ML102520154

Initial Exam 2010-301 Draft Administrative Job Performance Measures

ML102520154
Person / Time
Site:	Browns Ferry
Issue date:	08/16/2010
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-259/10-301, 50-260/10-301, 50-296/10-301 50-259/10-301, 50-260/10-301, 50-296/10-301
Download: ML102520154 (61)

Text

JPM NO. 548 REV. NO. 1 PAGE 1 OF 5 OPERATOR:

RO _____

SRO DATE:

JPM NUMBER:

548 TASK NUMBER:

Radiation Control TASK TITLE:

Locked High Radiation Entry K/A NUMBER: 2.3.12 K/A RATING: RO _3.2_ SRO:

3.7 TASK STANDARD: Determine dress out requirements and estimate dose to verify within RWP and quarterly limits.

LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: Handout JPM 548 RWP and Survey Map, SPP 5.1 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS: ______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY ___

UNSATISFACTORY_____

SIGNATURE: ______________

DATE:

EXAMINER BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

Class Room INITIAL CONDITIONS: You are a Browns Ferry employee who has obtained an accumulative yearly dose of 750 mrem.

The job will require you to vent the RWCU Regenerative Hx and to manually close the 3-FCV-69-2 valve and place a mechanical restraining device on the valve. The RWCU Regenerative Hx will be vented from the scaffold at the south end of the Hx's (a scaffold has been erected to be used for venting - cannot leave scaffold while venting is in progress), and will require 30 minutes for venting. Then proceed to 3-FCV-69-2 valve to manually close and install the mechanical restraining device, it should require 10 minutes to close the valve and another 15 minutes to install the mechanical restraining device. Assume the 30cm reading will be the whole body dose received at each location. Assume a total travel dose of 15 mrem will be received.

INITIATING CUES: Given the survey map and RWP, determine the following:

• Dress-out requirements for entry to perform your assigned task

• Whether you can complete the assigned task in the area without exceeding your TVA administrative dose limit

• Whether you can complete the assigned task in the area without exceeding the RWP dose entry limits both rate and total dose, i.e. will you receive an MG alarm.

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

JPM NO. 548 REV. NO. 1 PAGE 3 OF 5 START TIME Performance Step:

Critical X Not Critical Determines Dress Out requirements Standard:

Shoe covers - one pair, Coveralls - one pair, Face Shield, Gloves - rubber - two pair, cloth inserts, Booties - plastic - 2 pair, Rain suit, and Hood SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Calculates RWCU HX venting dose.

Standard:

30 minutes in a 250 mrem/hr area = 125 mrem SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Calculates 69-2 valve work dose Standard:

25 minutes in a 100 mrem/hr area = 42 mrem SAT UNSAT N/A COMMENTS:

JPM NO. 548 REV. NO. 1 PAGE 4 OF 5 Performance Step:

Critical X Not Critical Calculates total dose recieved Standard:

15 mrem travel + 125 mrem venting + 42 mrem 69-2 = 182 mrem SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Calculates total dose for quarter Standard:

750 mrem + 182 mrem = 932 mrem SAT UNSAT N/A COMMENTS:

Performance Step:

Critical_ Not Critical

_X Verifies RWP MG Setpoints Standard:

MG setpoints: for Dose Rate alarm of 500 mrem/hr will not be exceeded and Dose alarm of 200 mrem will not be exceeded.

SAT UNSAT N/A COMMENTS:

JPM NO. 548 REV. NO. 1 PAGE 5 OF 5 Performance Step:

Critical_ Not Critical

_X Verifies dose limits for quarter and RWP Standard:

Verifies will have a total dose of less than 950 mrem which is below the TVA limit SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME

BROWNS FERRY NUCLEAR PLANT Unit: 3 Permit Number: Training Page: 1 RADIOLOGICAL WORK PERMIT BRIEFING REQUIRED EVERY ENTRY GENERAL DESCRIPTION Status: Active Start Date: 01-Jan-This year End Date: 01-Jan-Next year Type: SPECIFIC MAP ID: Outage: Y Name:

Task: ROUTINE PLANT MAINTENANCE PSE: N HP CONTINUOUS Authorization Type: INDIVIDUAL ALARA Review Number: 0A-0010 Primary Work Doc:

Person-mrem Estimate: 1904 Person-Hrs Estimate: 1082 Dose Alarm: 200 Dose Rate Alarm: 500 DAC-Hrs Tracked: N Work Area

Description:

RWCU HX Room Unit 3 DESCRIPTION OF WORK TO BE PERFORMED Unit 3 Maintenance on RWCU (69) Systems (LHRA VARIOUS DRESS) 200 / 500 ANTI-CONTAMINATION CLOTHING REQUIREMENTS 1 LAB COAT 1,2 BOOTIES, CLOTH, ONE PAIR 1,2 GLOVES, RUBBER, ONE PAIR 1,2,3 CLOTH INSERTS 1,2,3 SHOE COVERS, ONE PAIR 1,2,3 MODESTY CLOTHING 1,2,3 NO PERSONAL OUTER CLOTHING 1,2,3 SURGEON'S CAP 2,3 COVERALLS, ONE PAIR 3 BOOTIES, PLASTIC, TWO PAIR 3 FACE SHIELD 3 RAIN SUIT 3 GLOVES, RUBBER, TWO PAIR 3,4 HOOD DOSIMETRY REQUIREMENTS ELECTRONIC DOSIMETER TLD BRIEFING REQUIREMENTS PRE-JOB BRIEFING WORK STEPS 1 MANAGEMENT / WO WALKDOWN 2 3-CI-412 3 OPS VALVE LINEUP OI-69 & HX VENTING 4 07-712928-000 5 06-722560-000 6 06-727133-000 7 06-722556-000 8 06-722559-000 9 06-718308-002 10 06-722558-000 BROWNS FERRY NUCLEAR PLANT Unit: 3 Permit Number: Training

Page: 1 RADIOLOGICAL WORK PERMIT BRIEFING REQUIRED EVERY ENTRY WORKER INSTRUCTIONS 1 DRESSOUT CODE APPLICATIONS

1) FLOOR LEVEL INSP, LOW TO MODERATE CONTAMINATION.

2) MINOR MAINTENANCE, NO PRIMARY SYSTEM BREACH.

3) PRIMARY SYSTEM BREACH, HEAT EXCHANGER VENTING.

4) ANY WORK ABOVE FLOOR LEVEL REQUIRES SAFETY BELT W/ LIFELINE.

5) REQUIRED TO WEAR HEADGEAR OTHER THAN PERSONAL HARDHAT.

2 MONITOR YOUR ED (DAD) FREQUENTLY, EXIT THE AREA PRIOR TO REACHING THE DOSE ALARM SET POINT OR UPON RECEIVING ANY UNEXPECTED ALARMS.

3 DO NOT EXCEED 200 mrem PER ENTRY OR DOSE MARGIN (RAD-REMAINING ALLOWABLE DOSE).

4 REMOTE MONITORING, PEA, OR SIMILAR DEVICE REQUIRED.

5 ED (DAD) TO BE BAGGED (WRAPPED) AND WORN OUTSIDE OF C-ZONE CLOTHING.

6 REVIEW PLANNED WORK OR INSPECTIONS WITH RAD PROTECTION PRIOR TO ENTRY.

7 UTILIZE TIME, DISTANCE, AND SHIELDING ALARA PRINCIPLES.

8 REVIEW APPROPRIATE SURVEY DATA PRIOR TO ENTRY. NOTE AND AVOID POSTED HOT SPOTS. LOCATE AND UTILIZE LOW DOSE WAITING AREAS.

9 RADWORKER SHALL ADHERE TO ANY SPECIAL INSTRUCTIONS (APR, ETC) ON WHICH HE/SHE HAS BEEN BRIEFED BY RAD PROTECTION.

10 NOTIFY RADCON PRIOR TO ANY SYSTEM BREACH.

11 RAD PROTECTION COVERAGE MAY BE PROVIDED FROM OUTSIDE THE C-ZONE.

12 SECURE ALL HOSES, ELECTRICAL CORDS, WELDING LEADS AND OTHER SERVICES ENTERING THE C-ZONE AT THE C-ZONE BOUNDRY AND NOTIFY RAD PROTECTION.

13 NOTIFY RAD PROTECTION OF ANY UNUSUAL RADIOLOGICAL CONDITIONS (FOR EXAMPLE: WATER, LEAKS, RADIATION MONITOR ALARMS).

14 RAD PROTECTION PERMISSION REQUIRED PRIOR TO WELDING, GRINDING, BUFFING OR OTHER SURFACE DISTURBING ACTIVITIES.

APPROVAL Prepaired by: TJFRANK Approved by: MJHAZEL Final Approval: JWSMITH3 End of RWP

JPM NO. 551 REV. NO. 0 PAGE 1 OF 5 OPERATOR:

RO SRO DATE:

JPM NUMBER:

551 TASK NUMBER:

Conduct of Operations TASK TITLE:

Work Hour Limitations K/A NUMBER: 2.1.5 K/A RATING: RO 2.9 SRO:

3.9 TASK STANDARD: Determine Work Hour limitation will be exceeded and complete first part of attachment 1 of SPP 1.5.

LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: SPP 1.5 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS: ______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY ___

UNSATISFACTORY_____

SIGNATURE: ______________

DATE:

EXAMINER BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

Class Room INITIAL CONDITIONS: You are a Reactor Operator on Unit 2. Unit 1 is operating at 100%, Unit 3 is coming out of a Refuel Outage and startup is planned for tomorrow. Unit 2 has just pulled critical after a forced outage. Below is your work schedule. You were off on Saturday 6/12.

INITIATING CUES: Review the work schedule to verify your working hours are within the guidelines of SPP 1.5 Fatigue Management and Work Hour Limits.

Sun Mon Tues Wed Thu Fri Sat 6/13 6/14 6/15 6/16 6/17 6/18 6/19 07-19 07-19 19-07 19-07 19-07 Off 07-19 Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 07-19 07-19 Off 19-07 19-07 19-07 Off BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

JPM NO. 551 REV. NO. 0 PAGE 3 OF 5 START TIME Performance Step:

Critical X Not Critical 3.2 Requirements 3.2.1 The 10 CFR 26 Overtime Limits A. The following limits apply to covered individuals regardless of unit status:

1.

No more than 16 work hours in any 24-hour period

2.

No more than 26 work hours in any 48-hour period

3.

No more than 72 work hours in any 7-day period

4.

At least a 10-hour break between successive work periods, or an 8-hour break when a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is necessary to accommodate a crew's scheduled transition between work schedules or shifts.

5.

A 34-hour break in any 9-calendar day period (this limit may be incorporated into the following table of limits)

Standard:

Evaluates Schedule and determines he will need a need 10 CFR 26 Overtime Limits Waiver.

SAT UNSAT N/A COMMENTS:

CUE: Request Candidate complete page 1, up the point of identifying the work activity, of the 10 CFR 26 Overtime Limits Waiver

JPM NO. 551 REV. NO. 0 PAGE 4 OF 5 Performance Step:

Critical X Not Critical Cognizant Supervisor: ________________________________________

Date/Time Waiver Initiated: _______________/_____________________

Identify the individual who will exceed a 10 CFR 26 Overtime Limit:

Name:________________________________________

Department:___________________

Date/Time Waiver to Start: _______________/_____________________

Date/Time Waiver to End: ________________/_____________________

Waiver Duration (hours beyond limits): ___________________________

Identify all the limit(s) that will be exceeded by placing a check mark by the limit(s):

> 16 work hours in any 24-hour period

> 26 work hours in any 48-hour period

> 72 work hours in any 7-day period

< 10-hour (consecutive hours) break between successive work periods

< 34-hour (consecutive hours) break in any 9-day period Minimum Days Off (MMD) required Online Outage Required numbers of days off: ____

Shift schedule applied to individual: ____-hour shift Identify the work activity for which the waiver will be issued:

Standard:

Critical block required to be checked is < 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break in any 9 day period SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME

JPM NO. 551 REV. NO. 0 PAGE 5 OF 5 (Page 1 of 3) 10 CFR 26 Overtime Limits Waiver

JPM NO. 551sro REV. NO. 0 PAGE 1 OF 10 OPERATOR:

SRO DATE:

JPM NUMBER:

551 SRO TASK NUMBER:

Conduct of Operations TASK TITLE:

Work Hour Limitations K/A NUMBER: 2.1.5 K/A RATING: SRO:

3.9 TASK STANDARD: Determine Work Hour limitation will be exceeded and complete first part of attachment 1 of SPP 1.5.

LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: SPP 1.5 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS: ______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY ___

UNSATISFACTORY_____

SIGNATURE: ______________

DATE:

EXAMINER BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

Class Room INITIAL CONDITIONS: You are the Unit 2 Unit Supervisor, Unit 1 is operating at 100%, Unit 3 is coming out of a Refuel Outage and startup is planned for tomorrow. Unit 2 has just pulled critical after a forced outage. Attached is the work schedule for 3 reactor operators for the Unit 2 startup.

The attached list of operators are part of the Control Room crew.

INITIATING CUES: Review the work schedules of the Reactor Operators to verify that they are within the guidelines of SPP 1.5 Fatigue Management and Work Hour Limits.

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

JPM NO. 551sro REV. NO. 0 PAGE 3 OF 10 Reactor Operator #1 Sun Mon Tues Wed Thu Fri Sat 6/13 6/14 6/15 6/16 6/17 6/18 6/19 07-19 07-19 19-07 19-07 19-07 Off 07-19 Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 07-19 07-19 Off 19-07 19-07 19-07 Off Reactor Operator #2 Sun Mon Tues Wed Thu Fri Sat 6/13 6/14 6/15 6/16 6/17 6/18 6/19 07-19 07-19 07-19 07-19 07-19 07-19 Off Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 19-07 19-07 19-07 19-07 19-07 Off Off Reactor Operator #3 Sun Mon Tues Wed Thu Fri Sat 6/13 6/14 6/15 6/16 6/17 6/18 6/19 07-19 07-19 07-21 07-19 Off Off 19-09 Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 18-07 19-07 Off 19-07 19-07 Off Off These three operators were off on 6/12

JPM NO. 551sro REV. NO. 0 PAGE 4 OF 10 START TIME Performance Step:

Critical X Not Critical 3.2 Requirements 3.2.1 The 10 CFR 26 Overtime Limits A. The following limits apply to covered individuals regardless of unit status:

1.

No more than 16 work hours in any 24-hour period

2.

No more than 26 work hours in any 48-hour period

3.

No more than 72 work hours in any 7-day period

4.

At least a 10-hour break between successive work periods, or an 8-hour break when a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is necessary to accommodate a crew's scheduled transition between work schedules or shifts.

5.

A 34-hour break in any 9-calendar day period (this limit may be incorporated into the following table of limits)

Standard:

Evaluates Schedule and determines that operators #1 and #3 will need a need 10 CFR 26 Overtime Limits Waiver and that operator #2 is with in the guidelines of SPP 1.5.

SAT UNSAT N/A COMMENTS:

CUE: Request Candidate complete page 1 of the 10 CFR 26 Overtime Limits Waiver as required.

JPM NO. 551sro REV. NO. 0 PAGE 5 OF 10 Performance Step:

Critical X Not Critical Cognizant Supervisor: ________________________________________

Date/Time Waiver Initiated: _______________/_____________________

Identify the individual who will exceed a 10 CFR 26 Overtime Limit:

Name:________________________________________

Department:___________________

Date/Time Waiver to Start: _______________/_____________________

Date/Time Waiver to End: ________________/_____________________

Waiver Duration (hours beyond limits): ___________________________

Identify all the limit(s) that will be exceeded by placing a check mark by the limit(s):

> 16 work hours in any 24-hour period

> 26 work hours in any 48-hour period

> 72 work hours in any 7-day period

< 10-hour (consecutive hours) break between successive work periods

< 34-hour (consecutive hours) break in any 9-day period Minimum Days Off (MMD) required Online Outage Required numbers of days off: ____

Standard:

Critical block for Reactor Operator #1 is < 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break in any 9 day period Critical block for Reactor Operator #3 is > 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> in any 48.

SAT UNSAT N/A COMMENTS:

JPM NO. 551sro REV. NO. 0 PAGE 6 OF 10 Performance Step:

Critical X Not Critical Shift schedule applied to individual: ____-hour shift Identify the work activity for which the waiver will be issued:

==

Description:==

Circumstances that cause need for exceeding limits:

Waiver is required to address conditions that are adverse to safety?

Yes No If no, waiver is not valid Submitted by:

Print Name Signature Date Time Standard:

Critical block for both operators #1 and #3 is the yes block for adverse to safety.

SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME

JPM NO. 551sro REV. NO. 0 PAGE 7 OF 10 ANSWER KEY for OPERATOR #1 Cognizant Supervisor: ____NAME_______________________________

Date/Time Waiver Initiated: ____ _/_____________________

Identify the individual who will exceed a 10 CFR 26 Overtime Limit:

Name:_____REACTOR OPERATOR #1_________

Department:_____OPS______________

Date/Time Waiver to Start: _______________/_____________________

Date/Time Waiver to End: _____________/__________________

Waiver Duration (hours beyond limits): ___________________________

Identify all the limit(s) that will be exceeded by placing a check mark by the limit(s):

> 16 work hours in any 24-hour period

> 26 work hours in any 48-hour period

> 72 work hours in any 7-day period

< 10-hour (consecutive hours) break between successive work periods

< 34-hour (consecutive hours) break in any 9-day period Minimum Days Off (MMD) required Online Outage Required numbers of days off: ____

Shift schedule applied to individual: __12-hour shift Identify the work activity for which the waiver will be issued:

==

Description:==

Plant Startup Unit 2 Circumstances that cause need for exceeding limits: Forced Outage Waiver is required to address conditions that are adverse to safety?

Yes No If no, waiver is not valid Submitted by: NAME SIGNATURE Print Name Signature Date Time

JPM NO. 551sro REV. NO. 0 PAGE 8 OF 10 ANSWER KEY for OPERATOR #3 Cognizant Supervisor: ____NAME_______________________________

Date/Time Waiver Initiated: ____ _/_____________________

Identify the individual who will exceed a 10 CFR 26 Overtime Limit:

Name:_____REACTOR OPERATOR #3_________

Department:_____OPS______________

Date/Time Waiver to Start: _______________/_____________________

Date/Time Waiver to End: _____________/__________________

Waiver Duration (hours beyond limits): _______1 Hour________________

Identify all the limit(s) that will be exceeded by placing a check mark by the limit(s):

> 16 work hours in any 24-hour period

> 26 work hours in any 48-hour period

> 72 work hours in any 7-day period

< 10-hour (consecutive hours) break between successive work periods

< 34-hour (consecutive hours) break in any 9-day period Minimum Days Off (MMD) required Online Outage Required numbers of days off: ____

Shift schedule applied to individual: __12-hour shift Identify the work activity for which the waiver will be issued:

==

Description:==

Plant Startup Unit 2 Circumstances that cause need for exceeding limits: Forced Outage Waiver is required to address conditions that are adverse to safety?

Yes No If no, waiver is not valid Submitted by: NAME SIGNATURE Print Name Signature Date Time

JPM NO. 551sro REV. NO. 0 PAGE 9 OF 10 (Page 1 of 3) 10 CFR 26 Overtime Limits Waiver

JPM NO. 551sro REV. NO. 0 PAGE 10 OF 10 (Page 1 of 3) 10 CFR 26 Overtime Limits Waiver

APPENDIX A Page 1 of 1 GENERAL EMERGENCY INITIAL NOTIFICATION FORM High drywell radiation levels with RCS barrier NOT intact x

x Inside primary containment Shift Manager 2.3-G.2 x

x Current Today 216 20 x

Answer Key x

APPENDIX A Page 1 of 1 GENERAL EMERGENCY INITIAL NOTIFICATION FORM High drywell radiation levels with RCS barrier NOT intact x

x Inside primary containment Shift Manager 2.3-G.1 x

x Current Today 144 20 x

Applicant Handout

JPM NO. 552tc REV. NO. 0 PAGE 1 OF 5 OPERATOR:

SRO DATE:

JPM NUMBER:

552tc TASK NUMBER:

S-000-EM-25 TASK TITLE:

Classify the Event per EPIP-1 (2.3 G.2)

K/A NUMBER: 2.4.44 K/A RATING: SRO:

4.4 TASK STANDARD: Correct Initial Notification issued and correct Protective Action Recommendation issued.

LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: EPIP-1 and 5, Completed Notification Handout VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: 15 minutes (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS: ______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY ___

UNSATISFACTORY_____

SIGNATURE: ______________

DATE:

EXAMINER BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

Class Room INITIAL CONDITIONS: You are a Senior Reactor Operator on Unit 2. Unit 2 scrammed a short time ago on an MSIV isolation due to a complete loss of condenser vacuum. MSIV Line A failed to isolate and all attempts to isolate from the control room have failed. Current conditions are Drywell Pressure 10 psig and rising, Drywell Temperature 245°F and rising, All Control inserted on the scram, Reactor Level is at -100 inches and rising slowly, Reactor Pressure is currently at 900 psig and rising and being controlled on SRVs. Numerous High Radiation Alarms are in for all Turbine areas, and Drywell radiation levels are greater than 3000 R/hr on both radiation monitors and rising.

Stack Noble Gas (WRGERMS) indicates 9.5 x e9 µci/sec. Chemistry has just completed a Dose projection at 5 miles and it indicates 500 mREM TEDE and 1500 mREM Thyroid CDE. Current wind speed is 20 mph from 216° INITIATING CUES: The Shift Manager requests you to review General Emergency Initial Notification Form prior to notification of the State.

JPM is Time Critical BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

JPM NO. 552tc REV. NO. 0 PAGE 3 OF 5

JPM NO. 552tc REV. NO. 0 PAGE 4 OF 5

JPM NO. 552tc REV. NO. 0 PAGE 5 OF 5 START TIME Performance Step:

Critical X Not Critical Candidate reviews General Emergency Initial Notification Form Standard:

Candidate determines that: Step #3 is incorrect; correct designator is 2.3-G.2 2.3-G.1 is not met, 2.3-S1, 2.3-S.2 and 4.1-S are met but exceeded by the GE classification 2.3-G.2 SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Candidate reviews General Emergency Initial Notification Form Standard:

Candidate determines that: Step #7 Wind Direction is incorrect; should be 216° SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Candidate reviews General Emergency Initial Notification Form Standard:

Candidate determines that: Step #8 Protective Action Recommendation is incorrect; Recommendation 2 should be checked with the block next to 204 - 282 under column REC 2 checked. The answer to short term release is NO and the answer to table 1 limits is NO, for a protective action recommendation of 2.

SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME

JPM NO. 553sro REV. NO. 0 PAGE 1 OF 7 OPERATOR:

SRO DATE:

JPM NUMBER:

553 SRO TASK NUMBER:

Conduct of Operations TASK TITLE:

NRC Event Notification K/A NUMBER: 2.1.18 K/A RATING: SRO:

3.8 TASK STANDARD: Determine NRC Event Notification requirements LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: SPP 3.5 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS: ______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY ___

UNSATISFACTORY_____

SIGNATURE: ______________

DATE:

EXAMINER BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

Class Room INITIAL CONDITIONS: Unit 1 was conducting a shutdown in preparation for entering a refueling outage. The shutdown schedule called for power to be reduced to 20% and then a manual reactor scram was to be inserted.

Thirty minutes ago while lowering Reactor Recirculation Pump speed, a problem with the VFD on Reactor Recirculation Pump B developed. The Reactor Operator tripped Reactor Recirculation Pump B and inserted a manual reactor scram. Reactor Power was 35% at the time of the scram. All equipment operated as designed following the scram and plant conditions are now stable.

INITIATING CUES: As the Shift Manager evaluate this event for NRC Notification. Document any required notifications to the NRC Operations Center within the required time frame.

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

JPM NO. 553sro REV. NO. 0 PAGE 3 OF 7 START TIME Performance Step:

Critical X Not Critical Evaluates SPP-3.5 Appendix A: 3.1.C 3 Standard:

Determines a 4-Hr Non-Emergency 10CFR50.72(b)(2)(iv)(B) notification is required.

SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Complete SPP-3.5 NRC Event Notification Worksheet Standard:

Under Event Classification a check in box for 50.72 Non-Emergency SAT UNSAT N/A COMMENTS:

JPM NO. 553sro REV. NO. 0 PAGE 4 OF 7 Performance Step:

Critical Not Critical

_X Complete SPP-3.5 NRC Event Notification Worksheet Standard:

Under 4-Hr Non-Emergency 10CFR50.72(b)(2) a check in box (iv)(B) RPS Actuation (scram) ARPS.

SAT UNSAT N/A COMMENTS:

Performance Step:

Critical Not Critical

_X Complete SPP-3.5 NRC Event Notification Worksheet Standard:

Under 8-Hr Non-Emergency 10CFR50.72(b)(3) a check in box (iv)(A) Specified System Actuation AESF are the Critical Portions of the Form.

SAT UNSAT N/A COMMENTS:

JPM NO. 553sro REV. NO. 0 PAGE 5 OF 7 Performance Step:

Critical Not Critical

_X Complete SPP-3.5 NRC Event Notification Worksheet Standard:

Power/Mode Before will be 35%/Mode 1, Power/Mode After will be Shutdown/Mode 3 and a brief description of the event.

SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME CUE: JPM complete once an entry is made in description block on first page, Additional Information page not required to be completed.

JPM NO. 553sro REV. NO. 0 PAGE 6 OF 7

JPM NO. 553sro REV. NO. 0 PAGE 7 OF 7 (Page 2 of 2)

SPP-3.5 NRC Event Notification Worksheet

JPM NO. 554 REV. NO. 0 PAGE 1 OF 9 OPERATOR:

RO SRO DATE:

JPM NUMBER:

554 TASK NUMBER:

Conduct of Operations TASK TITLE:

Core Alts K/A NUMBER: 2.1.36 K/A RATING: RO 3.0 SRO:

4.1 TASK STANDARD: Completion of SRM Operability surveillance.

LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: 1-SR-3.3.1.2.4 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS: ______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY ___

UNSATISFACTORY_____

SIGNATURE: ______________

DATE:

EXAMINER BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

Class Room INITIAL CONDITIONS: You are a Reactor Operator on Unit 1. Unit 1 is in Mode 5, core alterations have been suspended for the past 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> due to bridge problems. Core quadrant A fuel moves are complete for the current off load schedule. No fuel assemblies remain around SRM A but 16 fuel assemblies remain in quadrant A. Core quadrants B, C, and D are completely fueled.

Bridge repairs are complete and core alterations are scheduled to commence in core quadrant B for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Core Alts can commence upon completion of 1-SR-3.3.1.2.4 Source Range Monitor System Count Rate and Signal to Noise Ratio Check. All data for 1-SR-3.3.1.2.4 has been obtained.

INITIATING CUES: The Unit Supervisor directs you to complete the calculations and acceptance criteria steps in 1-SR-3.3.1.2.4 and notify him of the results of the acceptance criteria..

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

JPM NO. 554 REV. NO. 0 PAGE 3 OF 9 START TIME Performance Step:

Critical X Not Critical

[5.8] COMPUTE the signal to noise ratio as follows AND RECORD results below:

Reading in Step7.0[5.5]

Reading in Step 7.0[5.7] Reading in Step 7.0[5.5]

The signal to noise ratio is________.

[5.9] VERIFY signal to noise ratio is > 3.

[5.12] VERIFY that SRM A has 3 cps, OR VERIFY that 4 fuel assemblies are adjacent to the SRM AND NO other fuel assemblies in the associated core quadrant.

Standard:

Calculates a signal to noise ratio of 24 and verifies >3. Determines that SRM has less than the required 3 cps with fuel assemblies loaded in core quadrant A.

SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 4 OF 9 Performance Step:

Critical X Not Critical

[6.8] COMPUTE the signal to noise ratio as follows AND RECORD results below:

Reading in Step7.0[6.5]

Reading in Step 7.0[6.7] Reading in Step 7.0[6.5]

The signal to noise ratio is________.

[6.9] VERIFY signal to noise ratio is > 3.

[6.12] VERIFY that SRM B has 3 cps, OR VERIFY that 4 fuel assemblies are adjacent to the SRM AND NO other fuel assemblies in the associated core quadrant.

Standard:

Calculates a signal to noise ratio of 9 and verifies >3. Verifies SRM B has > 3cps.

SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 5 OF 9 Performance Step:

Critical X Not Critical

[7.8] COMPUTE the signal to noise ratio as follows AND RECORD results below:

Reading in Step7.0[7.5]

Reading in Step 7.0[7.7] Reading in Step 7.0[7.5]

The signal to noise ratio is________.

[7.9] VERIFY signal to noise ratio is > 3.

[7.12] VERIFY that SRM C has 3 cps, OR VERIFY that 4 fuel assemblies are adjacent to the SRM AND NO other fuel assemblies in the associated core quadrant.

Standard:

Calculates a signal to noise ratio of 2.75 and determines that the ratio is less than 3 cps.

Verifies SRM C has > 3cps.

SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 6 OF 9 Performance Step:

Critical X Not Critical

[8.8] COMPUTE the signal to noise ratio as follows AND RECORD results below:

Reading in Step7.0[8.5]

Reading in Step 7.0[8.7] Reading in Step 7.0[8.5]

The signal to noise ratio is________.

[8.9] VERIFY signal to noise ratio is > 3.

[8.12] VERIFY that SRM D has 3 cps, OR VERIFY that 4 fuel assemblies are adjacent to the SRM AND NO other fuel assemblies in the associated core quadrant.

Standard:

Calculates a signal to noise ratio of 8 and verifies >3. Verifies SRM D has > 3cps.

SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 7 OF 9 Performance Step:

Critical X Not Critical Standard:

Quad A Quad B Quad C Quad D NO yes yes yes

> 3 cps yes yes NO yes

> 3:1 signal to noise yes yes yes yes quadrant fueled no YES no no SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 8 OF 9 Performance Step:

Critical X Not Critical

[14]

VERIFY an operable SRM detector is located in each core quadrant in which core alterations are being performed (OR planned within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

AND an adjacent core quadrant. CHECK MARK the appropriate operable SRMs for each core Quad:

IF Quad A, THEN SRM A and either SRM B or SRM D _____(AC)

IF Quad B, THEN SRM B and either SRM A or SRM C _____(AC)

IF Quad C, THEN SRM C and either SRM B or SRM D _____(AC)

IF Quad D, THEN SRM D and either SRM A or SRM C _____(AC)

Standard:

Completes Step 14 for a minimum of Quadrant B, determines acceptance criteria not met.

SAT UNSAT N/A COMMENTS:

CUE: If needed can ask Candidate if acceptance criteria is met for any core quadrant.

NOTE: NO CORE Alterations can commence

JPM NO. 554 REV. NO. 0 PAGE 9 OF 9 Performance Step:

Critical X Not Critical

[15]

RECORD the appropriate test information on Attachment 1, Surveillance Procedure Review Form (located in Section 8.0), AND COMPLETE up to Unit Supervisor Review.

[16]

NOTIFY UO that this SR test procedure is complete.

[17]

NOTIFY US that this SR test procedure is complete.

Standard:

Critical Step: completes Attachment 1 and marks NO for acceptance criteria satisfied.

Notifies UO and US.

SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME CUE: Acknowledge communication as Unit Operator and Unit Supervisor

JPM NO. 555sro REV. NO. 0 PAGE 1 OF 4 OPERATOR:

SRO DATE:

JPM NUMBER:

555sro TASK NUMBER:

Equipment Control TASK TITLE:

Containment Penetration Isolation to meet 3.6.1.3 K/A NUMBER: 2.2.40 K/A RATING: SRO:

4.7 TASK STANDARD: Determine components to provide isolation for Containment penetration X-211B, due to failure of 2-FCV-74-72 to meet TS 3.6.1.3 LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: TS 3.6.1.3, Drawing 2-47E811-1, SPP 10.2 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS: ______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY ___

UNSATISFACTORY_____

SIGNATURE: ______________

DATE:

EXAMINER BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

Class Room INITIAL CONDITIONS: The plant is in MODE 1. During performance of 2-SR-3.6.1.3.5 RHRII, RHR System MOV Operability Loop II, valve 2-FCV-74-72 RHR SYS II SUPPR CHBR SPRAY VALVE blew all main line fuses during its stroke time test. The valve is currently open and attempts to manually close 2-FCV-74-72 have been unsuccessful. The valve has been declared INOPERABLE and Technical Specification 3.6.1.3 (PCIVs), Condition A has been entered.

INITIATING CUES: The Shift Manager directs you as a Senior Reactor Operator, to determine the component(s) that will require isolation in order to comply with Technical Specification 3.6.1.3, Condition A. The Unit Supervisor is completing the required LCOs.

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

JPM NO. 555sro REV. NO. 0 PAGE 3 OF 4 START TIME Performance Step:

Critical Not Critical

_X Review print 2-47E811-1 to determine components that can isolate penetration X-211B due to failure of 2-FCV-74-72 Standard:

Locates and reviews print for designated CTMT Penetration and valves in flow path SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Identifies the following component to meet Technical Specification 3.6.1.3.

Standard:

2-FCV-74-71 needs Closed, De-activated and under Administrative Control SAT UNSAT N/A COMMENTS:

CUE: Not required to generate clearance. Identify component(s) that would be required to be listed on a clearance.

JPM NO. 555sro REV. NO. 0 PAGE 4 OF 4 Performance Step:

Critical X Not Critical Identifies the following component to meet Technical Specification 3.6.1.3.

Standard:

Test Valve 796B Closed and under Administrative Control SAT UNSAT N/A COMMENTS:

Performance Step:

Critical Not Critical

_X May Identify the following components but they are not required to meet Technical Specification 3.6.1.3.

Standard:

2-FCV-74-73, 2-74-715B, and 2-VTV-74-711B SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME

JPM NO. 556 REV. NO. 0 PAGE 1 OF 10 OPERATOR:

RO _____

SRO DATE:

JPM NUMBER:

556 TASK NUMBER:

U-000-SU-06 TASK TITLE:

Drywell Leakage Calculation K/A NUMBER: 2.2.38 K/A RATING: RO _3.6_ SRO:

4.5 TASK STANDARD: Calculate Drywell Floor and Equipment Sump leakage using 2-SR-2 and determine unidentified leakage is outside the acceptance criteria.

LOCATION OF PERFORMANCE: Class Room / Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: 2-SR-2 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS: ______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY ___

UNSATISFACTORY_____

SIGNATURE: ______________

DATE:

EXAMINER BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

Class Room INITIAL CONDITIONS: Unit 2 is operating at 100% power after a Refuel Outage last month.

The unit has been on line for 10 days. It is 0800 and the DW Floor and Equipment Drain have completed pumping down. The 0800 reading for Floor Drain is 60380 and for Equipment Drain is 44988.

INITIATING CUES: The Unit Supervisor directs you as a Reactor Operator to complete 2-SR-2 for the Drywell Floor and Equipment Drain Sumps and report results.

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

JPM NO. 556 REV. NO. 0 PAGE 3 OF 10 START TIME Performance Step:

Critical Not Critical

_X Completes 2-SR-2 for Drywell Unidentified Leakage for 0800 Saturday morning.

Standard:

Completes 0800 readings for Saturday SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Calculates a current unidentified leakrate of 3.41 gpm Standard:

Calculates a current unidentified leakrate of 3.41 gpm SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Calculates a change in leakrate of 2.02 gpm Standard:

Calculates a change in leakrate of 2.02 gpm SAT UNSAT N/A COMMENTS:

JPM NO. 556 REV. NO. 0 PAGE 4 OF 10 Performance Step:

Critical Not Critical

_X Completes 2-SR-2 for Drywell Identified Leakage and Total Leakage for 0800 Saturday morning Standard:

Completes 0800 readings for Saturday SAT UNSAT N/A COMMENTS:

Performance Step:

Critical X Not Critical Calculates a current identified leakrate of 2.32 gpm Standard:

Calculates a current identified leakrate of 2.32 gpm SAT UNSAT N/A COMMENTS:

JPM NO. 556 REV. NO. 0 PAGE 5 OF 10 Performance Step:

Critical_X Not Critical Calculates a total leakrate of 5.73 gpm Standard:

Calculates a total leak rate of 5.73 gpm SAT UNSAT N/A COMMENTS:

Performance Step:

Critical_X Not Critical Reports that the Unidentified increase in leakage does not meet the acceptance criteria of

<2 gpm within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

Standard:

Reports that the Unidentified increase in leakage does not meet the acceptance criteria of

<2 gpm within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME

Table 1.2 DRYWELL UNIDENTIFIED LEAKAGE DAY SHIFT WEEK: ________________________ to ________________________

APPLICABILITY:

Modes 1, 2 & 3 Readings are required at all times.

Surveillance Requirements:

3.4.4.1 LOCATION: Panel 2-9-4, 2-FQ-77-6 Col. A.1 Col. B.1 Col. C.1 Col. D.1 Col. E.1 Col. F.1 Col. G.1 Col. H.1 Col. I.1 Review Init Preferred reading times are 0800, 1200 and 1600 Current 2-FQ-77-6 Reading (gals)

(Notes 1, 2)

Previous Days 2-FQ-77-6 Reading from Col. A.1 (gals)

(Note 2)

Gallons Pumped Col. A.1

- Col. B.1 (Note 2)

Current Time (Note 2)

Previous Days Time from Col. D.1 (Note 2)

Elapsed Time Col. D.1

- Col. E.1 (min)

(Note 2)

Current Leakrate Col. C.1

÷ Col. F.1 (gpm)

(Note 2)

Previous Days Leakrate from Col. G.1 (gpm)

(Note 2)

Change in Leakrate Col. G.1

- Col. H.1 (gpm)

(Note 2, 3)

LIMITS (AC)

UO Unit Supvr (Note 4)

Friday 55469 53461 2008 0800 0800 1440 1.39 1.09

+.20 Col. G.1 5.0 gpm and (Note 3)

Col. I.1 2 gpm MS 57716 54182 3534 1200 1200 1440 2.45 1.11

+1.34 DZ 59010 54884 4126 1600 1600 1440 2.87 1.10

+1.77 BC Saturday Sunday Student Handout Student Handout Student Handout Monday Student Handout Student Handout Student Handout (1) Manually pump down sump per 2-OI-64 prior to reading. To record gallons, disregard the decimal position on integrator. Record only five digits including right-hand dials hash marks as gallons of flow. Example: Record 0065432.1 as 54321.

(2) May be N/Ad if Surveillance Requirement is being met with the performance of 2-SR-3.4.4.1 or 2-SR-3.4.4.1-a and a note stating such shall be made in the remarks section of this SR. When initial integrator reading is taken and no previous reading exists, all other entries except for Col. A.1 and D.1 should be N/Ad.

(3) Acceptance Criteria for Col. I.1 is only applicable when in Mode 1 for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4) Unit Supervisor shall Independently Verify Inleakage Calculations and verify Inleakage Acceptance Criteria.

Table 1.3 DRYWELL IDENTIFIED and TOTAL LEAKAGE DAY SHIFT WEEK: ________________________ to ________________________

APPLICABILITY:

Modes 1, 2 & 3 Readings are required at all times.

Surveillance Requirements:

3.4.4.1 LOCATION: Panel 2-9-4, 2-FQ-77-16 Col. A.2 Col. B.2 Col. C.2 Col. D.2 Col. E.2 Col. F.2 Col. G.2 Col. H.2 Col. I.2 Review Init Preferred reading times are 0800, 1200 and 1600 Current 2-FQ-77-16 Reading (gals)

(Notes 1, 2)

Previous Days 2-FQ-77-16 Reading from Col. A.2 (gals)

(Note 2)

Gallons Pumped Col. A.2

- Col. B.2 (Note 2)

Current Time (Note 2)

Previous Days Time from Col. D.2 (Note 2)

Elapsed Time Col. D.2

- Col. E.2 (min)

(Note 2)

Current Leakrate Col. C.2

÷ Col. F.2 (gpm)

(Note 2)

Current Unidentified Leakrate from Col. G.1 (gpm)

(Notes 2 & 3)

Total Leakrate Col. G.2

+ Col. H.2 (gpm)

(Note 2)

LIMITS (AC)

UO Unit Supvr (Note 4)

Friday 41647 39756 1891 0800 0800 1440 1.31 1.39 2.70 Col. I.2 30.0 gpm MS 41957 40080 1877 1200 1200 1440 1.30 2.45 3.75 DZ 42266 40388 1878 1600 1600 1440 1.30 2.87 4.17 BC Saturday Sunday Student Handout Student Handout Student Handout Monday Student Handout Student Handout Student Handout (1) Manually pump down sump per 2-OI-64 prior to reading. To record gallons, disregard the decimal position on integrator. Record only five digits including right-hand dials hash marks as gallons of flow. Example: Record 0065432.1 as 54321.

(2) May be N/Ad if Surveillance Requirement is being met with the performance of 2-SR-3.4.4.1 or 2-SR-3.4.4.1-a and a note stating such shall be made in the remarks section of this SR. When initial integrator reading is taken and no previous reading exists, all other entries except for Col. A.2 and D.2 should be N/Ad.

(3) G.1 reading is from Drywell Unidentified Leakage Col. G.1 on previous page.

(4) Unit Supervisor shall independently Verify Inleakage Calculations and verify Inleakage Acceptance Criteria.

Table 1.2 DRYWELL UNIDENTIFIED LEAKAGE DAY SHIFT WEEK: ________________________ to ________________________

APPLICABILITY:

Modes 1, 2 & 3 Readings are required at all times.

Surveillance Requirements:

3.4.4.1 LOCATION: Panel 2-9-4, 2-FQ-77-6 Col. A.1 Col. B.1 Col. C.1 Col. D.1 Col. E.1 Col. F.1 Col. G.1 Col. H.1 Col. I.1 Review Init Preferred reading times are 0800, 1200 and 1600 Current 2-FQ-77-6 Reading (gals)

(Notes 1, 2)

Previous Days 2-FQ-77-6 Reading from Col. A.1 (gals)

(Note 2)

Gallons Pumped Col. A.1

- Col. B.1 (Note 2)

Current Time (Note 2)

Previous Days Time from Col. D.1 (Note 2)

Elapsed Time Col. D.1

- Col. E.1 (min)

(Note 2)

Current Leakrate Col. C.1

÷ Col. F.1 (gpm)

(Note 2)

Previous Days Leakrate from Col. G.1 (gpm)

(Note 2)

Change in Leakrate Col. G.1

- Col. H.1 (gpm)

(Note 2, 3)

LIMITS (AC)

UO Unit Supvr (Note 4)

Friday 55469 53461 2008 0800 0800 1440 1.39 1.09

+.20 Col. G.1 5.0 gpm and (Note 3)

Col. I.1 2 gpm MS 57716 54182 3534 1200 1200 1440 2.45 1.11

+1.34 DZ 59010 54884 4126 1600 1600 1440 2.87 1.10

+1.77 BC Saturday 60380 55469 4911 0800 0800 1440 3.41 1.39

+2.02 ANSWER KEY ANSWER KEY ANSWER KEY Sunday ANSWER KEY ANSWER KEY ANSWER KEY Monday (1) Manually pump down sump per 2-OI-64 prior to reading. To record gallons, disregard the decimal position on integrator. Record only five digits including right-hand dials hash marks as gallons of flow. Example: Record 0065432.1 as 54321.

(2) May be N/Ad if Surveillance Requirement is being met with the performance of 2-SR-3.4.4.1 or 2-SR-3.4.4.1-a and a note stating such shall be made in the remarks section of this SR. When initial integrator reading is taken and no previous reading exists, all other entries except for Col. A.1 and D.1 should be N/Ad.

(3) Acceptance Criteria for Col. I.1 is only applicable when in Mode 1 for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4) Unit Supervisor shall Independently Verify Inleakage Calculations and verify Inleakage Acceptance Criteria.

Table 1.3 DRYWELL IDENTIFIED and TOTAL LEAKAGE DAY SHIFT WEEK: ________________________ to ________________________

APPLICABILITY:

Modes 1, 2 & 3 Readings are required at all times.

Surveillance Requirements:

3.4.4.1 LOCATION: Panel 2-9-4, 2-FQ-77-16 Col. A.2 Col. B.2 Col. C.2 Col. D.2 Col. E.2 Col. F.2 Col. G.2 Col. H.2 Col. I.2 Review Init Preferred reading times are 0800, 1200 and 1600 Current 2-FQ-77-16 Reading (gals)

(Notes 1, 2)

Previous Days 2-FQ-77-16 Reading from Col. A.2 (gals)

(Note 2)

Gallons Pumped Col. A.2

- Col. B.2 (Note 2)

Current Time (Note 2)

Previous Days Time from Col. D.2 (Note 2)

Elapsed Time Col. D.2

- Col. E.2 (min)

(Note 2)

Current Leakrate Col. C.2

÷ Col. F.2 (gpm)

(Note 2)

Current Unidentified Leakrate from Col. G.1 (gpm)

(Notes 2 & 3)

Total Leakrate Col. G.2

+ Col. H.2 (gpm)

(Note 2)

LIMITS (AC)

UO Unit Supvr (Note 4)

Friday 41647 39756 1891 0800 0800 1440 1.31 1.39 2.70 Col. I.2 30.0 gpm MS 41957 40080 1877 1200 1200 1440 1.30 2.45 3.75 DZ 42266 40388 1878 1600 1600 1440 1.30 2.87 4.17 BC Saturday 44988 41647 3341 0800 0800 1440 2.32 3.41 5.73 ANSWER KEY ANSWER KEY ANSWER KEY Sunday ANSWER KEY ANSWER KEY ANSWER KEY Monday (1) Manually pump down sump per 2-OI-64 prior to reading. To record gallons, disregard the decimal position on integrator. Record only five digits including right-hand dials hash marks as gallons of flow. Example: Record 0065432.1 as 54321.

(2) May be N/Ad if Surveillance Requirement is being met with the performance of 2-SR-3.4.4.1 or 2-SR-3.4.4.1-a and a note stating such shall be made in the remarks section of this SR. When initial integrator reading is taken and no previous reading exists, all other entries except for Col. A.2 and D.2 should be N/Ad.

(3) G.1 reading is from Drywell Unidentified Leakage Col. G.1 on previous page.

(4) Unit Supervisor shall independently Verify Inleakage Calculations and verify Inleakage Acceptance Criteria.