ML102520176

Initial Exam 2010-301 Final Administrative Job Performance Measures

ML102520176
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: ML102520176 (58)

Text

JPM NO. 548 REV. NO. 1 PAGE 1 OF 6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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 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 35 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.

JPM NO. 548 REV. NO. 1 PAGE 3 OF 6 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 35 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 (Electronic Dosimeter).

JPM NO. 548 REV. NO. 1 PAGE 4 OF 6 START TIME Performance Step 1: 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 2: Critical X Not Critical _

Calculates RWCU HX venting dose.

Standard:

35 minutes in a 250 mrem/hr area = 146 mrem SAT UNSAT N/A COMMENTS:

Performance Step 3: 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 5 OF 6 Performance Step 4: Critical X Not Critical _

Calculates total dose received Standard:

15 mrem travel + 146 mrem venting + 42 mrem 69-2 = 203 mrem SAT UNSAT N/A COMMENTS:

Performance Step 5: Critical X Not Critical _

Calculates total dose for quarter Standard:

750 mrem + 203 mrem = 953 mrem SAT UNSAT N/A COMMENTS:

Performance Step 6: *Critical_X Not Critical _

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 be exceeded.

SAT UNSAT N/A COMMENTS:

JPM NO. 548 REV. NO. 1 PAGE 6 OF 6 Performance Step 7: Critical _X Not Critical Verifies dose limits for quarter and RWP Standard:

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

END OF TASK STOP TIME

JPM NO. 551 REV. NO. 0 PAGE 1 OF 6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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 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. You have worked NO hours outside your schedule prior to 6/12.

INITIATING CUES: Review the upcoming 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 0700-1900 0700-1900 1900-0700 1900-0700 1900-0700 Off 0700-1900 Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 0700-1900 0700-1900 Off 1900-0700 1900-0700 1900-0700 Off

JPM NO. 551 REV. NO. 0 PAGE 3 OF 6 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. You have worked NO hours outside your schedule prior to 6/12.

INITIATING CUES: Review the upcoming 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 0700-1900 0700-1900 1900-0700 1900-0700 1900-0700 Off 0700-1900 Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 0700-1900 0700-1900 Off 1900-0700 1900-0700 1900-0700 Off

JPM NO. 551 REV. NO. 0 PAGE 4 OF 6 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 5 OF 6 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 6 OF 6 Attachment 1 (Page 1 of 3) 10 CFR 26 Overtime Limits Waiver

JPM NO. 551sro REV. NO. 0 PAGE 1 OF 11 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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 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. None of the operators have worked any hours outside their scheduled hours prior to 6/12.

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

JPM NO. 551sro REV. NO. 0 PAGE 3 OF 11 Reactor Operator #1 Sun Mon Tues Wed Thu Fri Sat 6/13 6/14 6/15 6/16 6/17 6/18 6/19 0700-1900 0700-1900 1900-0700 1900-0700 1900-0700 Off 0700-1900 Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 0700-1900 0700-1900 Off 1900-0700 1900-0700 1900-0700 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 0700-1900 0700-1900 0700-1900 0700-1900 0700-1900 0700-1900 Off Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 1900-0700 1900-0700 1900-0700 1900-0700 1900-0700 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 0700-1900 0700-1900 0700-2100 0700-1900 Off Off 1900-0900 Sun Mon Tues Wed Thu Fri Sat 6/20 6/21 6/22 6/23 6/24 6/25 6/26 1800-0700 1900-0700 Off 1900-0700 1900-0700 Off Off These three operators were off on 6/12

JPM NO. 551sro REV. NO. 0 PAGE 4 OF 11 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. None of the operators have worked any hours outside their scheduled hours prior to 6/12.

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

JPM NO. 551sro REV. NO. 0 PAGE 5 OF 11 START TIME Performance Step 1: 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 6 OF 11 Performance Step 2: 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 7 OF 11 Performance Step 3: 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 8 OF 11 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 9 OF 11 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 10 OF 11 Attachment 1 (Page 1 of 3) 10 CFR 26 Overtime Limits Waiver

JPM NO. 551sro REV. NO. 0 PAGE 11 OF 11 Attachment 1 (Page 1 of 3) 10 CFR 26 Overtime Limits Waiver

JPM NO. 552tc REV. NO. 0 PAGE 1 OF 6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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 INITIAL CONDITIONS: You are a Senior Reactor Operator on Unit 2. Unit 2 scrammed a short time ago on an MSIV isolation. 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 Rods inserted on the scram

• Reactor Level is at -100 inches and rising slowly

• Reactor Pressure is currently at 900 psig and rising being controlled on SRVs

• Numerous High Radiation Alarms are in for all Turbine areas

• 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

JPM NO. 551tc REV. NO. 0 PAGE 3 OF 6 Class Room INITIAL CONDITIONS: You are a Senior Reactor Operator on Unit 2. Unit 2 scrammed a short time ago on an MSIV isolation. 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 Rods inserted on the scram

• Reactor Level is at -100 inches and rising slowly

• Reactor Pressure is currently at 900 psig and rising being controlled on SRVs

• Numerous High Radiation Alarms are in for all Turbine areas

• 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

JPM NO. 551tc REV. NO. 0 PAGE 4 OF 6

JPM NO. 551tc REV. NO. 0 PAGE 5 OF 6

JPM NO. 551tc REV. NO. 0 PAGE 6 OF 6 START TIME Performance Step 1: 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 2: 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 3: 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 8 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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 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.

JPM NO. 553sro REV. NO. 0 PAGE 3 OF 8 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.

JPM NO. 553sro REV. NO. 0 PAGE 4 OF 8 START TIME Performance Step 1: 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 2: 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 5 OF 8 Performance Step 3: Critical X Not Critical _

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 4: 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.

SAT UNSAT N/A COMMENTS:

JPM NO. 553sro REV. NO. 0 PAGE 6 OF 8 Performance Step 5: 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:

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

END OF TASK STOP TIME

JPM NO. 553sro REV. NO. 0 PAGE 7 OF 8

JPM NO. 553sro REV. NO. 0 PAGE 8 OF 8 Attachment 1 (Page 2 of 2)

SPP-3.5 NRC Event Notification Worksheet

JPM NO. 554 REV. NO. 0 PAGE 1 OF 10 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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: 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 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, core alterations are scheduled to commence only 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 all the calculations and acceptance criteria steps in 1-SR-3.3.1.2.4 and notify him of the results of the acceptance criteria..

JPM NO. 554 REV. NO. 0 PAGE 3 OF 10 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, core alterations are scheduled to commence only 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 all the calculations and acceptance criteria steps in 1-SR-3.3.1.2.4 and notify him of the results of the acceptance criteria..

JPM NO. 554 REV. NO. 0 PAGE 4 OF 10 START TIME Performance Step 1: *Critical X Not Critical _

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

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

Reading in Step7.0[5.5]

The signal to noise ratio is________.

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

[5.10] IF applicable,

[5.11] UN-BYPASS SRM (OR FLC) A.

• [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 intials acceptance criteria for step 5.9.

Determines that SRM has less than the required 3 cps with fuel assemblies loaded in core quadrant A. Does not initial acceptance criteria for step 5.12.

SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 5 OF 10 Performance Step 2: *Critical X Not Critical _

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

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

Reading in Step7.0[6.5]

The signal to noise ratio is________.

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

[6.10] IF applicable,

[6.11] UN-BYPASS SRM (OR FLC) B.

• [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. Initals acceptance criteria for step 6.9 and step 6.12.

SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 6 OF 10 Performance Step 3: *Critical X Not Critical _

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

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

Reading in Step7.0[7.5]

The signal to noise ratio is________.

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

[7.10] IF applicable,

[7.11] UN-BYPASS SRM (OR FLC) C.

• [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, determines that the ratio is less than 3 cps and does not initial acceptance criteria for step 7.9 . Verifies SRM C has > 3cps and initials acceptance criteria for step 7.12.

SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 7 OF 10 Performance Step 4: *Critical X Not Critical _

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

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

Reading in Step7.0[8.5]

The signal to noise ratio is________.

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

[8.10] IF applicable, THEN

[8.11] UN-BYPASS SRM (OR FLC) D.

• [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. Initals acceptance criteria for step 8.9 and step 8.12.

SAT UNSAT N/A COMMENTS:

JPM NO. 554 REV. NO. 0 PAGE 8 OF 10 Performance Step 5: *Critical X Not Critical _

NOTE SRM Operability is established when the count rate 3 cps with a signal-to-noise ratio 3:1 (NOT required when 4 fuel assemblies adjacent to the SRM AND NO other fuel assemblies in the associated core quadrant) Step 7.0[14] may be N/Aed for each core quad where NO core alterations are being performed AND NONE expected within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 9 OF 10 Performance Step 6: 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 and does not initial for acceptance criteria 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 10 OF 10 Performance Step 7: 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:

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

JPM NO. 555sro REV. NO. 0 PAGE 1 OF 5 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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 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.

JPM NO. 555sro REV. NO. 0 PAGE 3 OF 5 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.

JPM NO. 555sro REV. NO. 0 PAGE 4 OF 5 START TIME Performance Step 1: 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 2: 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 5 OF 5 Performance Step 3: 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 4: 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. 561 REV. NO. 0 PAGE 1 OF 6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________

RO _____ SRO DATE:

JPM NUMBER: 561 TASK NUMBER: S-000-AD-55 TASK TITLE: PCS Head Tank Pump 2B Isolation Boundary K/A NUMBER: 2.2.41 K/A RATING: RO _3.5_ SRO: 3.9 TASK STANDARD: Determine the isolation boundary for PCS Head Tank Pump 2B LOCATION OF PERFORMANCE: Class Room / Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: 2-47E814-1, 2-45E779-19, 2-47E610-75-1, 2-45E2750-4, and 2-45E751-3 and 5 VALIDATION TIME:

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 INITIAL CONDITIONS: PCS Head Tank Pump 2B has a cracked weld on the discharge line where 2-75-SHV-76 ties into the line.

INITIATING CUES: The Unit Supervisor directs you as a Reactor Operator to determine the isolation points for the repair work on PCS Head Tank Pump 2B discharge line.

JPM NO. 561 REV. NO. 0 PAGE 3 OF 6 Class Room INITIAL CONDITIONS: PCS Head Tank Pump 2B has a cracked weld on the discharge line where 2-75-SHV-76 ties into the line.

INITIATING CUES: The Unit Supervisor directs you as a Reactor Operator to determine the isolation points for the repair work on PCS Head Tank Pump 2B discharge line.

JPM NO. 561 REV. NO. 0 PAGE 4 OF 6 START TIME Performance Step 1: Critical Not Critical _X Review prints to determine required isolation boundary: 2-47E814-1, 2-45E779-19, 2-47E610-75-1, 2-45E2750-4, and 2-45E751-3 and 5 Standard:

Locates and reviews prints for 2B PSC Head Tank Pump SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical _

Determines Isolation boundary Standard:

2-75-SHV-599 Pump Suction Valve Closed SAT UNSAT N/A COMMENTS:

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

JPM NO. 561 REV. NO. 0 PAGE 5 OF 6 Performance Step 3: Critical X Not Critical _

Determines Isolation boundary Standard:

2-75-SHV-603 Pump Discharge Valve Closed SAT UNSAT N/A COMMENTS:

Performance Step 4: Critical Not Critical _X Determines Isolation boundary Standard:

2-75-HS-75-75A Control Room Handswitch Pull to Lock SAT UNSAT N/A COMMENTS:

Performance Step 5: Critical X Not Critical _

Determines Isolation boundary Standard:

2B Pump Power Supply, 480 Volt RMOV Board 2B Disconnect 11D Open SAT UNSAT N/A COMMENTS:

JPM NO. 561 REV. NO. 0 PAGE 6 OF 6 Performance Step 6: Critical_ Not Critical _X Determines Isolation Boundary Standard:

The following drain valves may be identified but are not critical for personnel protection, 2-75-DRV-76, 2-75-DRV-604 and 2-75-DRV-605.

SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME