 ADMIN JPM COO2 10/19 10120 1 012 1 10122 10123 10124 10125 1830-0642 1830-0630 1830-0642 1830-0654 1830-0642 1830-0642 (includes 12 (includes 0 (includes 12 (includes 24 (includes 12 (includes 12 OFF minutes of minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover t me) turnover time) turnover time) turnover time) 10126 October 2008 10/19 10120 10121 10122 10/23 I

10126 10124 10125 1830-0642 (includes 12 minutes of turnover time) 1830-0630 1830-0648 1830-0642 1830-0642 1830-0742 (includes 0 (includes 18 (includes 12 (includes 12 (includes 12 minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time)

ATTACHMENT B - SROS 1011 9 (includes 12 minutes of turnover time) 1830-0642 10120 1 012 1 1012:!

10123 10124 1 0125 10126 1830-0642 1830-0735 1830-0642 1830-0720 (includes (includles (includes (includes 12 minutes OFF 65 minutes OFF 12 minutes 50 minutes OFF of turnover of turnover of turnover of turnover time) time) time) time) 10/19 10120 1 012 1 10122 1 0123 10124 10125 0630-1 830 (includes 0 minutes of turnover time) 10126 1830-0642 (includes 12 minutes of turnover time)

OFF 1830-0630 1830-0648 1830-0642 (includes 0 (includes (includes minutes of 18 minutes 12 minu,tes OFF turnover of turnover of turnover time) time) time)

NRC 2008 ADMIN JPM COO2 October 2008

I I

1 1

ATTACHMENT C - RO Answer Sheet RO #1 RO #2 RO #3 Eligible to work without an Overtime Deviation Request?

(YesNo)

If No, what work hour limit(s) would be exceeded IAW GAP-FFD-02?

NRC 2008 ADMIN JPM COO2 October 2008

ATTACHMENT D - SRO Answer Sheet Eligible to work without an Overtime Ileviation Request?

RO #1 If No, what work hour limit@)

would be exceeded IAW GAP-RO #2 RO #3 (Yes/No)

SRO #1 SRO #2 FFD-02?

NRC 2008 ADMIN JPM COO2 October 2008

Initial Conditions:

1. The plant is shutdown.

2. In order to support critical path work required for startup, personnel overtime will be

3. All the overtime hours will be spent plxforming (ROs) or supervising (SROs) field required for the night shift on October 26 from 1830-0630.

activities.

Initiating Cues:

1. From the provided list of personnel working hours, determine who is eligible to work a complete 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of overtime beginning at 1830 on October 26 without requiring an Overtime Deviation Request IAW GAP-FFD-02.

2. If an Overtime Deviation Request would be required for individual(s), state the work hour limit(s) which would be exceeded IAW GAP-FFD-02.

3. SROs ONLY - Complete the appropriate sections of an Overtime Deviation Request Form for all individuals who would need a deviation approved to cover the shift.

NRC 2008 ADMIN JPM COO2 October 2008

Nine Mile Point Nuclear Station Station Administrative Procedure GAP-FF D-02 CONTROL OF WORKING HOURS Revision 01700 50.59 Review Tech Spec.

INFORMATION USE Applicable To:

Nine Mile Point Nuclear Station, Units 1 and 2 Sponsor: Director-Licensing (NMP)

Approval Authority: Plant General Manager

CONTROL OF WORKING HOURS GAP-F F 0-02 Revision 01700 Page 2 of 10

SUMMARY

OF ALTERATIONS Revision Change Summary of Revisio'n or Change 01 7 00 Reworded Section 5.3.A Section 7: Added guidance for retention of monthly overtime reports.

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01700 Page 3 of 10 TABLIE OF CONTENTS SECTION TITLE PAGE 1. 0 2.0 3.0 4.0 5.0 6.0 7.0 I NTRO D UCT I ON...........................................................................................................................

4 1.1 Purpose........................................................................................................................ 4 1.2 Scope/Applicability:....................................................................................................... 4 REFERENCES...............................................................................................................................

4 2.1 Developmental References..........................................................................................

4 2.2 Performance References...............................................................................................

4 DEFINITIONS...............................................................................................................................

4 RESPONSIBILITIES.....................................................................................................................

5 PROCESS.....................................................................................................................................

5 5.1 Work Hour Limits...........................................................................................................

5 5.2 5.3 Review of Overtime Worked / Independent Review.....................................................

9 BASES..........................................................................................................................................

9 RECORDS....................................................................................................................................

9 Exceeding Work Hour Limits;.........................................................................................

6. OVERTIME DEVlATiON REQUEST...............................................................................

10

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01700 Page 4 of 10 1.o 1.1 1.2 2.0 2.1 2.2 3.0 INTRODU CTlON Purpose A.

To establish administrative controls necessary for the implementation of technical specification requirements on individual working hours.

To ensure Station Personnel are physically/mentally fit for duty to perform job duties during extended working hour periods.

6.

ScopelApplicabi lity:

A.

The work hour limits specified in Section 5.1.B of this procedure apply to all station and non-station personnel working at NMP.

The documentation requiremerits of Section 5.2.E apply only to personnel who perform or directly supervise those who perform safety-related functions, specially:

B.

0 Licensed senior reactor operators, reactor operators, and non-licensed Chemistry, Radiation Pr,otection, and Reactor Analyst Technicians.

Key Maintenance personnel as defined in Section 3.B.

Personnel who perform inspections, examinations, or tests on safety-related operators.

0 0

0 Structures, Systems or (Components. [NO031 REFERENCES Developmental References A.

B.

C.

Performance References None DEFINITIONS A.

7 Day Period Unit 1 Technical Specifications, Section 6.2.2, Unit Staff Unit 2 Technical Specifications, Section 5.2.2, Unit Staff Unit 2 USAR, Section 1.1.O, Position on NUREG-0737 - I.A.1.3, Shift Manning A seven calendar day rolling period beginning at 0000 hours0 days 0 hours 0 weeks 0 months on the first day and ending at 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months on the seventh day. [ NO021

CONTROL OF WORKING HOURS GAP -FF D-02 Revision 01 700 3.0 (Continued)

B.

Key Maintenance Personnel Those personnel who are respcmible for the correct performance of maintenance, repair, modification or calibration of safety-related structures, systems, and components, and those personnel who are performing or immediately supervising the performance of such activities (reference GL 83-14).

4.0 RESPONSIBILITIES The following individuals and organizaiions are assigned responsibilities within this procedure:

A.

Plant General Manager B.

ManagedDirectors C.

General Supervisors/Supervisors D.

Individuals who work in excess of the limitations stated in Section 5.1 of this procedure 5.0 PROCESS 5.1 Work Hour Limits NOTE Work hour limits are established to ensure that individuals performing activities that directly impact personnel safety and the safe and reliable operation of the plant are not overly fatigued such that their mental alertness and decision-making ability might be impaired.

A.

ManagerdDirectors shall ensure adequate shift coverage is maintained without routine heavy use of overtime. The objective shall be to have operati ng personnel work a normal 8-12 hour day, nominal 40-hour week while the facility is operating.

B.

However, when circumstances dictate working beyond scheduled working hours, the following limitations apply:

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01 700 Page 6 of 10 5.1 (Continued)

NOTE For criteria in Section 5.1.B.1 below, turnover time should NOT be included. Turnover time of greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for any individual tour of duty is not exempted from individual overtime hours.

The below periods are consecutive rolling periods and are not based on calendar work weeks.

1.

Individuals identified in Section 1.2 should not be permitted to work more than:

a.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight

b.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

c.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period

d.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period

2.

Work in excess of these! limits shall NOT be routinely authorized.

C.

There should be a break in an individuals work schedule of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a work period for which work goes beyond the limitations in Step 5.1.B.

D.

The requirements and limits specified in Steps 5.1.6 and 5.1.C apply to all hours worked if any portion of an individuals total work time is spent performing or supervising field activities.

E.

Individuals working a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift schedule, who, as a result of transition in and out of daylight savings time, will exceed the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period guideline, are authorized to deviate from the guideline for the one hour transition period. No Overtime Deviation Request is required to be completed for this deviation.

5.2 Exceeding Work Hour Limits A.

It is recognized that deviations from the Work Hour Limits may occasionally occur. The use of overtime should be limited to circumstances where essential work must be done on an accelerated schedule and, except during extended shutdown periods, should be considered on an individual basis and not for the entire staff on a shift.

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01700 Page 7 of 10 5.2 (Continued)

9.

Circumstances that may warrant deviating from the guidelines of Section 5.1 include, but are not limited to:

0 To respond to a Limitins2 Condition for Operation (LCO).

To complete a work aciivity where it is safer to complete than to secure.

To complete work affecting critical path during a shutdown.

To complete work on a problem immediately affecting nuclear or industrial safety.

0 0

Absenteeism.

0 Weather-related extension of work periods.

C.

All paid overtime should be approved by authorized supervision before the overtime is worked.

The following are the requirements applicable to personnel who do NOT perform or directly supervise those who perform safety-related functions. Refer to Section 5.2.E for additional guidance.

D.

1.

2.

3.

4.

Personnel shall track their work hours and notify their supervisors if they expect to reach the limits of Section 5.1.

Prior to exceeding any of the work hour limits in Section 5.1, personnel shall obtain verbal approval irom their Supervisor, General Supervisor, Director, or Manager. Approval shall be given only if the following conditions are met:

0 The work activity is necessary to support safe and re1 iable operation of the plant.

AND 0

Other personnel cannot reasonably be made available to perform the work activity.

Personnel shall generale a Condition Report if work hour limits were exceeded without obtaining prior approval.

Supervisors shall:

a.

b.

Ensure personnlsl are fit for duty at all times.

Make more frequent direct observations of personnel exceeding work hour limits.

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01 700 5.2 (Continued)

NOTE The following personnel are required to complete Overtime Deviation Requests :

0 Operations - Personnel below General Supervisor level (except OPS Support)

Chemistry - Supervisors and below Rad Protection - Supervisors and below Radwaste - Supervisors and below Personnel who perform inspection of safety related equipment including:

b Maintenance - Personnel below General Supervisor level 0

0 0

0

- Quality Inspection Personnel

- Inservice Inspection and Test Personnel

- Contract Inspection Personnel [NO041 E.

The following are the requirements applicable to personnel who perform or directly supervise those who perform safety-related functions.

1.

Except as allowed in Section 5.2.D, Supervisors of personnel who expect to exceed the limitations of Section 5.1 shall complete Attachment 1 Overtime Deviation Request.

a.

The supervisor shall sign the Overtime Deviation Request form. The signature attests that the supervisor has verified:

0 No one wil I work greater than 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months I exclusive of turnover time, in a 7-day period.

a Personnel will be periodically monitored to assess their fitness for duty, and to take action as appropriate, to ensure worker fatigue does not jeopardize nuclear or personnel safety.

b.

Except for unusual and unanticipated circumstances, overtime should be planned in advance. B lanket overtime deviations will not be approved.

[NO0011

2.

3.

I Overtime Deviation Request shall be for warded to the applicable Department Manager or Director for review and concurrence. Overtime Deviation Request shall be approved in advance of exceeding limits by the Plant General Manager or higher level of management.

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01700 Page 9 of 10 5.2 (Continued)

4.

Completed Attachment 1s shall be forwarded to the Administrative Assistant to the Plant General Manager.

5.3 Review of Overtime Worked / Independent Review A.

The Director of Human Resourfees (HR) shall ensure that overtime is reviewed on a monthly basis. The scope of monthly review shall include personnel identified in Section 1.2.6 of this procedure to assuie excessive hours have not been worked. It will be documented in a monthly report and supplied to the Plant General Manager.

B.

If the review determines that excessive hours of overtime have been assigned then a Condition Report shall be initialed, 6.0 BASES

[NO011 IN0021

[NO031

[NO041 NCTS 503524-10, NM PC will review all departments methods of overtime control and tracking.

DER C-95-3190 Provide definition for 7-day period.

DER C-91-(2-0464 Ensure overtime controls are applicable to personnel who perform safiety-related functions (including contractors) as expressed in NRC Information Notice 91-36.

DER NM-2001-1737 Apparent reliance on the excessive use of overtime deviations to com plete RF016.

7.0 RECORDS Completed Attachment 1 s, Overtime Cleviation Request, shall be retained by the Administrative Assistant to the Plant General Manageifor one year and then may be discarded.

Completed monthly independent Over time Report shall be maintained by the Hum an Resources Department for one year and then may be discarded.

LAST PAGE

GAP-FFD-02 Revision 01 700 Page 10 of 10 CONTROL OF WORKING HOURS WPE OF TIME PERIOD OF DEVIATION OVERTIME Name of Personnel (List Names Individually)

DEV. (1-5) FROM (DATEITIME) TO (DATEITIME)

$0 *a 4

lO/2C I430

'%7 0630

.Ro 2k 3 3

lo/26 1630

' O h 7 0630 5Ro a 2 10/26 wo 1 0 h T a630 Page 1 of 1, OVERTIME DEVIATION REQUEST OVERTIME DEVIATION REQUEST I

a I

6. Method to monitor employee physicallmental fitness h d r r -

a-dirwt dL*vh-h;rr C u r 5;rns'Ikr )

Supervisor (PrinVSignature)'

c 51'QfiCI.-

[Date - O,.&/-

Manaaer (PrinVSionature) bate Note: Ensure deviation is approved by the Plant General Manager before scheduling overtime.

'Upon signing, the Supervisor has verified :I) that no one will work greater than 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months , exclusive of turnover time, in a 7-day period. AND 2) that personnel will be periodically monitored to assess their fitness for duty, and to take action as appropriate, to ensure worker fatigue does not jeopardize nuclear or personnel safety.

PART 3 - Additional Actions 1

~

Plant General Manager Approval loate Approved Overtime Deviation request forms to be retained in the Plant General Manager's Office in accordance with NIP-RMG-01.

NRC.IPM SRO EC Constellation Energy Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Review of Surveillance Test (ST)

Revision: NRC 2008 Task Number: N/A Approvals:

Ge p4z ralsupervis r /..".l-p N/A General

- Exam Supervisor Security Operations Training (Designee)

Operations (Designee)

Date N/A - Exam Security Configuration Control Date Performer:

(SR.0)

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time:

20 minutes Time Critical Task:

No Alternate Path Task:

No Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature:

Date:

NRC 2008 ADMIN SRO JPM EC October 2008

Recommended Start Location: Classroom Simulator Set-up: None Directions to the Instructor/Evaluator:

For N 1 -ST-Q 19, enter the surveillance data using an archived record from an actual performance of the surveillance. EXCEPTION: Step 8.1.12.b, e:nter the CW Circ Pump 1 1 d/p = 21.2, and Step 8.3.2, enter the 2 10.1-0 1 CLOSE TO OPEN time = 3.O seconds.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.

Notes to Instructor / Evaluator:

1.

2.

During Evaluated JPM:

3.

During Training JPM:

Critical steps are identified as Passmail.

0 Self-verification shall be demonstrated.

0 No other verification shall be demonstrated.

References:

1. Nl-ST-Q19; Section 10.0.

3. K/A 2.2.12 (3.4).

4. WA 2.2.24 (3.8).

2. LER 2003-004.

Tools and Equipment:

1. None NRC 2008 ADMIN SRO JPM EC October 2008

Task Standard:

Complete Section 10.1, Operations Review, and identify the unsatisfactory results for N1-ST-Q19. Determine the appropriate actions in response to the unsatisfactory conditions.

Initial Conditions:

1. You are the Unit 1 Shift Manager.

2. Unit 1 is at 100% power.

3. N1-ST-Q19 has just been completed up to the Operations Review.

Initiating cue:

(Operators name), using the completed surveillance provided, complete Section 10.1, Operations Review. Record the results of your review and any required actions.

I Performance Steps 7 l a n d a r d I

Grade I

1. Provide repeat back of initiating cue.

Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME

2. Obtain a copy of the reference procedure and reviewhtilize the correct section.

3. N1-ST-019:

Completes section 10.1, Operations Review, anld references procedure sections as applicable to verify the required data. Evaluates the data.

NRC 2008 ADMIN SRO JPM EC Proper communications used for repeat back (GAP-OPS-0 1)

Copy of completed surveillance will be provided to the performer.

Transcribes surveillance data to the appropriate table in section 10.1.

Determines acceptance criteria NOT in acceptable range for CW Circ Pump 11 d/p.

Value is in the REQUIRED ACTION range.

Declares CW Circ Pump inoperable.

Informs Condition Monitoring Group (CMG).

Determines 2 10.1-01 CLOSED TO OPEN stroke time is UNSAT. Value is above the IST limit, but within the Limiting Stroke Time.

Determines 2 10.1-0 1 may be stroked a second time.

Determines pump to be entered in ESL.

Determines TS 3.4.5 entry is required; restore CW pump to operable within 7 days.

Satnrnsat SatAJnsat SatRJnsat Passmail Passmail SatAJnsat Passmail SatAJ nsat Satnrnsat Passmail October 2008

I Performance Steps I Standard I

Grade I

Determines entry into SM log required.

Satmnsat Determines yellow clearance tag required for CW pump.

Satmnsat Determines ACR and CR to be written.

Sat/Unsat Informs ISTKMG.

Sat/Unsat Informs Manager Operations.

Sat/Unsat TERMINATING CUE:

Operations Review of N1-ST-Q 19 is complete. Required actions and notifications are identified.

RECORD STOP TIME NRC 2008 ADMIN SRO JPM EC October 2008

Initial Conditions:

1. You are the Unit 1 Shift Manager.

2. Unit 1 is at 100% power.

3. N1-ST-Q19 has just been completed up to the Operations Review.

Initiating cue:

(Operators name), using the completed surveillance provided, complete Section 10.1, Operations Review. Record the results of your review and any required actions.

NRC 2008 ADMIN SRO JPM EC October 2008

Approved by:

J. Krakuszeski NINE MILE POINT NUCLEAR STATION UNIT 1 SURVEILLANCE TEST PROCEDURE N1 -ST-Q19 RE\\lSION 08 CONTROL ROOM HVAC SYSTEM OPERABILITY TEST 3/2/06 Date CONTROUEO WORKING COPY VERIFIEDBY N(TT TO BE USED AFTER %WW 0° 47 4 DAJIvTuI(E Effective Date: - March 2 1 2008

Page No.

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Change No.

LIST OF EFFECTIVE PAGES Paqe No.

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Page i N 1 -S T-Q 1 9 Rev 08

TABLE OF CONTENTS 1. 0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 PURPOSE.....................................................................................................................................................

1 TECHNICAL SPECIFICATIONS....................................................................................................................

1 REFERENCES AND COMMITMENTS..........................................................................................................

1 GENERAL TEST METHODS........................................................................................................................ 2 TEST EQUIPMENT.......................................................................................................................................

5 PRECAUTIONS AND LIMITATIONS.............................................................................................................

5 PREREQUISITES.......................................................................................................................................... 7 PROCEDURE..............................................................................................................................................

11 8.1 Chilled Water Train 11 Operability Test.....................................................................................

11 8.2 Chilled Water Train 12 Operability Test.....................................................................................

16 8.3 Stroke Test of BV 210.1-01 and BV 210.1-02, Cooling Coil 11 and 12 Inlet BVs......................

21 8.4 Stroke Test of 210.1-56, Chill Watei. Supply to Control Room Coolers.....................................

22 RETURN TO NORMAL............................................................................................................................... 23 ACCEPTANCE CRITERIA.......................................................................................................................... 24 ATTACHMENT 1: TEST PERSONNEL SIGNATURE AND INITIAL LOG................................................................

31 ATTACHMENT 2: CHILLED WATER CIRCULATING PJMP SKETCH...................................................................

32 ATTACHMENT 3: CHILLED WATER CIRCULATING P JMP TEST FLOW DIAGRAM............................................

33 Page ii N 1 -ST-Q19 Rev 08

1.o 1.I (UFSAR) 1.2 2.0 2.1 2.2 2.2.1 2.3 3.0 3.1 3.1.I 3.1.2 3.1.3 3.2 3.3 3.3.1 3.3.2 3.3.3 PURPOSE To provide instructions necessary to perforni Control Room HVAC System Valve and Pump operability testing in accordance with Plant Technical Slpecifications and the NMP Pump and Valve Inservice testing Program.

The purpose of this procedure is also to manage aging of components TECH N I CAL SPEC I FI CATIONS Surveillance Requirements Section 6.5.4, lnservice Testing Program Limiting Conditions for Operation (LCO)

Section 3.4.5.e, Control Room Air Treatment System Frequency This procedure shall be performed quarterly during all periods when the system is required for operation.

REFERENCES AND COMMITMENTS Licensee documentation NMPNS-IST-001, NMP Pump and Valve Inservice Testing Program Renewed Facility Operating License No. DPR-63, dated October 31, 2006 UFSAR, Appendix C, Section C.1.I 3 Closed-Cycle Cooling Water System Program Standards, Regulations, and Codes ASME Section XI, 1989 Edition Policies, Proqrams, and Procedures N1 -TDP-IIT-0102, Analysis and Trending of Inservice Testing Results N 1 -0P-49, Control Room Ventilation System Operating Procedure N1-ITP-01, Ultrasonic Flow Test 3.3.4 GAI-REL-06, Vibration Measurement Page 1 N1 -ST-QI 9 Rev 08

3.4 Technical Information 3.4.1 C-I 8021-C, Turbine Building HVAC Air Conditioning System for Laboratory Areas 3.4.2 C-18046-C, Air Conditioning System for the Administration Building HVAC 3.4.3 C-I 8047-C, Control Rooms Heating, Ventilating and Air Conditioning 3.4.4 Problem Report 1533 3.4.5 Problem Report 1574 3.4.6 3.4.7 I

DER 1993-0924, Difficulty in achieving IST Test results due to isolated Administration Building cooling coil.

DCR 1-93-001-LS221 Control Room Chilled Water System 3.4.8 Configuration Change 1 MOO641, Rev 1 3.5 Commitments Sequence Commitment N um ber Number Descripticn None 4.0 GENERAL TEST METHODS 4.1 Subsections 8.1, 8.2,8.3 and 8.4 may be performed in any order as necessary to facilitate Post-Maintenance Testing and to minimize shifting of plant equipment. Steps within these subsections shall be performed in the order specified.

NOTE: Failure of Operations Department to analyze Inservice Testing (IST) test data during the same shift could result in a violation of ASMEf Section XI requirements.

4.2 Subsection 8.1 CMG tests the following ccmponents:

e 210.1-37, Chilled Water Circulating Pump 11 e

70-25, RBCLC Inlet to Control Room Chiller 11 BV 0

210.1-34, Chilled Water Circulating Pump I 1 Discharge Check Valve in the forward flow direction e

210.1-35, Chilled Water Circulating Pump 12 Discharge Check Valve in the reverse flow direction Page 2 N 1-ST-Q19 Rev 08

4.3 Subsection 8.2 CMG tests the following cornponents:

rn 210.1-36, Chilled Water Circulating Pump 12 rn 70-26, RBCLC Inlet to Control Room Chiller 12 BV rn 210.1-35, Chilled Water Circulating Pump 12 Discharge Check Valve in the forward flow direction rn 210.1-34, Chilled Water Circulating Pump 11 Discharge Check Valve in the reverse flow direction 4.4 Subsection 8.3 CMG tests 210.1-01, Cooling Coil 11 Inlet BV AND 210.1-02, Cooling Coil 12 Inlet BV.

4.5 Subsection 8.4 CMG tests 210.1-56, Chilled Water Supply to Control Room Coolers BV.

(IST) 4.6 Chilled Water (CW) Circulatinq Pump Testiilg 4.6.1 Pump inlet pressures of CW Circulating Pumps 11 and 12 are read from the permanent plant pump suction gauges.

4.6.2 CW Circulating Pump differential pressures are recorded using the installed DP gauges.

4.6.3 CW Circulating Pump flow rates are taken using an ultrasonic flowmeter temporarily installed on the common pump suction header in accordance with N1-ITP-OI.

4.6.4 ASME Section XI requires gauge fluctuation to be less than k 2% of the observed reading. Hydraulic instrumentation may be dampened by using gauge snubbers or by throttling small valves in the instrument lines.

(IST) 4.7 Chilled Water Valve Testinq 4.7.1 Full exercise testing of power operated valves consists of operating the valve to the position(s) required to fulfill its safety function.

4.7.2 Cycling of valves consists of full exercising a valve from its normal position to the opposite position and returning it to its normal position again by firll exercising as indicated by observing indirect evidence that signals the change of disk position.

4.7.3 CW Circulating Pump Discharge Check Valve exercise testing in the forward flow direction consists of passing the required design flow rate through the valve.

4.7.4 CW Circulating Pump Discharge Check Valve exercising in the reverse flow direction consists of verifying the check valve disk is seated by observing the change in pump discharge pressure when the pump is stopped and the redundant pump is started.

Page 3 N1-ST-Q19 Rev 08

4.7.5 4.7.6 4.7.7 4.7.8 4.8 4.9 4.10 Full stroke times of power operated valves ;re measured during full exercise testing in the direction or directions specified in the NMPI Pump and Valve lnservice Testing Program Plan. Full stroke times are measured to within a tenth of a second for stroke time of _< 10 seconds. Full stroke time of > than 10 seconds are measured to the nearest second. Full stroke time is that time interval from the initiation of the actuating signal to the end of the actuating cycle.

Stroke Time Descriptions

a.

Limiting Stroke Time {LS} values pe'r the Inservice Pump and Valve Program Plan and ASMElANSl OMa-I988 Part I O, 4.2.1.4 are shown as "{}", such as {<30 sec}, and are the limits beyond which a valve shall be considered INOPERABLE.

b.

Acceptance Criteria for steps required for compliance with the Inservice Pump and Valve Testing Program Plan and ASMElANSl OMa-1988 Part I O, 4.2.1 -8 (IST) are shown in parenthesis, such as

(<20), and is the IST Acceptable Range. Stroke Time outside the IST Acceptable Range, and below the Technical Specification andlor Limiting Stroke Time value require Corrective Action.

rn Values shown as () are the IST Acceptable range (or Acceptance Criteria), valves outside the IST Acceptable range shall be immediately retested (only one time) or declared INOPERABLE.

IST values shown as {} are the Limiting Stroke Time Values. Valve stoke times exceeding this range are INOPERABLE, retest is not allowed.

Technical Specification values are shown as [ 1. Valve stroke times exceeding this range are INOPERABLE, retest is not allowed.

rn rn Subsection 8.4 may be performed concurrently with N1-ST-M9, Control Room Air Treatment Operability Test.

Fail Safe Testing where required, is accomplished by removing the normal source of power from the valve and observing proper valve operation to the required fail safe position. Unless otherwise specified, this function is fulfilled by cycling the valve usin13 the control switch.

Independent Verification Independent verification may be performed after the completion of Section 8.0, except those marked with an asterisk (*). Those marked with an asterisk must be performed in the order specified.

Post-Maintenance Testing This procedure may be used for Post-Main tenance testing and verification of operability for any equipment covered by this procedure. When used for this purpose, Sections 1.O through 6.0, and the applicable subsectionslsteps of sections 7.0 through '~0.0 shall be performed. All IST tests applicable to a particular component are required to be performed tci verify operability.

Use of Not Applicable (NIA) or Not Require'd (NIR) for Procedure Steps 4.10.1 NIA or NIR may be used where the procedure specifically allows for it; or, Page 4 N 1 -ST-Q19 Rev 08

4.10.2 N/A or N/R may be used to eliminate steps when only a portion of the procedure is performed, such as Post-Maintenance testing, retest to verify questionable data, or other testing to be specified in Section 7.0.

Document the reason for using N/A or NIR in Section 10.1, Remarks.

5.0 5.1 5.2 5.3 5.4 5.5 6.0 6.1 6.2 6.3 6.4 6.5 6.6 6.7 6.8 TEST EQUIPMENT Vibration Detector and Vibration Detector Transducers with a required accuracy of k 5%.

Calibrated stopwatch capable of measuring one tenth of a second.

Ultrasonic Flowmeter with a required accuracy off 2%.

0-30 psid DP cell with a required accuracy of k 2%.

Acceptance Criteria Instrumentation Instrument ID Instrument Name Location PI-21 0.1 -38R Pressure Indicator El. 300 S-E PI-210.1-39R Pressure Indicator El. 300 S-E PI-210.1-40R Pressure Indicator El. 300 S-E PI-210.1-41R Pressure indicator El. 300 S-E PRECAUTIONS AND LIMITATIONS Applicable Radiological precautions shall tie observed, Radiation Protection shall be contacted for guidance, as required.

All ALARA practices shall be observed to minimize personnel exposure and spread of contamination.

Failure to notify the Shift Manager (SM) itmmediately whenever a procedural step cannot be completed as stated, or if any other problem develops during the test may result in invalidating the test results.

The SM shall be notified immediately if the test results exceed the Acceptance Criteria.

Failure to use calibrated test equipment oi'the specified accuracy may result in invalidating test data obtained.

Operation of hand held radios in the vicini,ty of vibration monitoring equipment may adversely affect vibration recordings.

Failure to shift Chilled Water Circulating Pumps in the correct sequence may cause the running Chiller to trip on low chilled water flow and result in a loss of Control Room air conditioning.

Total Chill Water System flow should not exceed 200 gpm prior to and after IST testing.

Page 5 N I-ST-Q19 Rev 08

6.9 Cycling the Control Room Chill Water System Chillers, Chill Water Pumps or TCV may require entry into the LCO for the Control Room Air Treatmenl System (Tech Spec. 3.4.5). (See N1-OP-49 for T.S.

requirements associated with redundant equipment.)

6.10 Failure to wait 10 to 15 minutes following a shutdown to allow the motor windings to cool before restarting a compressor will induce a higher current inrush and potentially exceed the breaker limits resulting in a trip.

Page 6 N I

-ST-QI 9 Rev 08

Initials 7.0 PREREQUISITES 7.1 Specify the reason for test performance.

(3 Routine Surveillance, including IST

(-)

Post-Maintenance Testing, WO Number

(-)

Inoperable Component

(-)

Other (specify) 7.2 Notify Condition Monitoring Group (CMG) Department prior to the start of the test that assistance will be required to install Flowmeter.

Person Notified Date Time Dave gnnw

/Tdy

/ 06%

7.3 Personnel responsible for the performance of this test have read and thoroughly understand its content prior to test commencement.

7.4 Verify permanent plant instrumentation is calibrated.

Instrument ID Instrument Name Number Calibration Due Date Pressure PI 210.1-38R la/%

1 0 %

Pressure PI 210.1-39R JZ 13 I 1 0 4 Pressure PI 210.1-40R P /a 1/64 Pressure PI 210.1-41R 13/71 /OB Temperature TI 210.1-13 i d 3 I 109 Page 7 N 1 -ST-Q19 Rev 08

Initials 7.5 CMG Verify portable test instrumentation is calibrated.

Instrument ID/

Calibration Instrument Name Ranqe Used Serial N u r m Due Date Vibration NIA 667'1

/2/31/68 Detector Flowmeter NIA I \\ a?!;

I d 3 1 / O q I \\ 37.6 ta/ai/ou Flowmeter NIA CMG CMG 7.6 Perform the following:

PLANT IMPACT:

1. DURING PERFORMANCE OF SUBSECTIONS 8.1 AND 8.2 ONE CONTROL ROOM CHILLER WILL BE TAKEN OUT OF SERVICE.

2. DURING PERFORMANCE OF SUBSECTIONS 8.1 AND 8,2 A TEMPORARY DIP CELL WILL BE INSTALLED AT THE PUM'P SUCTION AND DISCHARGE PRESSURE GAUGE TEST TAPS.

3. TECH. SPEC, L.C.O. PER3.4.5APPLY.

a.

Discuss the Plant Impact with the $;M, Obtain SM permission to perform procedure and acknowledgement that temporary alterations are to be used.

b.

Notify the CRO that procedure is to be performed and that temporary alterations are used. Discuss the Plant Impact.

7.7 CMG verify vibration point Red Dots installed on 210.1-37, Chilled Water Circulating Pump 1 1 AND 21 0.1-36, Chilled Water Circulating Pump 12, as indicated on, Chilled Water Circulating Pump Sketch. Document vibration point Red Dots re-established in Section 10.2, Remarks.

7.8 CMG install Temporary Ultrasonic Flowme,:er on Common Chilled Water Circulating Pump Suction Line as shown on Attachmeit 3 in accordance with N1-ITP-01.

s A SM DS CMG Pg CMG Page 8 N 1 -ST-Q 1 9 Rev 08

7.9 7.9.1 7.9.2 7.9.3 7.9.4 7.9.5 7.10 7.1 1 Establish NO flow condition to allow CMG tci Zero portable ultrasonic Flowmeter as follows:

(-)

NIA, Establishing of a NO flow condition is not required to zero Flowmeter.

NOTE: Securing the Control Room Ventilation System Chillers and Chilled water pump renders the Control Room Ventilation System Inoperable per T.S. 3.4.5.

Notify the SM to Log entry into appropriate K O for Plant condition.

Place in OFF position, 11 1 CHILLER COMPRESSOR 112 OFFIAUTOlRUN Switch.

Place in OFF position, 121 CHILLER COMPRESSOR 122 OFFlAUTOlRUN Switch, Confirm off, red RUN lights for Compressor:; 111,112, 121,122.

Depress STOP Pushbutton, for running CH~LLED WATER CIRCULATING PUMP 1 l(12) AND confirm green indicator light lit.

CMG zero ultrasonic flowmeters.

Restore from NO flow condition as follows:

(-)

NIA, Establishing of a NO flow condition was not required to zero Flowmeter.

NOTES:

1.

2.

Section 8.1 starting configuration is 12 CW Circulating Pump and Control Room Chiller Operating.

Section 8.2 starting configuration is 11 CW Circulating Pump and Control Room Chiller Operating.

7.1 1.I Restore Chill Water Circulating Pumps and Chillers as follows:

a.

Depress START pushbutton for Chilled Water Circulating Pump 12 (1 1)........... (&

CAUTION Failure to wait I O to 15 minutes following a shutdown to allow the motor windings to cool before restarting a compressor will indiJce a higher current inrush and potentially exceed the breaker limits resulting in a trip.

b.

Place 11 1 Chiller Compressor 112 Control Switch to RUN Place 121 Chiller Compressor 122 Control Switch to RUN (8

(XI

c.

d.

Depress Chiller

e.

Depress Chiller 1 START pushbuiton (29 2 START pushbu tton............................................................

Initials 7-6 T t I-#

CMG Page 9 N1-ST-Ql9 Rev 08

7.12 7.13 7.14 7.15 Repeat Steps 7.9.2 through 7.1 1.1.1 as required UNTIL ultrasonic Flowmeters are zeroed.

Notify SM to exit Control Room Ventilation !System LCO

(-)

N/A, Establishing of a NO flow conditicln was not required to zero Flowmeter The Control Room Ventilation System is in iormal configuration in accordance with N1-OP-49, any exceptions have been noted and evaluated by the SM and determined to have no impact on the performance of this test.

Record start time and date.

07wJ

[ I o L

---+

Start time Date Initials CMG D$

T#

T A SM

-!-#I Page 10 N 1 -ST-Q 1 9 Rev 08

Initials 8.0 PROCEDURE NOTES:

1.

The letters IST in parenthesis (IST) will denote steps required for compliance with ASME Section XI as delineated in the NMPI Pump and Valve Inservice Testing Program Plan. If Specific Acceptance Criteria is required, the acceptable value will be given in parenthesis for example (30 sec).

Failure of Operaticms Department to analyze Inservice Testing (IST) test data during the same shift could result in a violation of ASME Section XI requirements.

2.

8.1 Chilled Water Train 11 Operability Test 8.1.I Verify the following:

Tlk

a.

210.1-36, CW Circulating Pump 12, running. If required depress Chilled Water Circulating Pump 12 START pushbutton.

nt.

b.

210.1-37, CW Circulating Pump 11, off. If required depress Chilled Water Circulating Pump 11 STOP pushbutton.

8.1.2 CMG Install Temporary DP cell to test taps on PI 210.1-38R and PI 210.1-40R1 CW Circulating Pump # I 1 Pump Suction and Gischarge Pressure Gauges, as indicated on.

08 CMG 7-4 Concurrent Verif.

(IST)

(UFSAR) 8.1.3 Record PI 210.1-38R, CW Circulating Purrp 11 Inlet Pressure.

PI 210.1-38R:

1 a psig (2 2.27 psig)

T L

NOTE: Steps 8.1.4 through 8.1.5 perform reverse flow full exercise test of 210.1-35, CW Circulating Pump 12 Discharge Check Valve.

8.1.4 Perform the following:

a.

Depress START pushbutton for Chilled Water Circulating Pump 11.

b.

Depress STOP pushbutton for Chilled Water Circulating Pump 12.

Page I 1 N1 -ST-QI 9 Rev 08

Initials 8.1.4 (Cont)

c.

WHEN 210.1-36, CW Circulating Pump 12, stops, THEN immediately record the following:

(1S-r)

1.

PI 210.1-40R, CW Circulating Pump 11 Discharge Pressure.

(U FSAR)

PI 210.1-40R 3

.psig (1S-r)

2.

PI 210.1-41R, CW Circulating Pump 12 Discharge Pressure.

(U F S AR)

PI 210.1-41R 11.5

-psig NOTE: CW Circulating Pump 11 (running) discharge pressure in Step 8.1.4c.l should be significantly greater than CW Circulating Pump 12 (idle) discharge pressure in Step 8.1.4c.2 to verify little or no back leakage through 210.1-35.

(ET) 8.1.5 Determine if back leakage exists through 210.1-35, CW Circulating Pump 12 Discharge Check Valve as follows:

0 IF pressure recorded in 8.1.4:.1 is significantly higher than pressure recorded in Step 8.1.4c.2, T t EN record SAT below (little or no back leakage exists).

IF pressure recorded in 8.1.4c.l is recorded in Step 8.1.4c.2, TtIEN record UNSAT below (excessive back leakage exists).

0 significantly higher than pressure (B

SAT (LITTLE OR NO BACK LEAKAGE)

(-)

UNSAT 8.1.6 Notify SM to enter appropriate LCO per T.S. 3.45 for loss of redundant equipment (N 1 -0P-49).

8.1.7 Place CHILLED WATER CIRC. PUMP 12 circuit breaker at Power Board 1671 to OFF position.

8.1.8 Manually close 210.1-35, CW Circulating Pump 12 Discharge Check Valve.

5D Concurrent Verif.

Page 12 N 1 -ST-Q19 Rev 08

Initials NOTES:

1.

The Control Room Chilled Water System has been flow balanced ts a system flow rate of 200 gpm using 21 0.1 -60, Lab Air Cooling Coil Chilled Water Outlet Valve.

When throttling flow rate in the following step, attempt to establish the exact reference value given. If the exact value cannot be achieved, throttle flow rate as close as practical within the allowable range provided in parenthesis.

2.

CAUTION Total Chill Water System flow should not exceed ZOO gpm prior to IST testing.

8.1.9 Unlock and Throttle 210.1-60, Lab Area Cc'oling Coil Chill Water Outlet Block Valve, as required to establish a flow rate of 161.6 (1 58.36 to 164.83) gpm as indicated by on ultrasonic flowmeter installed on 21 0.1-37 suction line.

7 NOTE: ASME Section XI requires the system to be run for at least 2 minutes under as stable conditions as the system permits prior to taking IST pump data.

The system shall be considered slable when little or no fluctuation in pump discharge pressure exists.

(,.

I 8.1.10 Verify 210.1-37 Control Room Chilled Water Pump flow rate is stable as demonstrated by little or no fluctuation in pump discharge pressure for 2 5 minutes using calibrated stopwatch.

NOTES:

1.

Flow rates should be obtained by averaging the total gallons of the ultra-sonic f owmeter totalizer for a minimum of 5 minutes. If Systern conditions prevent 5 minute averaging, flow averaging may be performed for shorter periods.

210.1-34, CW Circulating Pump 11 Discharge Check Valve, full exercise in the forward direction is verified when pump flow rate is 2158.33 gpm.

nt

2.

(ET)

(U FSAR) 8.1.11 Determine 210.1-37 Control Room Chilled Water Pump flow rate as follows:

Total Gallons 17-3 9

+ Collecticln Time 5

minutes Flow rate I 6 3. 47 (21 58.36 gpm) gprn (158.36 to 165 gpm)

SD Ind. Verif.

Page 13 N 1 -ST-Q19 Rev 08

I Initials 8.1.I2 Record the following:

\\,

(Up SAR)

a.

PI 210.1-38R, CW Circulating Pump 11 Inlet Pressure gauge.

PI 210.1-38R:

-5 psig (2 2.27 psig)

(IST)

b.

Temporary DIP Cell, CW Circulatirig Pump 11 DIP.

(UFSAR)

(IST) 8.1.13 8.1.14 8.1.15 CW Circulating Pump I I DIP:

3 1. a psid (17,190 to 21.010 pid)

CMG perform 210.1-37, CW Circulating Pump Number 11 vibration monitoring (refer to ) AND record unfiltered peak velocity (inlsec) vibration data below:

0 Point 1H: 0*05534 inlsec (I 0.153 inlsec)

(Horizontal)

Point 1V: O.o3C,6Y inlsec (5 0.065 inlsec)

(Vertical)

Point 2H: O.Oa%S7 inlsec (5 0,093 inlsec)

(Horizontal) 0 Point 2V: 0.03319 inlsec (5 0.105 inlsec)

(Vertical)

CMG record 210.1-37, CW Circulating Purnp Number 11, speed in rpm.

210.1-37 SPEED: 17 69 rpm Using ultra-sonic flowmeter, throttle 210.1-60 as necessary to restore system flow rate to approximately 190 gpm (I 200 gpm) AND record flow rate.

CWFLOW:

180 gpm (I 200 gpm)

Pu3 CMG 08 CMG D&

CMG

-rid -

S D Concurrent Verif.

Page 14 N 1 -ST-Q19 Rev 08

8.1.16 Lock 210.1-60 8.1.17 Open 210.1-35 8.1.I8 Place CHILLED WATER CIRC. PUMP 12 circuit breaker at Power Board 1671 in ON position.

8.1.I9 Notify SM that LCO may be exited for loss of redundant component.

8.1.20 Notify the SM to enter the applicable LCO lor one Control Room Chiller out of service.

8.1.21 Perform the following to record stroke time for 70-25:

a.

Verify 210.1-120, Control Room Chiller 12, running.

b.

Verify 11 1 Chiller Compressor 112 switch in OFF

c.

Depress STOP pushbutton for Chiller 11

d.

Place 11 1 Chiller Compressor 112 switch in RUN.

CAU TlON Failure to wait I O to 15 minutes following a shutdown to allow the motor windings to cool before restarting a compressor will induce a higher current inrush and potentially exceed the breaker limits resulting in a trip.

(IST) 8.1.22 Depress START pushbutton for Chiller 11 to start 210.1-1 19, Control Room Chiller 11, AND record Close to Open stroke time of 73-25, RBCLC Inlet to Control Room Chiller 11 BV.

70-25 CLOSE to OPEN STROKE TIME: 13. s 6 sec (2: 9.6 sec and I 16.1 sec)

{;:

6.5 sec and 5 19.33 sec) 8.1 2 3 Independently verify 70-25 Open, Initials

-rH 5D Ind. Verif.

Ind. Verif.

TCC Ind. Verif.

7 4 4D Page 15 N1 -ST-Q19 Rev 08

Initials -

Ti4 I

8.1.24 Notify SM that LCO for single chiller operat on may be exited.

8.1.25 CMG remove Temporary DP cell from test taps on PI 210.1-38R and PI 210.1-40R, CW Circulating Pump # I 1 Pump Suction and Discharge Pressure Gauges.

DB f3t CMG Ind. Verif.

8.1.26 Complete Section 10.1.I

, Acceptance Criteria for Chilled Water Train 11 testing.

8.2 Chilled Water Train 12 Operability Test 8.2.1 Verify the following:

TrS

a.

210.1-37, CW Circulating Pump 11, running. If required] depress START pushbutton for Chilled Water Circulating Water Pump 11.

TH

b.

210.1-36, CW Circulating Pump I;!,

off. If required] depress STOP pushbutton for Chilled Water Circulating Water Pump 12.

8.2.2 CMG install temporary DP cell to test taps Ion PI 210.1-39R and PI 210.1-41R1 CW Circulating Pump # I 2 Pump Suction and Discharge Pressure Gauges, as indicated on.

Dl3 J-#

CMG Concurrent Verif.

(IST) 8.2.3 Record PI 210.1-39R1 CW Circulating Pump 12 Inlet Pressure (UFSAR)

PI 210.1-39R: 1q-7 psig (L 2.27 psig)

Page 16 N1 -ST-Q19 Rev 08

Initials NOTE: Steps 8.2.4 through 8.2.5 perform reverse flow full exercise test of 210.1-34, CW Circulating Pump 11 Discharge Check Valve.

8.2.4 Perform the following:

a.

Depress START pushbutton for Chilled Water Circulating Pump 12.

b.

Depress STOP pushbutton for Chilled Water Circulating Pump 11

c.

WHEN 210.1-37, CW Circulating Fump 11, stops, THEN immediately record the following:

I (1S-r)

1.

PI 210.1-41R, CW Circula:ing Pump 12 Discharge Pressure (UFSAR)

PI 210.1-41R 33-5 psig

-I I

( W

2.

PI 210.1-40R, CW Circulating Pump 11 Discharge Pressure (UFSAR)

PI 210.1-40R

'5.psig NOTE: CW Circulating Pump 12 (running) discharge pressure in Step 8.2.4c.1 should be significantly greater than CW Circulating Pump 11 (idle) discharge pressure in Step 8.2.4c.2 to verify little or no back leakage through 210.1-34.

. I 8.2.5 Determine if back leakage exists through 210.1-34, CW Circulating Pump 11 Discharge Check Valve as follows:

0 IF pressure recorded in Step 8.2.4c.l is significantly higher than pressure recorded in Step 8.2.4c.2, THEN record SAT below (little or no back leakage exists).

0 IF pressure recorded in Step 8.2.4c.l is MSignificantly higher than pressure recorded in Step 8.2.4c.2, THEN record UNSAT below (excessive back leakage exists).

(&) SAT (LITTLE OR NO BASK LEAKAGE)

(-)

UNSAT

-rH I

8.2.6 Notify SM to enter appropriate LCO per T.S. 3.4 5 for loss of redundant equipment (NI-OP-49).

-t#

8.2.7 Place CHILLED WATER CIRC. PUMP 11 circuit breaker at Power Board 1671 in OFF position.

4D Concurrent Verif.

Page 17 N1 -ST-Q19 Rev 08

Initials 8.2.8 Manually close 210.1-34, CW Circulating Pump 11 Discharge Check Valve.

NOTE: The Control Room Chilled Water !System has been flow balanced to a system flow rate of 200 gpm using 210.1-l50, Lab Air Cooling Coil Chilled Water Outlet Valve.

CAUTION Total Chill Water System flow should not exceed 200 gpm prior to IST testing.

NOTE: When throttling flow rate in the following step, attempt to establish the exact reference value given. If the exact value cannot be achieved, throttle flow rate as close as practical within the allowable range provided in parenthesis.

8.2.9 Unlock and Throttle 210.1-60, Lab Area Cooling Coil Chill Water Outlet Block Valve, as required to establish a flow rate of 161 (157.78 to 164.22) gpm as indicated by on ultrasonic flowmeter installed on 210.1-36 suction line.

x NOTE: ASME Section XI requires the system to be run for at least 2 minutes under as stable conditions as the system permits prior to taking IST pump data.

The system shall be considered stable when little or no fluctuation in pump discharge pressure exists.

(IST) 8.2.10 Verify 210.1-36 Control Room Chilled Water Pump flow rate is stable as demonstrated by little or no fluctuation in pump discharge pressure for 2 5 minutes using calibrated NOTES:

1.

stopwatch.

n-Flowrates should be obtained by averaging the total gallons of the ultra-sonic floumeter totalizer for a minimum of 5 minutes.

If System conditions prevent 5 minute averaging, low averaging may bct performed for shorter periods.

210.1-35, CW Circulating Pump 12 Discharge Check Valve, full exercise in the forward direction is verified when pump flow rate is 2157.78 gpm.

2.

(IST)

(U FSAR) 8.2.1 1 Determine 210.1-36 Control Room Chillecl Water Pump flow rate as follows Total Gallons 795.

+ Collection Time 5

minutes

= Flowrate 159.03 gpm (158 to 134 gpm)

Ind. Verif.

Page 18 N 1 -ST-Q19 Rev 08

Initials 8.2.12 Record the following:

a.

PI 210.1-39RI CW Circulating Pump 12 Inlet Pressure gauge.

PI 210.1-39R:

I 5 psig

( II i-SA R)

(2 2.27 psig)

(W

b.

Temporary DIP Cell, CW Circulating Pump 12 DIP.

(UFSAR)

CW Circulating Pump 12 DIP:

I 9 - 6 psid (1 7.775 to 21.725 psid)

(IST) 8.2.13 CMG perform 210.1-36, CW Circulating Pump Number 12 vibration monitoring (refer to Attachment 2) AND record unfiltered peak velocity (inlsec) vibration data below:

c Point IH: O00SS3% inlsec (I 0.145 inlsec)

(Horizontal) 0 Point 1 V : O - O ~ a ~

6 inlsec (I 0.133 inlsec)

(Vertical) 0 Point 2 H : 0 - 0 3 ~ 0 5 inlsec (I 0.118 inlsec)

(Horizontal) 0 Point 2V: 0 -03a09 inlsec (I 0.105 inlsec)

(Vertical) 8.2.14 CMG record 210.1-36, CW Circulating Punip Number 12, speed in rpm.

210.1-36 SPEED: 1765 rpm 8.2.15 Using ultra-sonic flowmeter, throttle 210.1-8?0 as necessary to restore system flow rate to approximately 190 gpm (I 200 gpm) AND record flow rate.

CWFLOW:

le3 gpm (1200 gpm)

Tct DB CMG OB CMG DB CMG OB CMG OB CMG TI!

5 9 Concurrent Jerif.

Page 19 N 1 -ST-Q19 Rev 08

8.2.1 6 Lock 21 0.1-60.

8.2.17 Open 210.1-34.

8.2.18 Place CHILLED WATER CIRC. PUMP 11 (circuit breaker at Power Board 1671 in ON position 8.2.19 Notify SM that LCO may be exited for loss of redundant equipment.

8.2.20 Notify the SM to enter the applicable LCO for one Control Room Chiller out of service.

8.2.21 Perform the following to record stroke time of 70-26:

a.

Verify 210.1-119, Control Room Chiller 21, running.

b.

Verify 121 Chiller Compressor IZ! switch in OFF

c.

Depress STOP pushbutton for Chiller 12

d.

Place 121 Chiller Compressor 122: switch in RUN.

CAUTION Failure to wait I O to 15 minutes following a shutdown to allow the motor windings to cool before restarting a compressor will induce a higher current inrush and potentially exceed the breaker limits resulting in a trip.

(IST) 8.2.22 Depress START pushbutton for Chiller 12 to start 210.1-120, Control Room Chiller 12, AND record Close to Open stroke time of ?0-26, RBCLC Inlet to Control Room Chiller 12 BV.

70-26 CLOSE to OPEN STROKE TIME: - I q. 3 9 sec (2 9.9 sec and L. 16.5 sec)

{2 6.7 sec and I 19.8 sec) 8.2.23 Independently verify 70-26 Open.

Initials 7-14 5 0 Ind. Verif.

J-++

a-Ind. Verif.

Tf.4 SD Ind. Verif.

TI+ -

't-q Page 20 N 1 -ST-Q 1 9 Rev 08

8.2.24 Notify SM that LCO for single chiller operation may be exited.

Initials I

De TH 8.2.25 CMG remove Temporary DP cell from test taps on PI 210.1-39R and PI 210.1-41R1 CW Circulating Pump #I2 Pump Suction and Discharge Pressure Gauges.

CMG 8.2.26 Complete Section 10.1.2, Acceptance Criteria for Chilled Water Train 12 testing 8.3 Stroke Test of BV 210.1-01 and BV 210.1-02, Coolinq Coil 11 and 12 Inlet BVs NOTE: Valves BV 210.1-01 and BV 210.1-02 are controlled by a common hand switch RMS 210.1-15, located on Panel N. When one valve is open the other is closed.

8.3.:

Record initial positions of 210.1-01, Cooling Coil 11 Block Valve and 210.1-02, Cooling Coil 12 Block Valve.

a.

b.

210.1-01, COOLING COIL 11 BLOCK VALVE: ope0 210.1-02, COOLING COIL 12 BLOCK VALVE: c \\ O 5 4

',T) 8.3.2 Using common control switch for 210.1-01, Cooling Coil 11 Block Valve and 210.1-02, Cooling Coil 12 Block Valve, AND calibrated stopwatch, cycle 210.1-01 and 210.1-02 as required to record Close to Open valve stroke times:

210.1-01 CLOSE to OPEN STROKE TIME: 3 0 secs (2 0.9 sec and I 2.8 sec)

{> 0.47 sec and I 3.27 sec}

secs (2 1.2 sec and I 3.7 sec)

{r 0.62 sec and I 4.32 sec) 8.3.3 Verify 210.1-01, Cooling Coil 11 Block Valve, and 210.1-02, Cooling Coil 12 Block Valve, restored to initial positions recorded in Step 8.3.1 AND record final positions below:

210.1-01, COOLING COIL 11 ElLOCK VALVE: o p ~ h 21 0.1-02 CLOSE to OPEN STROKE TIME: a -79 0

. 210.1-02, COOLING COIL 12 EILOCK VALVE: clod

Ind. Verif.

crtt 5D Ind. Verif.

7c).

5 0 Ind. Verif.

Page 21 N1 -ST-Q19 Rev 08

8.3.4 Complete Acceptance Criteria Section 10.1.3 for 210.1-01 and 210.1-02 testing.

Initials

-rR 8.4 8.4.1 Stroke Test of 210.1-56, Chill Water Supply to Control Room Coolers Notify the SM to enter the applicable LCO for Control Room Air Treatment System out of service (Tech Spec 3.4.5).

I

-t*

8.4.2 Establish communications between the TCV and Control Room.

7-R 8.4.3 Record initial position of TCV 210.1-56 (local).

10 okr,k pS;+ldh Tct 8.4.4 Hold in the close position, TCV-210.1-56 Control Switch until local indicator indicates closed.

NOTES:

1.

When 210.1-56 indicates CLOSED, the cooling coils are bypassed. When 210.1-56 indicates OPEN, the cooling coils are in use.

2.

When 210.1-56C selector switch (mounted locally at the chillers) is positioned from ON to OFF, the valve fails from the CLOSED position to the OPEN position.

{ET) 8.4.5 Place in OFF, 21O.1-56Cl selector switch fix 210.1-56, AND record 210.1-56 close to open stroke time.

210.1-56 CLOSE to OPEN: 3% SE!C (2 24.5 sec ard 540.8 sec)

(2 16.35 sec and 5 49.05 sec}

8.4.6 Place in ON, 210.1-56C1 selector switch for 210.1-56.

8.4.7 Verify TCV 210.1-56 remains full open.

8.4.8 Return TCV 210.1-56 to initial position recorded above.

8.4.9 Notify the SM that LCO may be exited.

8.4.10 Complete Acceptance Criteria Section 10.1.4 for 210.1-56 testing.

TJt 5D t C I.

-J-u Ind. Verif.

TCC I Page 22 N 1 -ST-Q19 Rev 08

Initials 9.0 RETURN TO NORMAL 9.1 CMG remove temporary ultrasonic flowmeter installed on common Chilled Water Circulating Pump Suction Line.

9.2 Notify the SM and CRO that the procedure is completed, and temporary alteration(s) used have been returned to normal.

9.3 Verify all test personnel performing this procedure have initialed and signed, Test Personnel and Initial Log.

9.4 Verify that all independent verification steps have been completed.

9.5 Record stop time and date.

Stop time Page 23 DB CMG T H 7 - H

-rv N1 -ST-Q19 Rev 08

COMPONENT 21 0.1 -34 21 0.1-35 70-25 If any stroke time exceeds the IST stroke timelacceptance limit ( ) and is within the Limiting Stroke Time {LS}, the valvc? may be stroked a second time per section 4.7.6. If after a second stroke, the time ex1:eeds the IST stroke timelacceptance limit ( ), then declare the valve INOPERABLE, Initiate a CR and notify IST for any valve, which required a second stroke.

TEST STROKE ACCEPTANCE TEST DIRECTION TllWE CRITERIA**

RESULTS

( ) UNSAT NIA OR NO

(-)

UNSAT sec (2

9.6 sec and s 16.1 sec)

(-1 SAT FORWARD NIA

(-1 SAT 2 158.36 gpm (8.1.1 1)

LITTLE L)

SAT REVERSE (8.1 -5)

CLOSED TO OPEN *

(8.1.22)

(2 6.5 sec and I 19.33 sec)

(-1 UNSAT BACK LEAKAGE Page 24 N 1 -ST-Q19 Rev 08

10.1.I (Cont)

MEASURED ACCEPT VALUE RANGE 4 8.1.3 2 2.27

b.

CW CircLding Pump 1 ALERT RANGE NIA (UFSAR)

(U FSAR)

(UFSAR)

(8.1.12a)

(8.1.12b)

(8.1.I

1)

(8.1.13)

TEST PARAMETER Initial Inlet Pressure (psig)

Running Inlet Pressure (psig)

DIP

( P W Pump Flowrate (gpm)

Vibration Point 1H Vi bration Point 1V Vibration Point 2H Vibration Point 2V 2 2.27 NIA HIGH 2 17.190 to NIA NIA to NIA I

21.010 -

LOW 2 158.36 5165 I0.153 to

> 0.153 5 0.366 0.065 50.065 to Test Resiilts r1.13: 1

'0'093 1 ;&:

I 0.105 8.1.I3 I

0.252 REQUIRED ACTION RANGE 2.27

< 2.27 HIGH

> 21.010 LOW c 17.190 NIA

> 0.366

> 0.156

> 0.222

> 0.252 RESULTS ACC or AL*

or RIA**

ACC

(-1 RIA**

Pump test results which fall into the Alert Range (AL) requires that the test frequency be doubled until the cause is determined and condition corrected. Subsequently inform the Condition Monitoring Group (CMG) of the pump condition. Alert Range test results are considered satisfactory for continued operation.

Pump test results which fall into the Required Action Range (RIA) shall be the basis for declaring the pump immediately inoperable. Contact the Condition Monitoring Group (CMG) of the inoperable pump.

Page 25 N 1 -ST-Q19 Rev 08

I 10.1.2 Chilled Water Train NIA FORWARD (8.2.1 1)

REVERSE (8.2.5) 21 0.1 -35 NlA 21 0.1-34 sec CLOSED TO OPEN * --

(8.2.22) 70-26 I

1 ACCEPTANCE TEST CRITERIA **

RESULTS 2 158.00 gpm

(-)

UNSAT

(-1 SAT

(-1 SAT LITTLE OR NO BACK LEAKAGE (2 9.9 sec and 5 16.5 sec)

(2 6.7 sec and 5 19.8 sec}

(-)

UNSAT

(-)

SAT

(-)

UNSAT 2 test results meet IST acceptance criteria as follows:

a.

Train 12 Valve Test Results Acceptance Valve exercising in the direction indicated verifies acceptable Fail-safe Testing.

If any stroke time exceeds the IST stroke timelacceptance limit ( ) and is within the Limiting Stroke Time {LS}, the valve may be stroked a second time per section 4.7.6. If after a second stroke, the time exceeds the IST stroke timelacceptance limit ( ), then declare the valve INOPERABLE. Initiate a CR and notify IST for any valve, which required a second stroke.

Page 26 N1 -ST-Q19 Rev 08

10.1.2 (Cont)

ACCEPT RANGE

b.

( U F SA R)

(U FSAR)

(UFSAR)

RESULTS REQUIRED ACC or ALERT ACTION AL*

RANGE RANGE or RIA**

CW Circulating Pump 12 Test ResiJlts TEST PARAMETER Initial Inlet Pressure (psig)

Running Inlet Pressure (psig)

D/P

( P W MEASURED VALUE (8.2.3)

(8.2.1 2a)

I Flowrate (gpm)

Vi bration Point 1H Vi bration Point 1V Vi bration Point 2H Vi bration Point 2V (8.2.12b)

Pump (8.2.1 1)

(8.2.13)

(8.2.1 3)

(8.2.13)

I I

I Pump test results which fall into the Alert Range (AL) requires that the test frequency be doubled until the cause is determined and condition corrected. Subsequently inform the Condition Monitoring Group (CMG) of the pump condition. Alert Range test results are considered satisfactory for continued operation.

Pump test results which fall into the Required Action Range (RIA) shall be the basis for declaring the pump immediately inoperable. Contact the Condition Monitoring Group (CMG) of the inoperable pump.

Page 27 N 1 -ST-Q19 Rev 08

10.1.3 BV 210.1-01 and BV 210.1-02, Cooling Coil 11 and 12 Inlet BVs test results meet IST Acceptance Criteria as follows:

TEST I;TROKE COMPONENT DIRECTION TIME

-set (8.3.2)

CLOSED TO OPEN

21 0.1-01 CLOSED TO OPEN *

--set (8.3.2) 210.1-02 ACCEPTANCE TEST CRITERIA**

RESULTS (2 0.9 sec and I 2.8 sec)

(A SAT

(-)

UNSAT (2 0.47 sec and I 3.27 sec)

(2 1.2 sec and I 3.7 sec)

(2 0.62 sec and I 4.32 sec)

(-)

SAT

(-) UNSAT Valve Test Results 1

I TEST 1

Si:($

COMPONENT DIRECTION CLOSED TO OPEN *

-set (8.4.5) 21 0.1-56 ACCEPTANCE TEST CRITERIA **

RESULTS (2 24.5 sec and I 40.8 sec)

(2 16.35 sec and I 49.05 sec}

(-1 SAT

(-)

UNSAT Acceptance Valve exercising in the direction indicated verifies acceptable Fail-safe Testing.

If any stroke time exceeds the IST stroke timelacceptance limit ( ) and is within the Limiting Stroke Time {LS}, the valve may be stroked a second time per section 4.7.6. If after a second stroke, the time exceeds the IST stroke timelacceptance limit ( ), then declare the valve INOPERABLE.

Initiate a CR and notify IST for any valve, which required a second stroke.

10.1.5 All test documentation is completed. (-)

YES (-)

NO I

Completed by CRSlSM Date Time Page 28 N1 -ST-Q19 Rev 08

10.1.6 SM Review

(-)

Satisfactory, no corrective action required.

(-)

Satisfactory, corrective action required. (Use Remarks Section as necessary and initiate an ACR.)

(-)

Unsatisfactory, (Use Remarks Section as necessary, initiate an ACR and immediately Notify

Operations Manager, or Alternate).

For any component tested with this surveillance test that is declared inoperable in accordance with the Acceptance Criteria, perform the following as applicable:

Enter it in the ESL.

Enter any applicable Technical Specification LCOs.

Make an entry in the SM Log.

Place a Yellow Clearance Section tag on the component.

Write an ACR.

Inform ISTlCMG (Engineering F'rograms).

Notify Manager Operations or dl, =SI

'g nee.

Generate a CR.

Name of person Notified Rem arks:

Signature SM Date Time Page 29 N 1 -ST-Q 19 Rev 08

10.2 IST Review

(-)

Satisfactory, no corrective action required.

(-)

Increased test frequency required (Lkt equipment ID in Remarks,)

(-)

Recommendations (explain in Remarks.)

Remarks:

Signature IST Date Time 10.3 Second Review All test data reviewed AND all documentation completed.

STAlSRO Signature Date Page 30 N 1-ST-Q19 Rev 08

ATTACHMENT 1: TEST PEqSONNEL SIGNATURE AND INITIAL LOG Completing this attachment signifies that each person has reviewed the applicable portions of this procedure.

NOTE:

PRINTED NAME SIGNATURE INITIALS SM Doh SA^*

CRO Page 31 N1-ST-Q19 Rev 08

I ATTACHMENT 2: CHILLED WATER CIRCULATING PUMP SKETCH EPN#: 210.137 (#It), 210.136 (#12)

Coupling Guard I

I I

1 1

I I

t 8

1

- Bebation View -

0

= Monitoring points required by CMG Page 32 N1-ST-Q19 Rev 08

ATTACHMENT 3: CHILLED WATE? CIRCULATING PUMP TEST FLOW DIAGRAM m70.25 L

L 3

210.1-21 210.1-119 210.1-32 70-26 Chilled Water Clrculalinp Pumps 210.1.2 I

U 210.168 6

210.1J7 210.1-75 210.1 -73

~~

~

Turbine Building I

I q

/

l M

210.158 8

210.161 210.1-60

~ ! Q W 210.162 Control Room 4

210.1-17 21 0.1 -19 Page 33 N 1 -ST-Q19 Rev 08

NRC JPM SRO RC Constellation Energy Group NINE MILE POINT UNIT 1 OPERATOR JOB F'ERFORMANCE MEASURE

Title:

Determine Actions for Inoperable Service Water Radiation Monitor Revision: NRC 2008 Task Number: N/A ate General Supervisor Date Operations 'Training (Designee)

Operations (Designee)

N/A - Exam Security Configuration Control Date TrainedEvaluator :

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time:

25 minutes Time Critical Task:

No Alternate Path Task:

No Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature:

Date:

October 2008 NRC 2008 SRO ADMIN JPM RC

- I -

Recommended Start Location: Classroom Simulator Set-up: None Directions to the InstructorEvaluator: None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as 1.he SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you wiih the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not avail able and that additional / concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore.,

either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas Pas,s/Fail.

2. During Evaluated JPM:

0

3. During Training JPM:

0 0

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. ARP H1; H1-4-5.

2. ODCM 3.6.14.a and TBL 3.6.14-1 Inst. 1B.

3. DER NM-2003-5 168, ODCM Entry Due to SW RM Low Flow.

4. DER NM-2004-976, Unplanned LCO - SW RM Low Flow.

5. WA 2.3.1 1 (3.2) Ability to control radiation releases.

Tools and Equipment:

1. None Task Standard: Determine actions per ARP H1-4-5 and ODCM in response to service water radiation monitor low flow condition.

NRC 2008 SRO ADMIN JPM RC October 2008

Initial Conditions:

1. The plant is operating at 100% power.

2. High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (12) hours.

3. HI-4-5, LQ PROCESS RAD MON, has alarmed.

4. Computer Point F172, SERVICE WATER SUI) FAILURE, is in alarm.

5. Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.

6. Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RE3).

7. Sample flow cannot be adjusted.

8. Ask the operator for any questions.

Initiating cue:

(Operators name), determine the appropriate actions and compensatory measures in response to ARP H1-4-5. Record your findings on the provided attachment.

EXAMINER NOTE: Provide Attachment 2.

1. Provide repeat back of initiating cue.

Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repe,at back (GAP-OPS-0 1 )

RECORD START TIME

1. Obtain a copy of the reference AW HI-4-5 obtained.

procedure and reviewhtilize the correct section.

Operator Actions referenced.

ODCM obtained.

DLCO 3.6.14 referenced.

Table D 3.6.14-1 referenced.

2. Per ARP H 1-4-5, if service water monitor alarm, and monitor EQUIP FAIL light is lit, then:

a. Notify Radiation Protection Notifies Radiation Protection Instrument Support to initiate repairs.

Instrument Support for repair.

b. Initiate LCO sampling (Chemistry).

3. Reference ODCM and takes appropriate actions.

Directs Chemistry to perform DLCO sampling per Table D 3.6.14-1 Instrument 1 B action (d); twelve (I 2) hour grab samples to be collected/analyzed for SW effluent.

Determines SW Radiation Monitor is inoperable.

Sat/Unsat SatXJnsat SatXJnsat Passmail SatXJnsat NRC 2008 SRO ADMIN JPM RC October 2008

I Standard and Table D 3.6.14-1 Instrument 1B and note (d) applies.

Grade Determines less than the minimum nurn ber of radioactive liquid effluent monitoring channels for service water effluent and takes action shown in Table D 3.6.14-1.

Detmnines action (d) applies.

Effluent releases via this pathway can continue provided that at least once per Iwelve (12) hours grab samples are collected and analyzed SW effluent.

Passmail Passmail TERMINATING CUE: Applicable actions per A.RP H1-4-5 and ODCM in response to service water radiation monitor low flow condition have been identified arid recorded.

RECORD STOP TIME NRC 2008 SRO ADMIN JPM RC October 2008

Initial Conditions:

1.

2.

3.

4.

5.

6.

7.

The plant is operating at 100% power.

High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (12) hours.

H1-4-5, LQ PROCESS RAD MON, has alarmed.

Computer Point F 172, SERVICE WATER SKID FAILURE, is in alarm.

Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.

Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpim on the west side (RB).

Sample flow cannot be adjusted.

Initiating cue:

(Operators name), determine the appropriate actions and compensatory measures in response to ARP H1-4-5. Record your findings on the provided attachment.

NRC 2008 SRO ADMIN JPM RC October 2008

.Attachment 1 ANSWER KEY Determine the appropriate actions in response to these conditions.

Action Notify Radiation Protection Instrument Support for repair.

Direct Chemistry to initiate required LCO sampling Determines SW Radiation Monitor is inoperable.

Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action shown in Table D 3.6.14-1.

Determines action identified in note (d) applies. Effluent releases via this pathway can continue provided that at least once per twelve (12) hours grab sample; are collected and analyzed.

Required By (Document)

ARP H 1-4-5 ODCM DLCO 3.6.14 TABLED 3.6.14-

1.

ODCM DLCO 3.6.14 TABLE NOTE (4

NRC 2008 SRO ADMIN JPM RC October 2008 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.

Action Required By (Document)

NRC 2008 SRO ADMIN JPM RC October 2008

PANEL: H1 ANNUNCIATOR: 4-5 1

2 3

4 5

6 7

8 1

2 3

4 LQ PROCESS RAD MON Computer Printout:

F163 SVC WTR HI RAD RX BLDG YES F164 SVC WTR HI RAD TURB BLDG YES F165 SVC WTR VALVE POS FAIL YES F172 SVC WTR SKID FAILURE YES E474 RB CLC RMON 11 CPS E473 RADWST DIS RMON 11 CPS F320 RADWST DIS RMON 12 CPS Operator Actions:

1. Confirm alarm on computer printout.

2. Confirm alarm condition at Rad Monitors on J Panel

3. IF Service Water Monitor I*HIGH" OR RBCLC "UPSCALE HI-HI",

THEN enter EPIP-EPP-21, AND execute concurrently.

4.

IF Service Water monitor alarm, THEN perform the following:

a.

For t1ALERTt8 or ltHIGHB1, confirm source of activity is Rx. Bldg. or

b.

Request Chemistry to sample discharge canal and Service Water to C.

IF alarm is F165 SVC WTR VAL'JE POS FAIL, Turb. Bldg. Service Water Hdr.

locate source of activity.

THEN confirm position of sampling valves 72-397 (Computer Input Pt.

F148) and 72-398 (Pt. F149).

THEN notify Rad Protection Instrument Support for repair AND initiate LCO sampling (Chemistry).

d.

IF monitor "EQUIP FAIL" light is lit,

5. IF RBCLC monitor alarm, THEN perform the following:

a.

Monitor RBCLC pressure, tempcrature, make-up tank to determine source of leak and isolate as required (Recirc Pump seal, Radwaste, SDC, RWCU, etc.)

THEN notify Chemistry to sample RBCLC as required to locate source of activity.

Section H, Feed And Bleed Procedure For Controlling RBCLC Activity.

THEN notify Rad Protection Instrument Support.

b.

IF "UPSCALE HIGH or "UPSCALN HI-HI",

c.

Control activity by Feed and Bleed in accordance with N1-OP-11,

d.

IF monitor INOP/DOWNSCALE, Operator Actions continued Device - Setpoint:

NOTE :

See monitors for current setpoints.

Page 29 N1 -ARP-H1 Rev 05

., I PANEL: H1 ANNUNCIATOR: 4-5 3perator Actions (Cont) 6. IF Liquid Radwaste Discharge monitor alarm, THEN perform the following:

a.

Request Radwaste Operator to stop batch discharge (if) in progress.

b.

Confirm Alarm potentiometer settings are correct or batch being

c.

Request Chemistry determine :if verification analysis is required or

d.

IF alarm sounds during period of no pump out,

e.

IF monitor INOP/Downscale, pumped.

whether discharge may continue.

THEN request Radwaste verify that monitor/detector is flushed with Demin Water.

THEN notify Rad Protection Instrument Support.

Possible Causes:

1. Radioactive cooling loads leaking into RBCLC or Service Water.

2. Malfunctioning Rad Monitor.

3. Service Water skid/valves power supply failure.

4. Rad Monitor element has "Hot Particle" requiring flushing.

References:

1. ODCM D 3.6.14 & 15

2. N1-OP-50B

3. N1-OP-11

4. N1-EOP-6

5. N1-EPP-1

6. P&ID:

C-18022-C, Sh. 1, 2 C-18045-C, Sh. 10

7. Electrical :

C-22025-C, Sh. 3 C-39640-C C-34857-C, Sh. 1 F-40212-C C-23146-C, Sh. 5 Alarm

Contact:

F163-74A/C2 (llC2)

F164-74A/D2 (llD2)

F165-74A/E2 (llE2)

F172-74A/L2 (llL2)

E474-Z6K1

- (RNO2B INOP)

Z6K2 - (RN02B Downscale)

Z6K3 - (RN02B High)

E473-25K2

- (RNO2A Dwnscl)

Z7K1 - (RN02A INOP)

Z5K1 - (RNOZA High)

F320-ZSK4

- (RNO2D Dwnscl)

Z7K2 - (RN02D INOP)

Z5K3 - (RNO2D High)

Page 30 N1 -ARP-Hl Rev 05

CONTROLS DLCO 3.6.14 RADIOACTIVE EFFLUENT INSTRUMENTATION Apdica bility:

Applies to the functionality of plant instrumentation that monitors plant effluents.

Obiective:

To assure the functionality of instrumentation to monitor the release of radioactive plant effluents.

Specification:

a.

Liquid Effluent The radioactive liquid effluent monitoring instru-mentation channels shown in Table D 3.6.14-1 shall be functional with their alarm setpoints set to ensure that the limits of Control DLCO 3.6.15.a.1 are not exceeded. The alarm setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Part 11.

With a radioactive liquid effluent monitoring instrumentation channel alarm setpoint less conservative than a value which will ensure that the limits of DLCO 3.6.15.a.l are met, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.

RADIOACTIVE EFFLUENT INSTRUMENTATIOI\\ - LIQUID D 3/4.6.14 SURVEILLANCE REQUIREMENT DSR 4.6.14 RADIOACTIVE EFFLUENT INSTRUMENTATION ADplicability:

Applies to the surveillance of instrumentation that monitors plant effluents.

Obiective:

To verify operation of monitoring instrumentation.

Specification:

a.

Liquid Effluent Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated functional by performance of the sensor check, source check, instrument channel calibration and channel test operations at the frequencies shown in Table D 4.6.14-1.

Records - Auditable records shall be maintained, in accordance with procedures in Part II, of all radioactive liquid effluent monitoring instrumentation alarm setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits of Control DLCO 3.6.15.a.1 are met.

13.1-1 Unit 1 ODCM Revision 29 February 2007

RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 CONTROLS SURVEILLANCE REQUIREMENT With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels functional, take the action shown in Table D 3.6.14-1. Restore the instruments to functional status within 30 days, or outline in the next Radioactive Effluent Release Report the cause of the nonfunctionality and how the instruments were or will be restored to functional status.

13.1-2 Unit 1 ODCM Revision 29 February 2007

RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 TABLE D 3.6.14-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Channels Functional Applicability

1. Gross Radioactivity Monitors(a)

A. Liquid Radwaste Effluent Line At all timedb)

B. Service Water System Effluent Line At all times("

2. Flow Rate Measurement Devices 1 (e)

At all

-.. times A. Liquid Radwaste Effluent Line H

B. Discharge Canal

3. Tank Level Indicating Devices")

A. Outside Liquid Radwaste Storage Tanks At all times

- Pumps curves or rated capacity will be utilized to estimate flow.

13.1-3 Unit 1 ODCM Revision 29 February 2007

RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 NOTES FOR TABLE D 3.6.14-1 Provide alarm, but do not provide automatic termination of release.

An operator shall be present in the Radwaste Control Room at all times during a release.

With the number of channels functional less than required by the minimum channels functional requirement, effluent releases may continue provided that prior to initiating a release:

1.

2.

Otherwise suspend release of radioactive effluents via this pathway.

With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gamma radioactivity at a lower limit of detection of at least 5x1 0 microcurie/ml.

At least two independent samples are analyzed in accordance with Specification DSR 4.6.15.a, and At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.

During discharge, with the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

With the number of channels functional less than required by the minimum channels functional requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during liquid additions to the tank.

Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents.

Deleted.

Monitoring will be conducted continuously by alternately sampling the reactor building and turbine building service water return lines for approximately 1 $minute intervals.

13.1-4 Unit 1 ODCM Revision 29 February 2007

RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 TABLE D 4.6.14-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Surveillance Reauirement Instrument Sensor Check Source Check(s Channel Test Channel Calibration

1.

2.

3.

Gross Beta or Gamma Radioactivity Monitors

a.

Liquid Radwaste Effluent Line

b.

Service Water Effluent Line Flow Rate Measurement Devices

a.

Liquid Radwaste Effluent Line

b.

Discharge Canal(d)

Tank Level Indicating Devicede)

a.

Outside Liquid Radwaste Storage Tanks 0 nce/d a y

Oncelday Once/day@)

None Once/day Once/discharge*

Once/3 months(a)*

0 n ce/yea r(b)*

Once/92 days Once/l84 days(a)

Once/24 months(b)

None None None

Required prior to removal of blank flange in discharge line and until blank flange is replaced.

- During liquid addition to the tank.

None None Once/3 months Once/24 months*

Oncelyear Oncell 8 months 13.1-5 Unit 1 ODCM Revision 29 February 2007

RADIOACTIVE EFFLUENT INSTRUMENTATION - LIQUID D 3/4.6.14 NOTES FOR TABLE D 4.6.14-1 (a)

The channel test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1.

Instrumentation indicates measured levels above the alarm setpoint.

2. Instrument indicates a downscale failure.

3.

Instrument controls not set in operate mode.

The channel calibration shall be performed using one or more reference standards certified by the National Institute of Standards and Technology (NIST), or using standards that are traceable to the NIST or using actual samples of liquid waste that have been analyzed on a system that has been calibrated with NlST traceable sources. These standards shall permit calibrating the system over its intended range of energy and measurement.

Sensor check shall consist of verifying indication of flow during periods of release. Sensor check shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic or batch releases are made.

Pump performance curves or rated data may be used to estimate flow.

Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents.

Source check may consist of an installed check source, response to an external source, or (for liquid radwaste monitors) verification within 30 minutes of commencing discharge of monitor response to effluent.

13.1-6 Unit 1 ODCM Revision 29 February 2007

NRC JPM SRO EP Constellation Energy Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Emergency Event Classification, Notification and Reclassification Revision: NRC 2008 Task Number: N/A

- Exam Securitv General Supervisor Date Operations Training (Designee)

Operations (Designee)

NIA - Exam Securitv Configuration Control Date Performer:

(SFLO)

TrainerEvahator:

Evaluation Method: Perform Evaluation Location: Classroom/Simulator Expected Completion Time: 30 minutes Time Critical Task:

Yes Alternate Path Task:

No Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature:

Date:

NRC 2008 SRO ADMIN JPM EP October 2008

Recommended Start Location: Classroom/Simulato~:

Simulator Set-up: None Directions to the InstructorEvaluator: None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the Unit 2 SM, Security Supervisor, Communication Aid, and other personnel as necessary. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

During this Training E M, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional 1 concurrent verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified as Passmail.

2. During Evaluated JPM:

0 Self-verification shall be demonstrated.

3. During Training JPM:

0 Self-verification shall be demonstrated.

0 No other verification shall be demonstrated.

References:

1. EPIP-EPP-0 1, Classification Of Emergency Conditions at Unit 1

2. EPIP-EPP-18, Attachment 1 SM/ED Checklist

3. EPIP-EPP-20, Emergency Notifications

5. WA 2.4.29(4.0), Knowledge of the Emergency Plan.

4. EPMP-EPP-0 10 1 Tools and Equipment:

2.0 SMED Checklist Package 1.O EPIP-EPP-0 1, ATTACHMENT 1, UNIT 1 13AL FLOWCHART NRC 2008 SRO ADMIN JPM EP October 2008

Task Standard:

Classify and declare the emergency event within 15 minutes of the time that indications are available to the Candidate that an EAL has been exceeded. Make notifications to New York State and Oswego County within 15 minutes of the time the event is declared.

Initial Conditions:

1. You are the Unit 1 Shift Manager.

2. Unit 1 is operating at 100% power.

3. Unit 2 is operating at 100% power.

4. The following conditions exist:

5. Ask the operator for any questions.

An Earthquake has just hit the site Unit 2 reports seismic instrumentation reads, 0.050g NAO reports structural steel has fallen and damaged Power Board 16B Initiating Cue:

(Operators name), based on the above conditions, determine the event classification per EPIP-EPP-0 1 and complete steps 1 through 7.b of EPIP-EPP-18, Attachment 1, SM/ED Checklist. This is a time critical task.

Examiner Note: After this event is classified, declared and the notifications initiated, the plant conditions will change as stated below and a reclassification will be required.

Initial Conditions #2:

1. The reactor has been scrammed due to rising drywell pressure.

2. Drywell pressure is 4.0 psig and slowly rising.

3. A Loss of Offsite Power has occurred and both EDGs are supplying their emergency buses.

4. The Security Supervisor notified the Control Room that an individual has entered the Reactor Building with intent to commit sabotage.

Initiating Cue:

(Operators name), based upon the above changes in plant conditions, determine any change in the emergency declaration level. This is a time critical task.

NRC 2008 SRO ADMIN JPM EP October 2008

I Performance Stem I Standard I

Grade I

1. Provide repeat back of initiating cue.

Proper communications used for repeat back Sat/Unsat Evaluator Acknowledge repeat back (GAP-OPS-0 1) providing correction if necessary RECORD START TIME

2. Obtain a copy of EPIP-EPP-0 1 attachment 1 and Shift Manager emergency paperwork and reviewhtilize the correct section.

EPIP-EPP-0 1 attachment 1 and Shift Manager emergency paperwork is obtained.

Sat/Unsat

3. Enters EPIP-EPP-18, Attachment 1, SMED Checklist and completes Steps 1 through 7.b.

Completes steps 1 thru 7b of EPIP-EPP-18, as described in subsequent JPM steps.

Sat/Unsat

4. Classifies and declares the emergency.

Declares an Alert within fifteen minutes of the Passmail JPM initial condition sheet being accepted in accordance with EAL 8.4.6.

EXAMINER NOTE: Time difference below must be 15 minutes or less:

JPM start time:

Time of Declaration:

5. Completes EPIP-EPP-18 attachment 1, figure Completes Attachment as shown in KEY Sat/Unsat 1 flowchart to determine evacuation and accountability requirements.

Note: Evacuation determination is subjective and may or may not be performed. This will determine which path is taken on EPIP-EPP-18 Attachment 1 and which steps are completed on EPIP-EPP-1 8.

6. Completes EPIP-EPP-18 attachment 2, Completes Attachment as shown in KEY SaWnsat Emergency Announcement.

NRC 2008 SRO ADMIN JPM EP

- 4 -

October 2008

I Standard I

Grade I

1 Performance Steps

7. Completes EPIP-EPP-20 Part 1 Notification Completes Attachment as shown in KEY Pass/Fail Fact Sheet.

Part 1 Notification Fact Sheet Steps 3 thru 7 are Critical Steps EXAMINER NOTE: Time difference must be 15 minutes or less:

Cue: If asked about the status of Unit 2, cue that Unit 2 is still operating at 100% power and meets EAL 8.4.1 (UE) due to the earthquake.

Time of Declaration (from JPM step 4):

Time EPIP-EPP-20 Part 1 Notification Fact Sheet is complete:

8. Completes EPIP-EPP-20 CAN Notification.

Completes Attachment as shown in KEY SatAJnsat EXAMINER NOTE:

Once EPIP-EPP-20 CAN Notification Form is completed, provide the applicant with Initial Conditions and Initiating Cue #2.

Cue: If contacted as Security or state police for road access state that road access is normal.

Note: This is also Time Critical.

6. Reviews the given conditions and determines that an SAE declaration is required per EAL 8.1.7 or 8.1.8 Declares SAE within 15 minutes per EAL 8.1.7 or 8.1.8 EXAMINER NOTE: Time difference below must be 15 minutes or less:

Time 2"d set of conditions was received:

Pass/Fail Time of Declaration:

TERMINATING CUE: The event has been classified and re-classified and all appropriate notifications initiated.

RECORD STOP TIME NRC 2008 SRO ADMIN JPM EP October 2008

Initial Conditions:

Stability Class

1. You are the Unit 1 Shift Manager.

2. Unit 1 is operating at 100% power.

3. Unit 2 is operating at 100% power.

4. The following conditions exist:

An Earthquake has just hit the site Unit 2 reports seismic instrumentation reads 0.050g NAO reports structural steel has fallen and damaged Power Board 16B D

Initiating Cue:

(Operators name), based on the albove conditions, determine the event classification per EPIP-EPP-0 1 and complete steps 1 through 7.b of EPIP-EPP-18,, SM/ED Checklist. This is a time critical task. : Meteorological Data Wind Direction (30 ft)

I Wind Direction (200 ft)

I 60 I

NRC 2008 SRO ADMIN JPM EP October 2008

Initial Conditions #2:

1. The reactor has been scrammed due to rising drywell pressure.

2. Drywell Pressure is 4.0 psig and slowly rising.

3. A Loss of Offsite Power has occurred and both EDGs are supplying their

4. The Security Supervisor notified the Control Room that an individual has entered emergency buses.

the Reactor Building with intent to commit sabotage.

Initiating Cue:

(Operators name), based upon the above changes in plant conditions, determine any change in the emergency declaraticin level. This is a time critical task.

NRC 2008 SRO ADMIN JPM EP October 2008

K CY ATTACElXENT I: SWE3 CHECKLIST

?aas 1 of 4 NOES:

1.

All steps should be peiformsd.

2.

3.

Us. M A or N/;i if appropriste.

A log axmentin3 sciiviiies shauld !E m$.ained.

1.

2.

3.

4.

5.

6.

7.

8.

3.

10.

. n M K l u i l indicaiions avaiiable in coniroi roorn)...........................................

....... n j q o El I Classify the emergency per E?I?-E??-OI or E?I?-EP?-03 (wiihin 15 rninu?es of Using ~ a c h n e n t I, iisclrs I fiowcha~ de:s:mini :IE appropriate evaxation and acmm:abiIi:y u

9 Announce to Conirol Room staff you are now sssming SMIED position and dLties! and you Ere ncw declaring (stste emergency classiiicakn level), and provide reason for clessifica;ion:dec!ara:ion/up3:ade....................................................... o &

o NGE: !F: the announcement for a gromd 2Zac.k hrs been mad2 8s required by EPI?-E??-IO, THEN: DO NOT make iuriher anncuncements until sakty is assured, coordinate as necessary with security.

Direct the appropriate announcement to 52 made using R:azhment 2 of this procedure NGT,:

[f ;""I--

wk,GssLfying and ERO has nDt been n:itified, repeat step 7 Inform unaffecied unit SM of forthcoming CAN not? cation fax and request Communica:ions Aide call CAN in accordance with faxed aKachment (only reed to call ogi :he E20 one time)

Compiete the idloving in accordance with EPI?-fF?-20:

a.

?art 1 Notification Fact Sheet (provide to Comm Aide) Include infomation from other Qnit as applicable.....................

!)q n n 0 ROTE:

Ass~re the safety of the E30 befor? ma {ing CAN Noiificalions. Consider directing E20 response to Alternate Emergency Duty Lacetion.

5.

CAN Nolification Form

1) F a compiekd for7 io u:,ai;'ec.;ed mil Co:,

(Ul-2996, U2-1207)...................................

or higher C.

N X Ro'irication Wo:ksh~e)s (provi3e i:, Corirn Aide).......................................................... 0 D O.. 3 NOTE:

For events sfi'ecting 5s:h mits, direct other Unit SM to cmpl?% K2C nstiiica:ion wo:ksheat a notify -;he N X Verify sFprc?riz?e Si2 Emersency ?rocedures implc.men:a:ion per,%achment 8..........................

U 0 c1 impiemeni emergency expasure controis in accordance with EPI?-E?P-l 5 (Including issuing KI ES required)..............................................................................

Implement Protective Actiors as needed per E?I?-E??-08, Atiachment 1.......................................................

CONTINUOCS

?age 5 EPP-EPP-I 8 iiev 16

k EY ATTACIiMENT 1 : FIGURE 3 EVACUATiONiACCOUNTABt LfTY FLOWCHART Page 8 EPIP-EPP-I 8 Rev 18

I k EY c3 li:

i

,477 AC 6 ki E NT 2 : E iV; E R G E N CY AN N OU t4 C E W EN T E A T 2 D b k

-I?!=.

IlitiL.

T M C I

It\\lSTEUCTiGNS: (cneck k x e s to select approprkk sn;ouncerner;t, c,znsiCer crcssing out rows not used)

1.

?LACE GAITXNICS IN KE2GE.

4.

0 a.

5.

0 a.

"h evacliation ~ f :

FOR A CREEISLE NSiCE? SECURITY TRREAT. 4DD (,Only do sie;, 3 once)

Secure sll non-essential activities in viial are,?s! :he two person line of sight viial area access rdes 2:s now in effest.

FOR A LOCAL.4RE4 EVACL'.4T!CNt ADD is being ordered due io:

M pmonne/ are to leas the (Unit 7/2)

[ a m ) sizying clear of and rep:: :3 I

E?l?-EP?-I 8

i KEY I

5.

IF NECESSARY ADD:

[If rzdisaciive release is in Frcgess, then olsiain plcme direction from Chem Tech 2nd check sppropiiak bcx below)

LI (De%ii oiier diiecrions as eppropriaie) 0 "I repeaf this is a drill."

"I repa: ihjs is an ac;u21 m q s n c y.

'I

12.

2epeai me alarm and eniire announcenent so :hat 211 specified steps of h e specific m o u n c m e n t are made 2 ( t w )

times.

Lezve GAlkonics in merge in&

fsrihe dilrsiion of?hi event.

U p n cmpietion rciurn ;his a:iachmeni io tht? E? Depi.

,I 3.

14.

P a p 1 1

ATTACHMENT IA: NINE MILE POINT NUCLEAR STATION NOTIFICATION FACT SHEET - PART 1 (Do not say items in italics)

Sheet 7 of 5

,-, Unaffected NMP Communications Center Warnina Point Power Plant Unit Notification ##

Chan ed F i

SECC)

I (not reqd in 15 min) I (not reqd in 15 min) I Step 4 This message is being transmitted on:

at via:

A. RECS I

(time - 24 hr clock)

ASK:

(provide as appropriate) THEN: This is the end of the message, standby for verification roll call.

Check those involved in verification roll call El Oswego County 0 JA Fitzpatrick Unaffected NMP 0 State Emergency Communications Center Warning Point Power Plant THEN STATE: Nine Mile Point out at time:

(time - 24 hr clock)

Approved by: (SMIED or EDIRM):

Print name:

Arne ~___

Signature :

I

ATTACHMENT 1A INSTRUCTIONS COMPLETING THE NOl'IFICATION FACT SHEET - PART 1 Sheet 2 of 5 NOTE:

1.

Complete all applicable sections.

2.

For all updates (all notifications except the initial) check the box or boxes that have changed from the last notification.

BLOCK #

INSTRUCTIONS

1.

2.

3.

Communications Aide completes this row using date and time that number was dialed (A then *).

Indicate actual emergency or exercise (drill) by circling a:; appropriate.

Indicate by circling as appropriate the:

A-D Classification Level, or E.

If event is terminated, or F.

Other Indicate the date and time (24 hr clock I military time) the event was classified.

Indicate the status of any releases of radioactive materials by circling as appropriate, request Chemistry Technician provide release information then indicate:

NOTE: (This section applies to a release of radioactive inaterials that took place DUE to the classified event. IF a radioactive

4.

5.

material release is taking place and it is unknown if it is related to the event, THEN assume the release is the result of the event)

A. No Release:

B. Release below federally approved operatinu limits (

C w

Circle this selection if a release is in progress due to the event AND the release rate has been determined (by any mean:; available) to NOT exceed ODCM [CI] Indicate using check box if to water or to atmosphere.

C. Release above federally approved operatinq limits (ODCM) Circle this selection if a release is in progress due to the event AND the release rate has been determined (by any mean:; available) to exceed ODCM. [CI] Indicate using check box if to water or to atmosphere.

D. Unmonitored release reauirinq evaluation: Circle this selection if evidence exists of a release from a pathway from which a release cannot be readily determined (examples: Emergency Condenser vents, steam or air passing blowout panels, Rx Bldg pressurized)

Circle this selection if there is no release related to the declared event.

6.

Indicate Protective Action Recommendations by circling as appropriate:

A.

8.

No need for protective actions Evacuate (indicate appropriate ERPAs as recommended by Dose assessment Advisor/ODAM) and implement the KI Plan for the following ERPAs and Shelter all remaining ERPAs. Circle the appropriate ERPAs

7.

Write the EAL #that the event was classified as, in the box provided for Item #7. If a site event, place the number nearest the Unit making the call. If each unit is declaring an emergency irldicate the appropriate EAL next to the specific unit number. Under -

Additional Information - see Notes below for examplesldirections for information that should be provided:

NOTES:

Do not repeat the EAL description here.

Provide other conditions if present that could have ian effect on future classifications / event or termination prognosis Put other EALs that amplify the present plant statu:,, do not write in all applicable EALs, only those that may impact present conditions. Other units status may be indicated here.

If the EAL requires no additional explanation, the Additional Information section should be left blank.

8.

Provide reactor status at both units. If unit is shutdown (per EOP definition), provide date and time of shutdown.

Each unit status should be provided regardless of an emergency has been declared at the opposite unit or not.

NOTES:

1.

2.

Meteorological Data to be recorded on the Part I Notification Fact Sheet is the 15 minute average data in accordance with EPIP-EPP-08.

IF meteorological data is not availablt? for the initial notification, then indicate LTR in that data field.

9.

Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record.

IO. Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record.

11. Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record. (Use elevated Stability class)

12. Communications Aide completes this row listing name and the commercial telephone they use.

THEN:

AND:

Provide to Communications Aide.

Sign the Part 1 Notification Fact Sheet.

For termination of Unusual Events only,

1.

Complete Part I - Notification Fact Sheet (Attachment 1 P ) through Line 4. Indicate date/time of termination on line 4 and:

a. Sign where appropriate

b. Provide to the Communications Aide Page '1 2 EPIP-EPP-20 Rev 20

KEY ATTACHMENT 4 E. Rapid Notify I

(Cont)

Sheet 2 of 5 REQUIREMENTS FOR RAPID NOTIFY NOTIFICATION Notification to RAPID NOTIFY and Pager Activation System should occur only when:

1.

Directed bv SMlEDl or EDlRM for event no:ification

2.

3.

4.

It is the first notification required for any Errergency Classification, OR The Emergency Classification is upgraded ?om an Unusual Event Classification.

Per EOF Communications Coordinator Checklist.

1.O CONTACT THE RAPID NOTIFY SYSTEM A.

B.

C.

Call RAPID NOTIFY System using orie of the numbers listed below:

Provide Message: "THIS IS TO REPORT AN INCIDENT AT NINE MILE POINT NUCLEAR STATION" then wait for the operator to pull up Nine Mile Point's file.

When prompted by the RAPID NOTIFY Operator, provide information as requested, including:

1. 8-1 -(800) 552-4226

2. 8-1-(877)-786-8478 Yourname Your position Your call-back number Unit 1 : (3 1 5)349-2869, (3 1 5)34E -1 204 Unit 2: (315)349-2171, (315)3458-1884 Other:

(write in number)

EOF: (315)593-5875 Password (ONTARIO) 2.0 When prompted by RAPID NOTIFY Operator, ]provide message as completed by SMlED A. This:

1. 0 is a drill checked

2. )(is an actual emergency This should be read as (example: *!A, This #I,,'s a drilfl COPY here:

a A

(used for step 4)

B.

Involving:

+

1.

Nine Mile Point Unit 1 Miy c(\\east e;&, /L 2. 0 Nine Mile Point Unit 2

3. 0 Both Units 5 L \\ J bL t c n S ; 5 b +

COPY checked here:

I o r 3 B

(used for step 4)

C.

Responders:

1.

No response is required COPY ##

a*

report to

2.

Response required to all ERFs checked

3. 0 Response recluired to Alternate

6. 0 Staff TSC/OSC only

8. 0 Precautionary staff ERFs here:

Emergency Duty Location C

(used for step 4) 3.0 Verify Correct Code A.

B.

When prompted by the RAPID NOTIFY Operator, repeat back the numerical code (as listed above):

Note time, date and person contacted:

Time:

Date:

Person Contacted:

C.

Hang-up the phone MANUALLY ACTIVATE THE PAGER SYSTEM Caution: Performing the following steps will result in the notification of the ERO.

A.

B.

C.

4.0 Call Pager Activation System at 8-249-0092 When asked to enter the password, enter '1357.

When asked to enter your numeric message, and using the three number code indicated in step 2 above, enter: (Be sure to include the Os) (OJ(OJ(OJ (2)

(1..'9 (a)

THEN PRESS #

A B

C D.

Hang-up the phone E.

Inform the SM/ED that RAPID NOTIFY has been notified.

Message Approval: (SMIED)(ED/RM) 5 i q n k k Time

-T;'tM\\e Pe'ge 19 EPIP-EPP-20 Rev 20

v t e Letter Sequence Draft Other
TAC:U01690, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML082980037, ML083220034, ML083230370, ML083230376, ML083230387, ML083230427, ML083230440, ML083230507, ML090330469
MONTHYEAR2008-11-14 [Table View]

ML083040108

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7.0 INTRODUCTION

1.2 ScopelApplicability

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6.2 REFERENCES

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