ML092870774

Initial Exam 2009-301 Draft Administrative JPMs

ML092870774
Person / Time
Site:	Browns Ferry
Issue date:	10/13/2009
From:	Division of Reactor Safety II
To:
References
50-259/09/301, 50-260/09/301, 50-296/09/301, JPM No. 541, Rev. 3
Download: ML092870774 (70)

Text

JPM NUMBER:

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 541 Admin Conduct of Operations JPM NO. 541 REV. NO.3 PAGE 1 of6 TITLE:

Determine Adequate Performance of License Reactivation PROVIDE CANDIDATE WITH A COpy OF: OPDP-10 (Only If Requested)

SUBMITTED BY:

VALIDATED BY:

APPROVED BY:

TRAINING PLANTCONCURRENCE:~ ________________ __

OPERATIONS DATE: ___

DATE: ____ _

DATE: ____ _

DATE: ____ _

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence JPM NUMBER:

BROWNS FERRY NUCLEAR PlANT JOB PERFORMANCE MEASURE 541 Admin Conduct of Operations JPM NO. 541 REV. NO. 3 PAGE 1 of6 TITLE:

Determine Adequate Performance of License Reactivation PROVIDE CANDIDATE WITH A COPY OF: OPDP-10 (Only If Requested)

SUBMITTED BY:

VALIDATED BY:

APPROVED BY:

TRAINING PLANT CONCURRENCE: ---=-==-:-==0=----

OPERATIONS DATE: ___

DATE: ___

DATE: ___

DATE: ___

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

Revision Effective Number Date 0

08/28/05 1

02/16/06 2

12/22/07 3

03/14/09 JPM NO. 541 REV. NO.3 PAGE2of6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue All Procedure Revision, Added references All General Revision & Procedure change All New Procedure (changed from OPDP-1 to OPDP-

10) and reformat and modified critical data Revision Effective Number Date 0

08/28/05 1

02/16/06 2

12/22/07 3

03/14/09 JPM NO. 541 REV. NO. 3 PAGE 2 of6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue All Procedure Revision, Added references All General Revision & Procedure change All New Procedure (changed from OPDP-1 to OPDP-

10) and reformat and modified critical data

JPM NO. 541 REV. NO.3 PAGE 30f6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ______________________________________________ __

RO SRO DATE: ____________ _

JPM NUMBER:

541 TASK TITLE:

Determine Adequate Performance of License Reactivation KIA NUMBER:

2.1.4 KIA RATING:

RO 3.3 SRO 3.8 TASK STANDARD: Determine which of the reactivating personnel have correctly completed the reactivation requirements.

PERFORMANCE LOCATION:

CLASSROOM:_---"-'X~_

REFERENCES/PROCEDURES NEEDED:

OPDP-10 Rev 0 VALIDATION TIME:

CLASSROOM: 15 min MAX. TIME ALLOWED: ____ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED?

YES __ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ___________ DATE: ____________ _

JPM NO. 541 REV. NO.3 PAGE 3 016 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ____________________________________________ __

RO SRO DATE: __________ __

JPM NUMBER:

541 TASK TITLE:

Determine Adequate Performance 01 License Reactivation KJA NUMBER:

2.1.4 KJA RATING:

RO 3.3 SRO 3.8 TASK STANDARD: Determine which olthe reactivating personnel have correctly completed the reactivation requirements.

PERFORMANCE LOCATION:

CLASSROOM: __ --"X'--_

REFERENCES/PROCEDURES NEEDED:

OPDP-10 Rev 0 VALIDATION TIME:

CLASSROOM: 15 min MAX. TIME ALLOWED: ____ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED?

YES ___ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _____________________ DATE: _____

INITIAL CONDITIONS:

License Preactivation Meeting SR01 LOR Training Lead Ops Superintendent SR02 Ops Training Manager Ops Superintendent R01 Ops Training Manager Shift Manager R02 Ops Training Manager Ops Superintendent R03 Ops Training Manager Ops Superintendent INITIATING CUES:

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EXAMINER'S KEY JPM NO. 541 REV. NO.3 PAGE4of6 5 licensed personnel have retumed to shift from rotating assignments and are reactivating their licenses. The following table gives information as to hours worked under direction of an activated licensee, tours performed, etc.

Shift 1 Shift 2 Shift 3 Shift 4 Shift 5 Shift 6 Plant Tour 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs 8 hrs PerSM U-1 U-2 U-2 U-2 U-3 U-3 instructions with SRO SRO SRO SRO SRO SRO U-2 Desk UO (RO) 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs 8hrs PerSM U-2 U-2 U-3 U-3 WCC U-1 instructions with SRO SRO SRO SRO SRO SRO Outside US (SRO) 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs 8hrs PerSM U-3 U-3 RO U-1 tagging U-2 U-2 instructions with RO RO UORO RO RO STA (SRO) 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs Per US U-2 U-2 RO U-1 U-3RO U-3 U-2 instructions with RO Called RO RO RO U-2 Desk UO for (RO)

Random during shift - 2 hrs 12 hrs 12 hrs 12 hrs 8hrs 8 hrs 8hrs PerSM U-2 U-2RO U-3 U-3RO U-1 U-1 instructions with RO RO RO RO U-2 Desk UO (RO)

Refer to the above information. Which of the personnel, (if any), have completed their requirements for license reactivation.

INITIAL CONDITIONS:

License Preactivation Meeting SR01 LOR Training Lead Ops Superintendent SR02 Ops Training Manager Ops Superintendent R01 Ops Training Manager Shift Manager R02 Ops Training Manager Ops Superintendent R03 Ops Training Manager Ops Superintendent INITIATING CUES:

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EXAMINER'S KEY JPM NO. 541 REV. NO. 3 PAGE 4 of6 5 licensed personnel have returned to shift from rotating assignments and are reactivating their licenses. The following table gives information as to hours worked under direction of an activated licensee, tours perfonmed, etc.

Shift 1 Shift 2 Shift 3 Shift 4 Shift 5 Shift 6 Plant Tour 12 hrs 12 hrs 12 hrs 12 hrs Bhrs Bhrs PerSM U-1 U-2 U-2 U-2 U-3 U-3 instructions with SRO SRO SRO SRO SRO SRO U-2 Desk UO (RO) 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs B hrs PerSM U-2 U-2 U-3 U-3 wee U-1 instructions with SRO SRO SRO SRO SRO SRO Outside US (SRO) 12 hrs 12 hrs 12 hrs 12 hrs Bhrs Bhrs Per SM U-3 U-3RO U-1 tagging U-2 U-2 instructions with RO RO UORO RO RO STA (SRO) 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs B hrs Per US U-2 U-2RO U-1 U-3RO U-3 U-2 instructions with RO Called RO RO RO U-2 Desk UO for (RO)

Random during shift - 2 hrs 12 hrs 12 hrs 12 hrs Bhrs 8hrs 8hrs PerSM U-2 U-2 RO U-3 U-3RO U-1 U-1 instructions with RO RO RO RO U-2 Desk UO (RO)

Refer to the above information. Which of the personnel, (if any), have completed their requirements for license reactivation.

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EXAMINER'S KEY Only R03 meets all the requirements for license reactivation.

JPM NO. 541 REV. NO.3 PAGE 50f6 SR01 did not interview with the Ops Training Manager and performed his tour with an RO.

SR02 worked one activation shift with the wee SRO, this position does not qualify, (the additional 8 hr shift worked was not enough, after four (4) 12 hr shifts, if changes to 8 hr shift, requires two (2) 8 hr shifts).

R01 did not interview with the Ops Superintendent and worked one activation shift with the tagging RO, this position does not qualify (after three (3) 12 hr shifts, if changes to 8 hr shifts, requires three (3) 8 hr shifts).

R02 left the Control Room for a random drug screening during one shift (but made up for it by working an additional shift - 8 hrs, however, the plant tour discussion was with the US instead of the SM.

START TIME STOP TIME END OF TASK BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EXAMINER'S KEY Only R03 meets all the requirements for license reactivation.

JPM NO. 541 REV. NO.3 PAGE 5 of6 SR01 did not interview with the Ops Training Manager and performed his tour with an RO.

SR02 worked one activation shift with the WCC SRO, this position does not qualify, (the additional 8 hr shift worked was not enough, after four (4) 12 hr shifts, if changes to 8 hr shift, requires two (2) 8 hr shifts).

R01 did not interview with the Ops Superintendent and worked one activation shift with the tagging RO, this position does not qualify (after three (3) 12 hr shifts, if changes to 8 hr shifts, requires three (3) 8 hr shifts).

R02 left the Control Room for a random drug screening during one shift (but made up for it by working an addITional shift - 8 hrs, however, the plant tour discussion was with the US instead of the SM.

START TIME STOP TIME END OF TASK

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 60f6 Classroom STUDENT HANDOUT INITIAL CONDITIONS:

5 licensed personnel have returned to shift from rotating assignments and are reactivating their licenses. The following table gives information as to hours worked under direction of an activated licensee, tours performed, etc.

License Preactivation Shift 1 Shift 2 Shift 3 Shift 4 Shift 5 Shift 6 Plant Tour Meeting SR01 LOR Training 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs 8 hrs PerSM Lead U-1 U-2 U-2 U-2 U-3 U-3 instructions Ops SRO SRO SRO SRO SRO SRO with U-2 Desk Superintendent UO (RO)

SR02 Ops Training 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs PerSM Manager U-2 U-2 U-3 U-3 WCC U-1 instructions Ops SRO SRO SRO SRO SRO SRO with Outside Superintendent US (SRO)

R01 Ops Training 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs 8 hrs PerSM Manager U-3 U-3RO U-1 RO tagging U-2 RO U-2 RO instructions Shift Manager RO UORO with STA (SRO)

R02 Ops Training 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs Per US Manager U-2 U-2RO U-1 RO U-3RO U-3RO U-2RO instructions Ops RO Called with U-2 Desk Superintendent for UO (RO)

Random during shift - 2 hrs R03 Ops Training 12 hrs 12 hrs 12 hrs 8 hrs 8 hrs 8 hrs PerSM Manager U-2 U-2 RO U-3RO U-3RO U-1 RO U-1 RO instructions Ops RO with U-2 Desk Superintendent UO (RO)

INITIATING CUES:

Refer to the above information. Which of the personnel, (if any), have completed their requirements for license reactivation.

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 6 of6 Classroom STUDENT HANDOUT INITIAL CONDITIONS:

5 licensed personnel have returned to shift from rotating assignments and are reactivating their licenses. The following table gives information as to hours worked under direction of an activated licensee, tours performed, etc.

License Preactivation Shift 1 Shift 2 Shift 3 Shift 4 Shift 5 Shift 6 Plant Tour Meeting SR01 LOR Training 12 hrs 12 hrs 12 hrs 12 hrs Bhrs B hrs Per SM Lead U-1 U-2 U-2 U-2 U-3 U-3 instructions Ops SRO SRO SRO SRO SRO SRO wlth U-2 Desk Superintendent UO (RO)

SR02 Ops Training 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs 8 hrs PerSM Manager U-2 U-2 U-3 U-3 wee U-1 instructions Ops SRO SRO SRO SRO SRO SRO with Outside Superintendent US (SRO)

R01 Ops Training 12 hrs 12 hrs 12 hrs 12 hrs Bhrs B hrs PerSM Manager U-3 U-3RO U-1 RO tagging U-2RO U-2RO instructions Shift Manager RO UO RO with STA (SRO)

R02 Ops Training 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs 8hrs Per US Manager U-2 U-2RO U-1 RO U-3RO U-3 RO U-2RO instructions Ops RO Called with U-2 Desk Superintendent for UO (RO)

Random during shift - 2 hrs R03 Ops Training 12 hrs 12 hrs 12 hrs Bhrs B hrs Bhrs PerSM Manager U-2 U-2RO U-3RO U-3RO U-1 RO U-1 RO instructions Ops RO with U-2 Desk Superintendent UO(RO)

INITIATING CUES:

Refer to the above information. Which of the personnel, (if any), have completed their requirements for license reactivation.

JPM NUMBER:

TITLE:

ADMIN:

510 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EVALUATE RECOMBINER PERFORMANCE Equipment Control PROVIDE CANDIDATE WITH A COpy OF: 3-01-66, section 6.1 SUBMITTED BY:

VALIDATED BY:

APPROVED BY:

TRAINING PLANTCONCURRENCE: ____________________ _

OPERATIONS JPM NO. 510 REV. NO.3 PAGE 1 of 14 DATE: ___

DATE: ___

DATE: ____ _

DATE: ____ _

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence JPMNUMBER:

TITLE:

ADMIN:

510 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EVALUATE RECOMBINER PERFORMANCE Equipment Control PROVIDE CANDIDATE WITH A COPY OF: 3-01-66, section 6.1 SUBMITTED BY:

VALIDATED BY:

APPROVED BY:

TRAINING PLANTCONCURRENCE: __ ~~~~~

OPERATIONS JPM NO. 510 REV. NO.3 PAGE 1 of 14 DATE: ___

DATE: ___

DATE :. ___

DATE :. _____ _

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

Revision Effective Number Date 0

08/08/02 1

06/22/07 2

01/02/08 3

05/18/09 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue All Procedure revision All General revision All General revision & re-format JPM NO. 510 REV. NO. 3 PAGE 2 of 14 Revision Effective Number Date 0

08/08/02 1

06/22/07 2

01 /02/08 3

05/18/09 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue All Procedure revision All General revision All General revision & re-format JPM NO. 510 REV. NO.3 PAGE 2 of 14

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 510 REV. NO.3 PAGE 3 of 14 OPERATOR: __________________________________________ ___

RO SRO DATE: __________ __

JPM NUMBER:

510 TASK TITLE:

EVALUATE RECOMBINER PERFORMANCE KIA NUMBER:

2.1.7 KIA RATING:

RO 4.4 SRO 4.7 TASK STANDARD: EVALUATE OFF-GAS RECOMBINER PERFORMANCE PERFORMANCE LOCATION:

CLASS ROOM: __ --=...:Xo.-_

REFERENCES/PROCEDURES NEEDED:

3-01-66, Rev 57 VALIDATION TIME:

CLASSROOM:

12:00 MAX. TIME ALLOWED:

________ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED?

YES ___ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ___________________ DATE: ______ __

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 510 REV. NO.

3 PAGE 3 of 14 OPERATOR: ____________________________________________ __

RO SRO DATE: ________ _

JPM NUMBER:

510 TASK TITLE:

EVALUATE RECOMBINER PERFORMANCE KJA NUMBER:

2.1.7 KJA RATING:

RO 4.4 SRO 4.7 TASK STANDARD: EVALUATE OFF-GAS RECOMBINER PERFORMANCE PERFORMANCE LOCATION:

CLASSROOM: __ ---"X'---_

REFERENCES/PROCEDURES NEEDED:

3-01-66, Rev 57 VALIDATION TIME:

CLASSROOM:

12:00 MAX. TIME ALLOWED:

_____ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATIACHED?

YES ___ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ___________,DATE: _____ __

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 510 REV. NO.3 PAGE 4 of 14 Classroom INITIAL CONDITIONS:

You are the desk operator. A startup is in progress on Unit 3 and reactor power has been raised to 99% rated thermal power. The Hydrogen Water Chemistry System is out of service lAW 3-01-4. Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with Section 5.0. The operating steam jet is operating properly.

INITIATING CUES:

The Shift Operations Supervisor directs you to evaluate Off-Gas Recombiner 3A performance in accordance with 3-01-66, Section 6.1.

3-TI-66-75A 393°F 3-TI-66-758 320 OF 3-TRS-66-77 A Center temp 618 OF 3-TRS-66-778 Center temp 380 OF Rx Power Thermal 3430 mwth 3-H2R-66-96 operable - both pens reading.24% H2 Classroom BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 510 REV. NO.3 PAGE 4 of 14 INITIAL CONDITIONS:

You are the desk operator. A startup is in progress on Unit 3 and reactor power has been raised to 99% rated thermal power. The Hydrogen Water Chemistry System is out of service lAW 3-01-4. Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with Section 5.0. The operating steam jet is operating properly.

INITIATING CUES:

The Shift Operations Supervisor directs you to evaluate Off-Gas Recombiner 3A performance in accordance with 3-01-66, Section 6.1.

3-TI-66-75A 393 OF 3-TI-66-75B 320 of 3-TRS-66-77A Center temp 618 of 3-TRS-66-77B Center temp 380 of Rx Power Thermal 3430 mwth 3-H2R-66-96 operable - both pens readinQ.24% H,

JPM NO. 510 REV. NO.3 PAGE 5 of 14 START TIME _____

6.1 Recombiner Performance Evaluation NOTES

1) The production of hydrogen and oxygen in the reactor is dependent upon reactor power level and upon the amount of hydrogen injected by the Hydrogen Water Chemistry System if in service. Since the recombination of hydrogen and oxygen is exothermic, the operating temperature of the recombiner is also dependent upon power level and the status of the HWC System.

2) Following startup, while still at low power, recombiner performance and hydrogen concentration should be closely monitored.

PERFORMANCE STEP:

CRITICAL NOT CRITICAL

[1]

PERFORM a recombiner performance evaluation as follows:

STANDARD:

[1.1]

DETERMINE the in-service recombiner inlet temperature as indicated on RECOMBINER 3A(3B), INLET TEMP 3-TI-66-75A(B), Panel 3-9-53.

Determined Recombiner 3A inlet temp 3-TI-66-75A, Panel 3-9-53 from handout.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO.3 PAGE 5 of 14 START TIME _____

6.1 Recombiner Performance Evaluation NOTES

1) The production of hydrogen and oxygen in the reactor is dependent upon reactor power level and upon the amount of hydrogen injected by the Hydrogen Water Chemistry System if in service. Since the recombination of hydrogen and oxygen is exothermic, the operating temperature of the recombiner is also dependent upon power level and the status of the HWC System.

2) Following startup, while still at low power, recombiner performance and hydrogen concentration should be closely monitored.

PERFORMANCE STEP:

CRITICAL NOT CRITICAL

[1]

PERFORM a recombiner performance evaluation as follows:

STANDARD:

[1.1]

DETERMINE the in-service recombiner inlet temperature as indicated on RECOMBINER 3A(3B), INLET TEMP 3-TI-66-75A(B), Panel 3-9-53.

Determined Recombiner 3A inlet temp 3-TI-66-75A, Panel 3-9-53 from handout.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO. 3 PAGE 6 of 14 PERFORMANCE STEP:

CRITICAL NOT CRITICAL STANDARD:

[1.2]

DETERMINE the in-service recombiner operating (center) temperature as indicated on RECOM81NER 3A/38 TEMPERATURE recorder, 3-TRS-66-77, Panel 3-9-53.

x Determined the in-service recombiner operating (center) temperature as indicated on Recombiner 3A temperature recorder, 3-TRS-66-77, Panel 3-9-53 (from handout).

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL STANDARD:

[1.3]

CALCULATE the temperature difference (.1T) between the values obtained in Steps 6.1 [1] and 6.1 [2].

Calculated Recombiner 3A inlet/center ~t and determined ~t is 225 of SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO. 3 PAGE 6 of 14 PERFORMANCE STEP:

CRITICAL NOT CRITICAL STANDARD:

[1.2]

DETERMINE the in-service recombiner operating (center) temperature as indicated on RECOM81NER 3A/38 TEMPERATURE recorder, 3-TRS-66-77, Panel 3-9-53.

x Determined the in-service recombiner operating (center) temperature as indicated on Recombiner 3A temperature recorder, 3-TRS-66-77, Panel 3-9-53 (from handout).

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL STANDARD:

[1.3]

CALCULATE the temperature difference (.1T) between the values obtained in Steps 6.1 [1] and 6.1 [2].

Calculated Recombiner 3A inlet/center ~t and determined ~t is 225 of SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO. 3 PAGE 7 of 14 PERFORMANCE STEP:

CRITICAL NOT CRITICAL STANDARD:

[1.4]

DETERMINE the reactor thermal power (MWt) from process computer.

Determined reactor thermal power from the handout.

x SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL NOT CRITICAL STANDARD:

[1.5]

USING Illustration 1, PLOT the corresponding point of reactor power in MWt and f). T.

Using illustration 1, Determined llt corresponding to 3430 MWT is 240.1 of.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO. 3 PAGE 7 of 14 PERFORMANCE STEP:

CRITICAL NOT CRITICAL STANDARD:

[1.4]

DETERMINE the reactor thermal power (MWt) from process computer.

Determined reactor thermal power from the handout.

x SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL NOT CRITICAL STANDARD:

[1.5]

USING Illustration 1, PLOT the corresponding point of reactor power in MWt and f). T.

Using illustration 1, Determined llt corresponding to 3430 MWT is 240.1 of.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO.3 PAGE 8 of 14 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL STANDARD:

[1.6]

VERIFY point on illustration 1 is above or equal to the appropriate line (HWC in service or HWC out of service)

Determines from Illustration 1 that calculated ~t vs MWt plots BELOW the HWC Out of Service (solid) line (Critical).

Stops task performance and informs SRO that acceptance criteria is NOT met. (Not Critical)

SAT UNSAT N/A __

COMMENTS: _____

CUE: SRO acknowledges acceptance criteria not met and directs performer to continue in the procedure and determine the required action to take.

JPM NO. 510 REV. NO.

3 PAGE 8 of 14 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL STANDARD:

[1.6]

VERIFY point on illustration 1 is above or equal to the appropriate line (HWC in service or HWC out of service)

Delermines from Illustration 1 that calculated LIt vs MWt plots BELOW the HWC Out of Service (solid) line (Critical).

Stops task performance and informs SRO that acceptance criteria is NOT met. (Not Critical)

SAT UNSAT N/A __

COMMENTS: _____

CUE: SRO acknowledges acceplance criteria not met and directs performer to continue In the procedure and determine the required action to lake.

JPM NO. 510 REV. NO.3 PAGE 9 of 14

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • kkkkkkk********************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

[2]

IF the in-service recombiner performance is below the minimum allowable, THEN:

STANDARD:

[2.1]

CHECK Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with Section 5.0.

N/A - Given in initial conditions.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

STANDARD:

[2.2]

MONITOR the OFFGAS HYDROGEN ANALYZER recorder, 3-H2R-66-96 on Panel 3-9-53.

Monitors the Offgas Hydrogen Analyzer recorder, 3-H2R-66-96 on Panel 3-9-53 (from handout both points operable and reading.24% H2.

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO.3 PAGE 9 of 14

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • kkkkkkk********************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

[2]

IF the in-service recombiner performance is below the minimum allowable, THEN:

STANDARD:

[2.1]

CHECK Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with Section 5.0.

N/A - Given in initial conditions.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

STANDARD:

[2.2]

MONITOR the OFFGAS HYDROGEN ANALYZER recorder, 3-H2R-66-96 on Panel 3-9-53.

Monitors the Offgas Hydrogen Analyzer recorder, 3-H2R-66-96 on Panel 3-9-53 (from handout both points operable and reading.24% H2.

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO.3 PAGE 10 of 14 PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

STANDARD:

[2.3]

IF both hydrogen analyzers are inoperable, THEN NOTIFY Chemistry to obtain a grab sample to determine hydrogen concentration.

Determined Step [2.3] is N/A.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL

[2.4]

IF a malfunction of the SJAE is suspected, THEN REFER TO Section 8.4 and TRANSFER SJAEs.

STANDARD:

Given in initial conditions that in service steam jet is operating properly and does NOT transfer SJAEs (Not Critical Unless determines to swap SJAE).

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO.3 PAGE 10 of 14 PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

STANDARD:

[2.3]

IF both hydrogen analyzers are inoperable, THEN NOTIFY Chemistry to obtain a grab sample to determine hydrogen concentration.

Determined Step [2.3] is N/A.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL

[2.4]

IF a malfunction of the SJAE is suspected, THEN REFER TO Section 8.4 and TRANSFER SJAEs.

STANDARD:

Given in initial conditions that in service steam jet is operating properly and does NOT transfer SJAEs (Not Critical Unless determines to swap SJAE).

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 510 REV. NO.3 PAGE 11 of 14 PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

[3]

IF off-gas hydrogen rises above 1 %, THEN REFER TO 3-AOI-66-1.

I CUE: [If asked] Off-Gas H2 has not changed (from the handout value)

STANDARD:

Determines off-gas hydrogen has NOT risen above 1 % from handout.

SAT UNSAT N/A __

COMMENTS: _____

CAUTION Off-Gas System valves are potentially spark-producing when operated; therefore, WHEN hydrogen concentration is suspected of being greater than 4%, THEN DO NOT TAKE any action that will change off-gas valve positions until after the unit is shut down.

PERFORMANCE STEP:

CRITICAL

[3]

IF off-gas hydrogen rises above 1 %, THEN REFER TO 3-AOI-66-1.

JPM NO. 510 REV. NO.3 PAGE 11 of14 NOT CRITICAL I CUE: [If asked] Off-Gas H2 has not changed (from the handout value)

STANDARD:

Determines off-gas hydrogen has NOT risen above 1% from handout.

x SAT UNSAT N/A __

COMMENTS: _____

CAUTION Off-Gas System valves are potentially spark-producing when operated; therefore, WHEN hydrogen concentration is suspected of being greater than 4%, THEN DO NOT TAKE any action that will change off-gas valve positions until after the unit is shut down.

I

JPM NO. 510 REV. NO. 3 PAGE 12 of 14

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • ***** k.***

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL

[4]

IF analysis or hydrogen analyzers show hydrogen concentration is below 4%, THEN PLACE standby recombiner in operation.

REFER TO Section 8.3.

STANDARD:

Determines the required action is to PLACE standby recombiner in operation lAW Section 8.3.

SAT UNSAT N/A __

COMMENTS: _____

I CUE: That completes this task.

END OF TASK STOP TIME ____

JPM NO. 510 REV. NO.

3 PAGE 12 of 14 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL

[4]

IF analysis or hydrogen analyzers show hydrogen concentration is below 4%. THEN PLACE standby recombiner in operation.

REFER TO Section 8.3.

STANDARD:

Determines the required action is to PLACE standby recombiner in operation lAW Section 8.3.

SAT UNSAT N/A __

COMMENTS: _____

I CUE: That completes this task.

END OF TASK STOP TIME. ____

250 200 150 100 o

Illustration 1 (Page 1 of 1)

JPM NO. 510 REV. NO.3 PAGE 13 of 14 Recombine Performance evaluation - AT to Reactor Power

~

/'"

V L

_".J-V

/'

,,-",A"

v.

~

_ ~ * ~. A t: IIIJ1VUZlUf V \\ ];Y...

~

o 500 1000 1500 2000 2500 MWt

--HWC OUt of Service. 0'010 HWC In Service Evaluation is satisfactory when intersection point of AT to Reactor Power is above the appropriate line.

For 3458mwt HWC in service HWC out Of service AT ~ 190°F AT ~242°F CURVE FACTORS Normal Water Chemistry (NWC)

Hydrogen water Chemistry (HVVC)

AT = O.070°F per MVVt AT = O.055°F per MVVt 250 200 150 100 o

Illustration 1 (Page 1 of 1)

JPM NO. 510 REV. NO.3 PAGE 13 of 14 Recombine Performance evaluation - AT to Reactor Power

~

/'"

V L

_".J-V

/'

,,-",A"

v.

~

_ ~ * ~. A t: IIIJ1VUZlUf V \\ ];Y...

~

o 500 1000 1500 2000 2500 MWt

--HWC OUt of Service. 0'010 HWC In Service Evaluation is satisfactory when intersection point of AT to Reactor Power is above the appropriate line.

For 3458mwt HWC in service HWC out Of service AT ~ 190°F AT ~242°F CURVE FACTORS Normal Water Chemistry (NWC)

Hydrogen water Chemistry (HVVC)

AT = O.070°F per MVVt AT = O.055°F per MVVt

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 14 of 14 Classroom INITIAL CONDITIONS:

You are the desk operator. A startup is in progress on Unit 3 and reactor power has been raised to 99% rated thermal power. The Hydrogen Water Chemistry System is out of service lAW 3-01-4. Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with Section 5.0. The operating steam jet is operating properly.

INITIATING CUES:

The Shift Operations Supervisor directs you to evaluate Off-Gas Recombiner 3A performance in accordance with 3-01-66, Section 6.1.

3-TI-66-75A 393°F 3-TI-66-758 320 of 3-TRS-66-77 A Center temp 618 of 3-TRS-66-778 Center temp 380 of Rx Power Thermal 3430 mwth 3-H2R-66-96 operable - both pens reading.24% H2 Classroom BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 14 of 14 INITIAL CONDITIONS:

You are the desk operator. A startup is in progress on Unit 3 and reactor power has been raised to 99% rated thermal power. The Hydrogen Water Chemistry System is out of service lAW 3-01-4. Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with Section 5.0. The operating steam jet is operating properly.

INITIATING CUES:

The Shift Operations Supervisor directs you to evaluate 00-Gas Recombiner 3A performance in accordance with 3-01-66, Section 6.1.

3-TI-66-7SA 393 OF 3-TI-66-7SB 320°F 3-TRS-66-77 A Center temp 618 OF 3-TRS-66-77B Center temp 380 OF Rx Power Thermal 3430 mwth 3-H2R-66-96 operable - both pens reading.24% H,

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER:

120F JPM NO. 120F REV. NO. 2 PAGE 1 of 28 TITLE:

PERFORM 2-SR-3.4.2.1 JET PUMP MISMATCH AND OPERABILITY TASK NUMBER:

U-068-SU-05 SUBMITTED BY:

DATE: ___

VALIDATED BY:

DATE: ___

APPROVED BY:

DATE: ___

TRAINING PLANTCONCURRENCE: ____________________ _

DATE: ___

OPERATIONS Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER:

120F JPM NO. 120F REV. NO.

2 PAGE 1 of 28 TITLE:

PERFORM 2-SR-3.4.2.1 JET PUMP MISMATCH AND OPERABILITY TASK NUMBER:

U-068-SU-05 SUBMITTED BY:

DATE: ___

VALIDATED BY:

DATE: ___

APPROVED BY:

DATE: ___

TRAINING PLANT CONCURRENCE: __===:::-:-:;:;-__ _

OPERATIONS DATE: ___

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

Revision Effective Number Date 0

06/03/07 1

06/27/08 2

05/01/09 JPM NO. 120F REV. NO.2 PAGE 2 of 28 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue All General revision & re-format All Procedure revision Revision Effective Number Date 0

06/03/07 1

06/27108 2

05/01 /09 JPM NO. 120F REV. NO.2 PAGE 2 of 28 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue All General revision & re-format All Procedure revision

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 120F REV. NO. 2 PAGE 3 of 28 OPERATOR: ____________________________________________ __

RO SRO DATE: _____

JPM NUMBER:

120F TASK NUMBER:

U-068-SU-05 TASK TITLE:

PERFORM 2-SR-3.4.2.1 JET PUMP MISMATCH AND OPERABILITY KIA NUMBER:

2.2.12 KIA RATING:

RO 3.7 SRO 4.1 TASK STANDARD: COMPLETE AN IN-PROGRESS SURVEILLANCE REQUIREMENT ON REACTOR RECIRCULATION SYSTEM JET PUMP MISMATCH AND OPERABILITY PERFORMANCE LOCATION:

CLASSROOM X PLANT _

CTRL ROOM _

REFERENCES/PROCEDURES NEEDED:

2-SR-3.4.2.1, Rev 25 VALIDATION TIME:

CLASSROOM:

30:00 LOCAL: ___

MAX. TIME ALLOWED: ____ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

The SR should be completed up to step 7.2 before it is given to Candidate ADDITIONAL COMMENT SHEETS ATTACHED?

YES __ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ___________ DATE: _____ __

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 120F REV. NO.2 PAGE 3 of 28 OPERATOR: __________________________________________ __

RO SRO DATE: __________ __

JPM NUMBER:

120F TASK NUMBER:

U-068-SU-05 TASK TITLE:

PERFORM 2-SR-3.4.2.1 JET PUMP MISMATCH AND OPERABILITY KiA NUMBER:

2.2.12 KiA RATING:

RO 3.7 SRO 4.1

• • • _**** __ **********-******"'****_*********_* ___ *_**_.... __ *******".1<,,"'****************

TASK STANDARD: COMPLETE AN IN-PROGRESS SURVEILLANCE REQUIREMENT ON REACTOR RECIRCULATION SYSTEM JET PUMP MISMATCH AND OPERABILITY PERFORMANCE LOCATION:

CLASSROOM.x PLANT _

CTRL ROOM _

REFERENCES/PROCEDURES NEEDED:

2-SR-3.4.2.1. Rev 25 VALIDATION TIME:

CLASSROOM:

30:00 LOCAL: ______ __

MAX. TIME ALLOWED:

________ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

The SR should be completed up to step 7.2 before it is given to Candidate ADDITIONAL COMMENT SHEETS ATTACHED?

YES ____ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________________ DATE: __________ __

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 120F REV. NO.2 PAGE 4 of 28 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit 2 Operator. Unit 2 is operating at 100% power for 280 Days on line,. 2-SR-3.4.2.1, Jet Pump Mismatch and Operability, is in progress and complete up to Step 7.2[1]. Candidate should contact Examiner for any necessary feedback or info and or to indicate task completion.

INITIATING CUES:

The Unit Supervisor directs you to continue with 2-SR-3.4.2.1. starting with Step 7.2[1].

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 120F REV. NO.2 PAGE 4 of 28 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit 2 Operator. Unit 2 is operating at 100% power for 280 Days on line,. 2-SR-3.4.2.1, Jet Pump Mismatch and Operability, is in progress and complete up to Step 7.2[lJ. Candidate should contact Examiner for any necessary feedback or info and or to indicate task completion.

INITIATING CUES:

The Unit Supervisor directs you to continue with 2-SR-3.4.2.1. starting with Step 7.2[lJ.

START TIME _____

JPM NO. 120F REV. NO.2 PAGE 5 of 28 Note: All of the following steps will require dating each page of the SR and initialing/"N/A"ing as appropriate.

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

7.2 Data Collections 7.2.1 Core Power and Flow Readings

[1]

RECORD the Core thermal power from Core Power and Flow Log.

(N/A if ICS is not available)

STANDARD:

Records ICS point CALC002 (From Data Sheet) 3456 CMWT.

SAT UNSAT N/A __

COMMENTS: _____

START TIME _____ _

JPM NO. 120F REV. NO.2 PAGE 5 of28 Note: All of the following steps will require daUng each page of the SR and initiallngf'N/A"ina as aDDroDrlate.

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 7.2 Data Collections 7.2.1 Core Power and Flow Readings x

[1]

RECORD the Core thermal power from Core Power and Flow Log.

(N/A if ICS is not available)

STANDARD:

Records ICS point CALC002 (From Data Sheet) 3456 CMWT.

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO. 2 PAGE 6 of 28

• • • • • • • • • • • • • • • • • • * * ********************** I< * *

• k*****************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

[2]

RECORD the Core plate differential pressure from ICS point 68-52 or 2-XR-68-50 (Green Pen). (N/A if not available).

STANDARD:

Records Core plate differential pressure from ICS point 68-52 or 2 XR-68-50 (From Data Sheet) 14.4 psid.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL

[3]

RECORD the Total Core flow.

STANDARD:

Total Core Flow (Red Pen) 2-XR-68-50 87.0 Mlb/hr Records Total Core Flow 2-XA-68-50 (From Data Sheet).

NOT CRITICAL x

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO. 2 PAGE 6 of 28

• • • • • • • • • • • • • • • • • • * * ********************** I< * * *******************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

[2]

RECORD the Core plate differential pressure from ICS point 68-52 or 2-XR-68-50 (Green Pen). (N/A if not available).

STANDARD:

Records Core plate differential pressure from ICS point 68-52 or 2 XR-68-50 (From Data Sheet) 14.4 psid.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL

[3]

RECORD the Total Core flow.

STANDARD:

Total Core Flow (Red Pen) 2-XR-68-50 87.0 Mlb/hr Records Total Core Flow 2-XA-68-50 (From Data Sheet).

NOT CRITICAL x

SAT UNSAT N/A __

COMMENTS: _____

NOTES JPM NO. 120F REV. NO.2 PAGE 7 of 28

1) If 2-SIT-68-59/71 (RB. EI 565 R-9 S-line - Local Panel) is used log the reason in post test Remarks.

2) Use the 2-SI-96-61 (or ICS PT 96-61) if both 2-SI-68-59 and 2-SIT-68-59 are not available for the2A Pump Motor and log the reason in post test Remarks.

3) Use the 2-SI-96-73 (or ICS PT 96-73) if both 2-SI-68-71 and 2-SIT-68-71 are not available for the 2B Pump Motor and log the reason in post test Remarks.

4) If a Recirculation Pump is not in service then the associated instrumentations can be marked as N/ A.

NOTES JPM NO. 120F REV. NO.2 PAGE 7 of 28

1) If 2-SIT-68-59/71 (RB. EI 565 R-9 S-line - Local Panel) is used log the reason in post test Remarks.

2) Use the 2-SI-96-61 (or ICS PT 96-61) if both 2-SI-68-59 and 2-SIT-68-59 are not available for the2A Pump Motor and log the reason in post test Remarks.

3) Use the 2-SI-96-73 (or ICS PT 96-73) if both 2-SI-68-71 and 2-SIT-68-71 are not available for the 2B Pump Motor and log the reason in post test Remarks.

4) If a Recirculation Pump is not in service then the associated instrumentations can be marked as N/ A.

JPM NO. 120F REV. NO. 2 PAGE 8 of 28

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 11 11*11*****************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 7.2.2 Recirculation Pump Loops STANDARD:

[1]

RECORD the Recirc Pump 2A and 28 Mtr Speeds for operating Recirc Pumps and circle instrumentation used.

Pump Mtr 2A Pump Mtr 28 2-SI-68-59 or 2-SI-68-71 or 2-SIT -068-0059 or 2-SIT-068-0071 or 2-SI-96-61 2-SI-96-73 1313 RPM 1313 RPM

[2]

RECORD th R P

e eClrc ump D' h

fl ISC arge ows.

Loop 2A Loop 28 2-FI-68-5 2-FI-68-81 45.0 gpm X 1000 44.0 gpm X 1000

[3]

RECORD th R

. I e eClrc oop 2A d 28 J t P an e

ump FI ow.

Loop 2A Loop 28 2-FI-68-46 2-FI-68-48 45 Mlb/hr 44 Mlb/hr Records Data in steps [1 ],[2], and [3] (From Data Sheet).

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO. 2 PAGE 8 of 28

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 11 11*11*****************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 7.2.2 Recirculation Pump Loops STANDARD:

[1]

RECORD the Recirc Pump 2A and 28 Mtr Speeds for operating Recirc Pumps and circle instrumentation used.

Pump Mtr 2A Pump Mtr 28 2-SI-68-59 or 2-SI-68-71 or 2-SIT -068-0059 or 2-SIT-068-0071 or 2-SI-96-61 2-SI-96-73 1313 RPM 1313 RPM

[2]

RECORD th R P

e eClrc ump D' h

fl ISC arge ows.

Loop 2A Loop 28 2-FI-68-5 2-FI-68-81 45.0 gpm X 1000 44.0 gpm X 1000

[3]

RECORD th R

. I e eClrc oop 2A d 28 J t P an e

um~ FI ow.

Loop 2A Loop 28 2-FI-68-46 2-FI-68-48 45 Mlb/hr 44 Mlb/hr Records Data in steps [1 ],[2], and [3] (From Data Sheet).

x SAT UNSAT N/A __

COMMENTS: _____

NOTE JPM NO. 120F REV. NO.2 PAGE 9 of 28 If a Recirculation Pump is not in service then the associated instrumentations can be marked as N/A.

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

7.2.3 Jet Pump Loops

[1]

RECORD the following Differential Pressure readings below:

Loop2A Loop2B INSTRUMENT JET PSID INSTRUMENT JET PSID PUMP PUMP 2-PDI-68-38 11 9.0 2-PDI-68-15 1

9.0 2-PDI-68-39 12 9.0 2-PDI-68-18 2

9.5 2-PDI-68-40 13 9.5 2-PDI-68-19 3

9.0 2-PDI-68-42 14 9.0 2-PDI-68-21 4

9.5 2-PDI-68-43 15 8.5 2-PDI-68-22 5

10.0 2-PDI-68-07 16 9.0 2-PDI-68-25 6

9.5 2-PDI-68-08 17 9.0 2-PDI-68-26 7

10.0 2-PDI-68-10 18 9.5 2-PDI-68-28 8

10.5 2-PDI-68-11 19 8.5 2-PDI-68-29 9

9.5 2-PDI-68-13 20 9.5 2-PDI-68-30 10

9.5 STANDARD

Records Jet Pump Differential Pressure readings (From Data Sheet)

SAT UNSAT N/A __

COMMENTS: _____

NOTE JPM NO. 120F REV. NO.2 PAGE 9 of 28 If a Recirculation Pump is not in service then the associated instrumentations can be marked as N/A.

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

7.2.3 Jet Pump Loops

[1 J RECORD the following Differential Pressure readings below:

LoopZA Loop2B INSTRUMENT JET PSID INSTRUMENT JET PSID PUMP PUMP 2-PDI-68-38 11 9.0 2-PDI-68-15 1

9.0 2-PDI-68-39 12 9.0 2-PDI-68-18 2

9.5 2-PDI-68-40 13 9.5 2-PDI-68-19 3

9.0 2-PDI-68-42 14 9.0 2-PDI-68-21 4

9.5 2-PDI-68-43 15 8.5 2-PDI-68-22 5

10.0 2-PDI-68-07 16 9.0 2-PDI-68-25 6

9.5 2-PDI-68-08 17 9.0 2-PDI-68-26 7

10.0 2-PDI-68-10 18 9.5 2-PDI-68-28 8

10.5 2-PDI-68-11 19 8.5 2-PDI-68-29 9

9.5 2-PDI-68-13 20 9.5 2-PDI-68-30 10

9.5 STANDARD

Records Jet Pump Differential Pressure readings (From Data Sheet)

SAT UNSAT N/A __

COMMENTS: ______ _

NOTES JPM NO. 120F REV. NO.2 PAGE 10 of 28

1)

Section 7.3 is performed when both Recirculation Pumps are in service. This section should be N/A'ed when in Single Loop Operation.

2)

To satisfy procedure Acceptance Criteria, either Step 7.3[3] or Step 7.3[4] must be satisfied.

• • • • • • • • • • • • • • • • "' It It * "'*****************************************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 7.3 Tech Spec 3.4.1.1 - Recirculation Loop Mismatch Verification With Both Recirculation Loops In Operation Checks

[1]

CALCULATE percent of rated core flow (%WT) using data obtained in Section 7.2.1 [3] as follows

[2]

STANDARD:

(Step 7.2.1[3] +102.5) X 100=

% Core Flow

(~+102.5) X 100 =

84.88 CALCULATE the absolute value for Recirculation Loop Jet Mismatch using data obtained in Section 7.2.2[3] as follows.

2-FI-68 2-FI-68-48 = Mismatch 45 Mlb/hr -

44 Mlb/hr

=

1 Mlb/hr Performs Calculation in Steps [1] and [2] (1 Mlb/hr mismatch).

X SAT UNSAT N/A __

COMMENTS: _____

NOTES JPM NO. 120F REV. NO.2 PAGE 10 of 28

1)

Section 7.3 is performed when both Recirculation Pumps are in service. This section should be N/A'ed when in Single Loop Operation.

2)

To satisfy procedure Acceptance Criteria, either Step 7.3[3] or Step 7.3[4] must be satisfied.

• • • • • • • • • • • • • • • • "' It It * "'*****************************************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 7.3 Tech Spec 3.4.1.1 - Recirculation Loop Mismatch Verification With Both Recirculation Loops In Operation Checks

[1]

CALCULATE percent of rated core flow (%WT) using data obtained in Section 7.2.1 [3] as follows

[2]

STANDARD:

(Step 7.2.1[3] +102.5) X 100=

% Core Flow

(~+102.5) X 100 =

84.88 CALCULATE the absolute value for Recirculation Loop Jet Mismatch using data obtained in Section 7.2.2[3] as follows.

2-FI-68 2-FI-68-48 = Mismatch 45 Mlb/hr -

44 Mlb/hr

=

1 Mlb/hr Performs Calculation in Steps [1] and [2] (1 Mlb/hr mismatch).

X SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 11 of 28 PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

[3]

IF %WT is < 70% as recorded in Step 7.3[1], THEN VERIFY Recirculation Loop Jet Pump Flow Mismatch recorded in Step 7.3[2] is =::; 10.25 Mlb/hr. (Otherwise N/A)

(AC)

[4]

IF %WT is ~ 70% as recorded in Step 7.3[1], THEN VERIFY Recirculation Loop Jet Pump Flow Mismatch recorded in Step 7.3[2] is =::; 5.12 Mlb/hr. (Otherwise N/A)

(AC)

STANDARD:

Marks Step [3] N/A due to > 70% AND Initials steps [4].

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 11 of 28 PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

[3]

IF %WT is < 70% as recorded in Step 7.3[1], THEN VERIFY Recirculation Loop Jet Pump Flow Mismatch recorded in Step 7.3[2] is =::; 10.25 Mlb/hr. (Otherwise N/A)

(AC)

[4]

IF %WT is ~ 70% as recorded in Step 7.3[1], THEN VERIFY Recirculation Loop Jet Pump Flow Mismatch recorded in Step 7.3[2] is =::; 5.12 Mlb/hr. (Otherwise N/A)

(AC)

STANDARD:

Marks Step [3] N/A due to > 70% AND Initials steps [4].

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 12 of 28 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4 Tech Spec 3.4.2.1 - Part A - Jet Pump Performance Checks 7.4.1 Loop 2A Recirculation Pump and Jet Pump Flow to Recirculation Pump Speed

[1]

Using the 2A Pump Speed recorded in Step 7.2.2[1] and the 2A Pump Flow recorded in Step 7.2.2[2]:

[2]

CHECK that the plot falls between the two bold lines on Illustration 1 and RECORD below.

I Plot falls between the bold lines Yes I:&:l No D

Using the 2A Pump Speed recorded in Step 7.2.2[1] and the 2A Jet Pump Flow in Step7.2.2[3]:

CHECK that the plot falls between the two bold lines on Illustration 2 and RECORD below.

I Plot falls between the bold lines Yes D

No I:&:l

[3]

Using Steps 7.4.1 [1] and 7.4.1 [2] from above:

DETERMINE if the Jet Pump Loop 2A criteria is satisfied by marking below if both steps are marked as Yes.

I Jet Pump Loop 2A criteria is satisfied Yes D No IXI STANDARD:

Marks Steps [1] YES, [2] and [3] NO after verifying Checking the plot does NOT fall between the bold lines on Illustration 2 for step 7.4.1 [2].

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 12 of 28 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4 Tech Spec 3.4.2.1 - Part A - Jet Pump Performance Checks 7.4.1 Loop 2A Recirculation Pump and Jet Pump Flow to Recirculation Pump Speed

[1]

Using the 2A Pump Speed recorded in Step 7.2.2[1] and the 2A Pump Flow recorded in Step 7.2.2[2]:

[2]

CHECK that the plot falls between the two bold lines on Illustration 1 and RECORD below.

I Plot falls between the bold lines Yes I:&:l No D

Using the 2A Pump Speed recorded in Step 7.2.2[1] and the 2A Jet Pump Flow in Step7.2.2[3]:

CHECK that the plot falls between the two bold lines on Illustration 2 and RECORD below.

I Plot falls between the bold lines Yes D

No I:&:l

[3]

Using Steps 7.4.1 [1] and 7.4.1 [2] from above:

DETERMINE if the Jet Pump Loop 2A criteria is satisfied by marking below if both steps are marked as Yes.

I Jet Pump Loop 2A criteria is satisfied Yes D No IXI STANDARD:

Marks Steps [1] YES, [2] and [3] NO after verifying Checking the plot does NOT fall between the bold lines on Illustration 2 for step 7.4.1 [2].

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 13 of 28 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4.2 Loop 2B Recirculation Pump and Jet Pump Flow to Recirculation Pump Speed

[1]

Using the 28 Pump Speed recorded in Step 7.2.2[1] and 28 Pump Flow recorded in Step 7.2.2[2]:

CHECK that the plot falls between the two bold lines on Illustration 3 and RECORD below.

I Plot falls between the bold lines Yes 0

No

[g]

[2]

Using the 28 Pump Speed recorded in Step 7.2.2[1] and 28 Jet Pump Flow recorded in Step7.2.2[3]:

CHECK that the plot falls between the two bold lines on Illustration 4 and RECORD below.

I Plot falls between the bold lines Yes

[g] No 0

[3]

Using Steps 7.4.2[1] and 7.4.2[2] from above:

DETERMINE if the Jet Pump Loop 28 criteria is satisfied by marking below if both steps are marked as Yes.

I Jet Pump Loop 28 criteria is satisfied Yes 0

No

[g]

STANDARD:

Marks Steps [1] NO,[2] YES, and [3] NO after verifying CHECKING the plot does NOT fall between the bold lines on Illustration 3 for step 7.4.2[2].

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 13 of 28 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4.2 Loop 2B Recirculation Pump and Jet Pump Flow to Recirculation Pump Speed

[1]

Using the 28 Pump Speed recorded in Step 7.2.2[1] and 28 Pump Flow recorded in Step 7.2.2[2]:

CHECK that the plot falls between the two bold lines on Illustration 3 and RECORD below.

I Plot falls between the bold lines Yes 0

No

[g]

[2]

Using the 28 Pump Speed recorded in Step 7.2.2[1] and 28 Jet Pump Flow recorded in Step7.2.2[3]:

CHECK that the plot falls between the two bold lines on Illustration 4 and RECORD below.

I Plot falls between the bold lines Yes

[g] No 0

[3]

Using Steps 7.4.2[1] and 7.4.2[2] from above:

DETERMINE if the Jet Pump Loop 28 criteria is satisfied by marking below if both steps are marked as Yes.

I Jet Pump Loop 28 criteria is satisfied Yes 0

No

[g]

STANDARD:

Marks Steps [1] NO,[2] YES, and [3] NO after verifying CHECKING the plot does NOT fall between the bold lines on Illustration 3 for step 7.4.2[2].

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO. 2 PAGE 14 of 28 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4.3 Recirculation Jet Pump Diffuser to Lower Plenum Differential Pressure Verification:

[1]

Using the individual 2A Jet Pump DP's recorded in Step 7.2.3[1]

CHECK that each individual Jet Pump DP recorded fall between the two bold lines on Illustration 5 for the recorded Total Flow in step 7.2.1 [3] and RECORD results below.

2A Individual DP's are between the bold lines.

Yes

!XI No 0

[2]

Using the individual 28 Jet Pump DP's recorded in Step 7.2.3[1]

CHECK that each individual Jet Pump DP recorded fall between the two bold lines on Illustration 6 for the recorded Total Flow in step 7.2.1 [3] and RECORD results below.

28 Individual DP's are between the bold lines.

Yes 0

No

!XI

[3]

Using Steps 7.4.3[1] and 7.4.3[2]

DETERMINE whether the Recirculation Jet Pump Diffuser to Lower Plenum Differential Pressure Verification criteria is satisfied by marking below if both steps are marked as Yes.

Jet Pump Diffuser to Lower Plenum Differential Pressure Verification criteria is satisfied Yes 0

No

!XI STANDARD:

Marks Steps [1] YES,[2] NO, and [3] NO after VERIFING DP is NOT between the two lines on Illustration 6 for step 7.4.3[2].

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO. 2 PAGE 14 of 28 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4.3 Recirculation Jet Pump Diffuser to Lower Plenum Differential Pressure Verification:

[1]

Using the individual 2A Jet Pump DP's recorded in Step 7.2.3[1]

CHECK that each individual Jet Pump DP recorded fall between the two bold lines on Illustration 5 for the recorded Total Flow in step 7.2.1 [3] and RECORD results below.

2A Individual DP's are between the bold lines.

Yes

!XI No 0

[2]

Using the individual 28 Jet Pump DP's recorded in Step 7.2.3[1]

CHECK that each individual Jet Pump DP recorded fall between the two bold lines on Illustration 6 for the recorded Total Flow in step 7.2.1 [3] and RECORD results below.

28 Individual DP's are between the bold lines.

Yes 0

No

!XI

[3]

Using Steps 7.4.3[1] and 7.4.3[2]

DETERMINE whether the Recirculation Jet Pump Diffuser to Lower Plenum Differential Pressure Verification criteria is satisfied by marking below if both steps are marked as Yes.

Jet Pump Diffuser to Lower Plenum Differential Pressure Verification criteria is satisfied Yes 0

No

!XI STANDARD:

Marks Steps [1] YES,[2] NO, and [3] NO after VERIFING DP is NOT between the two lines on Illustration 6 for step 7.4.3[2].

SAT UNSAT N/A __

COMMENTS: _____

CAUTION JPM NO. 120F REV. NO.2 PAGE 15 of 28 An Engineering Judgment/Review may only be utilized until relationships between core flow, jet pump flow, and Recirculation loop flow have been established following a refueling outage or during the initial weeks of extended single loop operation.

Engineering judgment of the daily surveillance results is used to detect significant abnormalities which could indicate a jet pump failure. (Reference SR 3.4.2.1 bases)

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4.4 Engineering Judgement/Review Criteria

[1]

IF any of the following conditions apply:

STANDARD:

Following Refueling Outage. (See Caution above)

OR The Reactor is in Single Loop Operation (See Caution above)

OR If point(s) plotted in sections 7.4.1, 7.4.2 and 7.4.3 fall outside the bolded lines, to determine if the graphs need updating, THEN PERFORM Attachment 2, Engineering Judgment/Review:

(Otherwise NI A if not required.)

The UNIT has been running for 280 days, Both recirc loops are lIS but Steps 7.4.2[3]

and 7.4.3[3] do not fall within the lines on the graphs, SO this Step should be initialed and Attachment 2 completed.

SAT UNSAT N/A __

COMMENTS: _____

CAUTION JPM NO. 120F REV. NO.2 PAGE 15 of 28 An Engineering Judgment/Review may only be utilized until relationships between core flow, jet pump flow, and Recirculation loop flow have been established following a refueling outage or during the initial weeks of extended single loop operation.

Engineering judgment of the daily surveillance results is used to detect significant abnormalities which could indicate a jet pump failure. (Reference SR 3.4.2.1 bases)

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4.4 Engineering Judgement/Review Criteria

[1]

IF any of the following conditions apply:

STANDARD:

Following Refueling Outage. (See Caution above)

OR The Reactor is in Single Loop Operation (See Caution above)

OR If point(s) plotted in sections 7.4.1, 7.4.2 and 7.4.3 fall outside the bolded lines, to determine if the graphs need updating, THEN PERFORM Attachment 2, Engineering Judgment/Review:

(Otherwise NI A if not required.)

The UNIT has been running for 280 days, Both recirc loops are lIS but Steps 7.4.2[3]

and 7.4.3[3] do not fall within the lines on the graphs, SO this Step should be initialed and Attachment 2 completed.

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 16 of 28 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL Engineering Judgement/Review CAUTION Date:

Engineering Judgment Evaluation may only be utilized until relationships between core flow, jet pump flow, and Recirculation loop flow have been established following a refueling outage or during the initial weeks of extended single loop operation. Engineering judgment of the daily surveillance results is used to detect significant abnormalities which could indicate a jet pump failure. (Reference SR 3.4.2.1 bases}

[1 ]

[2]

[3]

Mark the condition that applies:

Following Refueling Outage.

The Reactor is in Single Loop Operation Point(s) plotted in sections 7.4.1, or 7.4.2 or 7.4.3 fall outside the bolded lines REQUEST System Engineering to perform an Engineering Judgement/Review.

IF the Engineering Judgment/Review was performed following a Refueling Outage or during Single Loop Operation, THEN DETERMINE if the Jet Pump Criteria is satisfied and no significant abnormalities which could indicate a jet pump failure are indicated and RECORD the results below. (Otherwise N/A)

Jet Pump Criteria Satisfied.

Yes 0 No 0

[4]

IF the Engineering Judgment/Review was performed to determine if the graphs needs updated, THEN STANDARD:

REQUEST a System Engineering to: (Otherwise N/A)

A.

SUPPLY Operations with new graphs to Operations Procedures.

B.

RECORD below if Jet Pump Criteria is satisfied.

Jet Pump Criteria Satisfied.

Yes 0 No 0 0

0

[8]

Marks third box on [1] & signs, Signs [2], N/A's [3], and sends to engineering. CUE:

Engineer N/A's 4A and signs 48 after marking NO (See cue - below)

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 16 of 28 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL Engineering Judgement/Review CAUTION Date:

Engineering Judgment Evaluation may only be utilized until relationships between core flow, jet pump flow, and Recirculation loop flow have been established following a refueling outage or during the initial weeks of extended single loop operation. Engineering judgment of the daily surveillance results is used to detect significant abnormalities which could indicate a jet pump failure. (Reference SR 3.4.2.1 bases}

[1 ]

[2]

[3]

Mark the condition that applies:

Following Refueling Outage.

The Reactor is in Single Loop Operation Point(s) plotted in sections 7.4.1, or 7.4.2 or 7.4.3 fall outside the bolded lines REQUEST System Engineering to perform an Engineering Judgement/Review.

IF the Engineering Judgment/Review was performed following a Refueling Outage or during Single Loop Operation, THEN DETERMINE if the Jet Pump Criteria is satisfied and no significant abnormalities which could indicate a jet pump failure are indicated and RECORD the results below. (Otherwise N/A)

Jet Pump Criteria Satisfied.

Yes 0 No 0

[4]

IF the Engineering Judgment/Review was performed to determine if the graphs needs updated, THEN STANDARD:

REQUEST a System Engineering to: (Otherwise N/A)

A.

SUPPLY Operations with new graphs to Operations Procedures.

B.

RECORD below if Jet Pump Criteria is satisfied.

Jet Pump Criteria Satisfied.

Yes 0 No 0 0

0

[8]

Marks third box on [1] & signs, Signs [2], N/A's [3], and sends to engineering. CUE:

Engineer N/A's 4A and signs 48 after marking NO (See cue - below)

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 17 of 28 I CUE: Attachment 2 has come back from Engineering marked NO

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 11,," "':11,,:11:11:11***********

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4.5 Operability Determination

[1]

MARK the appropriate criteria results for the following.

(N/A any criteria not performed.)

Steps Criteria Results Yes No N/A 7.4.1 [3] and 7.4.2[3]

Both Jet Pump Loops 0

[&]

0 steps are marked as YES 7.4.3[3]

Jet Pump DP to criteria is 0

[&]

0 marked as YES.

Engineering Evaluation 0

[&]

0 is marked as YES.

STANDARD:

Marks Steps 7.4.1[3] and 7.4.2[3] NO, Step 7.4.3[3] NO and An 2 NO (after cue).

SAT UNSAT N/A __

COMMENTS: _____

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 11 '" * * * * '" **************************************************

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL

[2]

Using the Criteria Results in Step 7.4.5[1]

VERIFY at least one Criteria Results is satisfied and marked as YES.

STANDARD:

Does Not Sign Off Step 7.4.5[2] (Critical) and Notifies US of Failure (Not Critical)

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 120F REV. NO.2 PAGE 170f28 I CUE: Attachment 2 has come back from Engineering martc:ed NO PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 7.4.5 Operability Determination

[1J MARK the appropriate criteria results for the following.

(N/A any criteria not performed.)

Steps Criteria Results Yes No N/A 7.4.1[3J and 7.4.2[3J Both Jet Pump Loops 0

[lS]

0 steps are marked as YES 7.4.3[3J Jet Pump DP to criteria is 0

[lS]

0 marked as YES.

Engineering Evaluation 0

[lS]

0 is marked as YES.

STANDARD:

Marks Steps 7.4.1 [3J and 7.4.2[3J NO, Step 7.4.3[3J NO and ATT 2 NO (after cue).

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL

[2J Using the Criteria Results in Step 7.4.5[1J VERIFY at least one Criteria Results is satisfied and marked as YES.

STANDARD:

Does Not Sign Off Step 7.4.5[2J (Critical) and Notifies US of Failure (Not Critical)

SAT UNSAT N/A __

COMMENTS: _____ _

I

JPM NO. 120F REV. NO.2 PAGE 18 of 28 PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

7.5 Completion and Notifications

[1]

IF an Engineering Judgment/Review was performed, THEN VERIFY the Engineering Judgment/Review documentation is attached to this SR. (Otherwise N/A)

[2]

COMPLETE Attachment 1, Surveillance Procedure Review Form, up to Unit Supervisor review.

[3]

NOTIFY the Unit Supervisor that this test is complete.

STANDARD:

N/A SAT UNSAT N/A __

COMMENTS: _____

I CUE: That completes this task.

I JPM NO. 120F REV. NO.

2 PAGE 18 of 28 PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

7.5 Completion and Notifications

[1]

IF an Engineering Judgment/Review was performed, THEN VERIFY the Engineering Judgment/Review documentation is attached to this SR. (Otherwise N/A)

[2]

COMPLETE Attachment 1, Surveillance Procedure Review Form, up to Unit Supervisor review.

[3]

NOTIFY the Unit Supervisor that this test is complete.

STANDARD:

N/A SAT UNSAT N/A __

COMMENTS: _____

I CUE: That complete. this task.

JPM NO. 120F REV. NO.2 PAGE 19 of 28 PERFORMANCE STEP:

CRITICAL NOT CRITICAL PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

x SAT UNSAT N/A __

COMMENTS: _____

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A A A A A AA A******************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A __

COMMENTS: _____

END OF TASK STOP TIME: _____

JPM NO. 120F REV. NO.2 PAGE 19 of 28 PERFORMANCE STEP:

CRITICAL NOT CRITICAL PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

x SAT UNSAT N/A __

COMMENTS: _____

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A A A A A AA A******************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A __

COMMENTS: _____

END OF TASK STOP TIME: _____

JPM NO. 120F REV. NO. 2 PAGE 26 of 28 Examiner Copy - Do NOT give to Candidate Items in BOLD are out of bounds and result in failure of the SR Point CALC002 3456 CMWT 2-XR-68-50 CORE PRESSURE DROP (Green pen) 14.4 PSID 2-SI-68-59 RECIRC PUMP 2A MOTOR SPEED 1313 RPM 2-SI-68-71 RECIRC PUMP 28 MOTOR SPEED 1313 RPM 2*FI*68*5 RECIRC PUMP 2A DISCHARGE FLOW 45.0 gpm x 1000 2*FI*68*81 RECIRC PUMP 28 DISCHARGE FLOW 44.0 gpm X 1000 2-FI-68-46 RECIRC LOOP 2A JET PUMP FLOW 45 Mlb/hr 2-FI-68-48 RECIRC LOOP 28 JET PUMP FLOW 44 Mlb/hr 2-XR-68-50 TOTAL CORE FLOW (Red pen) 87.0 Mlb/hr 2-PDI-68-38 JET PUMP 11 LOOP2A 9.0 PSID 2-PDI-68-39 JET PUMP 12 LOOP2A 9.0 PSID 2-PDI-68-40 JET PUMP 13 LOOP2A 9.5 PSID 2-PDI-68-42 JET PUMP 14 LOOP2A 9.0 PSID 2-PDI-68-43 JET PUMP 15 LOOP 2A 8.5 PSID 2-PDI-68-07 JET PUMP 16 LOOP 2A 9.0 PSID 2-PDI-68-08 JET PUMP 17 LOOP2A 9.0 PSID 2-PDI-68-10 JET PUMP 18 LOOP2A 9.5 PSID 2-PDI-68-11 JET PUMP 19 LOOP2A 8.5 PSID 2-PDI-68-13 JET PUMP 20 LOOP2A 9.5 PSID 2-PDI-68-15 JET PUMP 1 LOOP 2B 9.0 PSID 2-PDI-68-18 JET PUMP 2 LOOP 2B 9.5 PSID 2-PDI-68-19 JET PUMP 3 LOOP 2B 9.0 PSID 2-PDI-68-21 JET PUMP 4 LOOP 2B 9.5 PSID 2*PDI*68*22 JET PUMP 5 LOOP2B 10.0 PSID 2-PDI-68-25 JET PUMP 6 LOOP 2B 9.5 PSID 2*PDI*68*26 JET PUMP 7 LOOP2B 10.0 PSID 2*PDI*68*28 JET PUMP 8 LOOP2B 10.5 PSID 2-PDI-68-29 JET PUMP 9 LOOP 2B 9.5 PSID 2-PDI-68-30 JET PUMP 10 LOOP 2B 9.5 PSID JPM NO. 120F REV. NO. 2 PAGE 26 of 28 Examiner Copy - Do NOT give to Candidate Items in BOLD are out of bounds and result in failure of the SR Point CALC002 3456 CMWT 2-XR-68-50 CORE PRESSURE DROP (Green pen) 14.4 PSID 2-SI-68-59 RECIRC PUMP 2A MOTOR SPEED 1313 RPM 2-SI-68-71 RECIRC PUMP 28 MOTOR SPEED 1313 RPM 2*FI*68*5 RECIRC PUMP 2A DISCHARGE FLOW 45.0 gpm x 1000 2*FI*68*81 RECIRC PUMP 28 DISCHARGE FLOW 44.0 gpm X 1000 2-FI-68-46 RECIRC LOOP 2A JET PUMP FLOW 45 Mlb/hr 2-FI-68-48 RECIRC LOOP 28 JET PUMP FLOW 44 Mlb/hr 2-XR-68-50 TOTAL CORE FLOW (Red pen) 87.0 Mlb/hr 2-PDI-68-38 JET PUMP 11 LOOP2A 9.0 PSID 2-PDI-68-39 JET PUMP 12 LOOP2A 9.0 PSID 2-PDI-68-40 JET PUMP 13 LOOP2A 9.5 PSID 2-PDI-68-42 JET PUMP 14 LOOP2A 9.0 PSID 2-PDI-68-43 JET PUMP 15 LOOP 2A 8.5 PSID 2-PDI-68-07 JET PUMP 16 LOOP 2A 9.0 PSID 2-PDI-68-08 JET PUMP 17 LOOP2A 9.0 PSID 2-PDI-68-10 JET PUMP 18 LOOP2A 9.5 PSID 2-PDI-68-11 JET PUMP 19 LOOP2A 8.5 PSID 2-PDI-68-13 JET PUMP 20 LOOP2A 9.5 PSID 2-PDI-68-15 JET PUMP 1 LOOP 2B 9.0 PSID 2-PDI-68-18 JET PUMP 2 LOOP 2B 9.5 PSID 2-PDI-68-19 JET PUMP 3 LOOP 2B 9.0 PSID 2-PDI-68-21 JET PUMP 4 LOOP 2B 9.5 PSID 2*PDI*68*22 JET PUMP 5 LOOP2B 10.0 PSID 2-PDI-68-25 JET PUMP 6 LOOP 2B 9.5 PSID 2*PDI*68*26 JET PUMP 7 LOOP2B 10.0 PSID 2*PDI*68*28 JET PUMP 8 LOOP2B 10.5 PSID 2-PDI-68-29 JET PUMP 9 LOOP 2B 9.5 PSID 2-PDI-68-30 JET PUMP 10 LOOP 2B 9.5 PSID

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 27 of 28 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit 2 Operator. Unit 2 is operating at 100% power for 280 Days on line,. 2-SR-3.4.2.1, Jet Pump Mismatch and Operability, is in progress and complete up to Step 7.2[1]. Candidate should contact Examiner for any necessary feedback or info and or to indicate task completion.

INITIATING CUES:

The Unit Supervisor directs you to continue with 2-SR-3.4.2.1. starting with Step 7.2[1].

BROWNS FERRY NUCLEAR PlANT JOB PERFORMANCE MEASURE PAGE 27 of28 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

• • • • • • • • • • • • • • • • • • • A.All****************************************************************************

INITIAL CONDITIONS:

You are a Unit 2 Operator. Unit 2 is operating at 100% power for 280 Days on line,. 2-SR-3.4.2.1, Jet Pump Mismatch and Operability, is in progress and complete up to Step 7.2[1]. Candidate should contact Examiner for any necessary feedback or info and or to indicate task completion.

INITIATING CUES:

The Unit Supervisor directs you to continue with 2-SR-3.4.2.1. starting with Step 7.2[1].

PAGE 28 of28 Candidate Copy Data Sheet Point CALC002 3456 CMWT 2-XR-68-50 CORE PRESSURE DROP (Green pen) 14.4 PSID 2-SI-68-59 RECIRC PUMP 2A MOTOR SPEED 1313 RPM 2-SI-68-71 RECIRC PUMP 2B MOTOR SPEED 1313 RPM 2-FI-68-5 RECIRC PUMP 2A DISCHARGE FLOW 45.0 gpm x 1000 2-FI-68-81 RECIRC PUMP 2B DISCHARGE FLOW 44.0 gpm X 1000 2-FI-68-46 RECIRC LOOP 2A JET PUMP FLOW 45 Mlb/hr 2-FI-68-48 RECIRC LOOP 2B JET PUMP FLOW 44 Mlb/hr 2-XR-68-50 TOTAL CORE FLOW (Red pen) 87.0 Mlb/hr 2-PDI-68-38 JET PUMP 11 LOOP2A 9.0 PSID 2-PDI-68-39 JET PUMP 12 LOOP2A 9.0 PSID 2-PDI-68-40 JET PUMP 13 LOOP2A 9.5 PSID 2-PDI-68-42 JET PUMP 14 LOOP2A 9.0 PSID 2-PDI-68-43 JET PUMP 15 LOOP2A 8.5 PSID 2-PDI-68-07 JET PUMP 16 LOOP2A 9.0 PSID 2-PDI-68-08 JET PUMP 17 LOOP2A 9.0 PSID 2-PDI-68-10 JET PUMP 18 LOOP2A 9.5 PSID 2-PDI-68-11 JET PUMP 19 LOOP2A 8.5 PSID 2-PDI-68-13 JET PUMP 20 LOOP2A 9.5 PSID 2-PDI-68-15 JET PUMP 1 LOOP 2B 9.0 PSID 2-PDI-68-18 JET PUMP 2 LOOP 2B 9.5 PSID 2-PDI-68-19 JET PUMP 3 LOOP 2B 9.0 PSID 2-PDI-68-21 JET PUMP 4 LOOP 2B 9.5 PSID 2-PDI-68-22 JET PUMP 5 LOOP2B 10.0 PSID 2-PDI-68-25 JET PUMP 6 LOOP2B 9.5 PSID 2-PDI-68-26 JET PUMP 7 LOOP2B 10.0 PSID 2-PDI-68-28 JET PUMP 8 LOOP2B 10.5 PSID 2-PDI-68-29 JET PUMP 9 LOOP 2B 9.5 PSID 2-PDI-68-30 JET PUMP 10 LOOP 2B 9.5 PSID PAGE 28 of28 Candidate Copy Data Sheet Point CALC002 3456 CMWT 2-XR-68-50 CORE PRESSURE DROP (Green pen) 14.4 PSID 2-SI-68-59 RECIRC PUMP 2A MOTOR SPEED 1313 RPM 2-SI-68-71 RECIRC PUMP 2B MOTOR SPEED 1313 RPM 2-FI-68-5 RECIRC PUMP 2A DISCHARGE FLOW 45.0 gpm x 1000 2-FI-68-81 RECIRC PUMP 2B DISCHARGE FLOW 44.0 gpm X 1000 2-FI-68-46 RECIRC LOOP 2A JET PUMP FLOW 45 Mlb/hr 2-FI-68-48 RECIRC LOOP 2B JET PUMP FLOW 44 Mlb/hr 2-XR-68-50 TOTAL CORE FLOW (Red pen) 87.0 Mlb/hr 2-PDI-68-38 JET PUMP 11 LOOP2A 9.0 PSID 2-PDI-68-39 JET PUMP 12 LOOP2A 9.0 PSID 2-PDI-68-40 JET PUMP 13 LOOP2A 9.5 PSID 2-PDI-68-42 JET PUMP 14 LOOP2A 9.0 PSID 2-PDI-68-43 JET PUMP 15 LOOP2A 8.5 PSID 2-PDI-68-07 JET PUMP 16 LOOP2A 9.0 PSID 2-PDI-68-08 JET PUMP 17 LOOP2A 9.0 PSID 2-PDI-68-10 JET PUMP 18 LOOP2A 9.5 PSID 2-PDI-68-11 JET PUMP 19 LOOP2A 8.5 PSID 2-PDI-68-13 JET PUMP 20 LOOP2A 9.5 PSID 2-PDI-68-15 JET PUMP 1 LOOP 2B 9.0 PSID 2-PDI-68-18 JET PUMP 2 LOOP 2B 9.5 PSID 2-PDI-68-19 JET PUMP 3 LOOP 2B 9.0 PSID 2-PDI-68-21 JET PUMP 4 LOOP 2B 9.5 PSID 2-PDI-68-22 JET PUMP 5 LOOP2B 10.0 PSID 2-PDI-68-25 JET PUMP 6 LOOP2B 9.5 PSID 2-PDI-68-26 JET PUMP 7 LOOP2B 10.0 PSID 2-PDI-68-28 JET PUMP 8 LOOP2B 10.5 PSID 2-PDI-68-29 JET PUMP 9 LOOP 2B 9.5 PSID 2-PDI-68-30 JET PUMP 10 LOOP 2B 9.5 PSID

JPM NUMBER:

TITLE:

528 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 1 of7 As a volunteer to accept an emergency exposure, complete Appendix B of EPIP-15, determine stay time, and determine the approving authority.

PROVIDE CANDIDATE WITH A COPY OF: EPIP-15 SUBMITTED BY:

DATE: ____ _

VALIDATED BY:

DATE: ____ _

APPROVED BY:

DATE: ____ _

TRAINING PLANTCONCURRENCE: ___________________ _

DATE: ____ _

OPERATIONS Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence JPM NUMBER:

TITLE:

528 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 1 of 7 As a volunteer to accept an emergency exposure, complete Appendix B of EPIP-15, determine stay time, and determine the approving authority.

PROVIDE CANDIDATE WITH A COPY OF: EPIP-15 SUBMITIED BY:

DATE: ______ __

VALIDATED BY:

DATE:. _____ _

APPROVED BY:

DATE :. _____ _

TRAINING PlANTCONCURRENCE: ____ ~~~~~------

OPERATIONS DATE: _____ _

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

Revision Effective Number Date 0

05/01/09 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue PAGE 2 of 7 Revision Effective Number Date 0

05/01 /09 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue PAGE 2 of 7

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 3 of 7 OPERATOR: ______________________________________________ __

RO JPM NUMBER:

TASK TITLE:

KIA NUMBER:

SRO DATE: ____________ _

528 As a volunteer to accept an emergency exposure, complete Appendix B of EPIP-15, determine stay time, and determine the approving authority.

2.3.4 KIA RATING:

RO 3.2 SRO 3.7

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • 11 II II II'" "'*******************************************************

TASK STANDARD: As a volunteer to accept an emergency exposure, complete Appendix B of EPIP-15, determine stay time, and determine the approving authority.

PERFORMANCE LOCATION:

CLASSROOM :_--:;;..;X'---_

REFERENCES/PROCEDURES NEEDED:

EPIP-15 Rev (If asked for)

VALIDATION TIME:

CLASSROOM: ___

MAX. TIME ALLOWED: ____ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS A IT ACHED?

YES __ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________ DATE: _____

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 3 of 7 OPERATOR: __________________________________________ __

RO JPM NUMBER:

TASK TITLE:

KJA NUMBER:

SRO DATE: __________ __

528 As a volunteer to accept an emergency exposure, complete Appendix B of EPIP-15, determine stay time, and determine the approving authority.

2.3.4 KJA RATING:

RO 3.2 SRO 3.7 TASK STANDARD: As a volunteer to accept an emergency exposure, complete Appendix B of EPIP-15, determine stay time, and determine the approving authority.

PERFORMANCE LOCATION:

CLASSROOM: __ -"X,--_

REFERENCES/PROCEDURES NEEDED:

EPIP-15 Rev (If asked for)

VALIDATION TIME:

CLASSROOM: ______ _

MAX. TIME ALLOWED:

________ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED?

YES ____ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ___________________ DATE: __________ __

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 4 of 7 Classroom INITIAL CONDITIONS

1. Unit 2 LOCA inside containment with fuel failure

2. Emergency Dose Limits for Protection of Valuable Property are in effect

3. Dose rate in affected area is 25 Rlhr (assume No dose incurred while traveling to and from work location)

4. You have received 500 mR TEDE this year

5. The Tech Support Center HAS NOT been staffed The following tasks are required to be performed:

TASK 1

Determine allowed stay time to operate equipment in a constant 25 Rlhr field (assume No dose incurred while traveling to and from work location) 2 Complete Appendix 8 of EPIP-15 3

Determine who has the authority to approve the emergency exposure INITIATING CUES:

Refer to the above information.

1.

How long do You have to complete task without exceeding his Emergency Dose Limits

2.

Complete Appendix 8 of EPIP-15

3.

Under the current conditions, who has the authority to approve the emergency exposure?

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 4 of 7

• • • • • • • • • '***************** A

• At 1******** __ ** ___ *** __ ***** ___ **** __ ***********************

Classroom INITIAL CONDITIONS

1. Unit 2 LOCA inside containment with fuel failure

2. Emergency Dose Limits for Protection of Valuable Property are in effect

3. Dose rate in affected area is 25 Rlhr (assume No dose incurred while traveling to and from work location)

4. You have received 500 mR TEDE this year

5. The Tech Support Center HAS NOT been slaffed The following tasks are required to be perfonmed:

TASK 1

Determine allowed stay time to operate equipment in a constant 25 Rlhr field (assume No dose incurred while traveling to and from work location) 2 Complete Appendix B of EPIP-15 3

Determine who has the authority to approve the emergency exposure INITIATING CUES:

Refer to the above infonmation.

1.

How long do You have to complete task without exceeding his Emergency Dose Limits

2.

Complete Appendix B of EPIP-15

3.

Under the current conditions, who has the authOrity to approve the emergency exposure?

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EXAMINER'S KEY PAGE50f7 Classroom INITIAL CONDITIONS

1. Unit 2 LOCA inside containment with fuel failure

2. Emergency Dose Limits for Protection of Valuable Property are in effect

3. Dose rate in affected area is 25 Rlhr (assume No dose incurred while traveling to and from work location)

4. You have received 500 mR TEDE this year

5. The Tech Support Center HAS NOT been staffed The following tasks are required to be performed:

TASK 1

Determine allowed stay time to operate equipment in a constant 25 Rlhr field (assume No dose incurred while traveling to and from work location) 2 Complete Appendix 8 of EPIP-15 3

Determine who has the authority to approve the emergency exposure INITIATING CUES:

Refer to the above information.

1.

How long do You have to complete task without exceeding his Emergency Dose Limits

2.

Complete Appendix 8 of EPIP-15

3.

Under the current conditions, who has the authority to approve the emergency exposure?

Classroom INITIAL CONDITIONS BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EXAMINER'S KEY

1. Unit 2 LOCA inside containment with fuel failure PAGE 50f7

2. Emergency Dose Limits for Protection of Valuable Property are in effect

3. Dose rate in affected area is 25 R1hr (assume No dose incurred while traveling to and from work location)

4. You have received 500 mR TEDE this year

5. The Tech Support Center HAS NOT been staffed The following tasks are required to be performed:

TASK 1

Determine allowed stay time to operate equipment in a constant 25 R1hr field (assume No dose incurred while traveling to and from work location) 2 Complete Appendix B of EPIP-15 3

Determine who has the authority to approve the emergency exposure INITIATING CUES:

Refer to the above information.

1.

How long do You have to complete task without exceeding his Emergency Dose Limits

2.

Complete Appendix B of EPIP-15

3.

Under the current conditions, who has the authority to approve the emergency exposure?

STEP 1:

EXAMINER KEY (Do NOT give to Candidate)

Determine allowable dose remaining for Protection of Valuable Property activities.

STANDARD: Determine allowable dose remaining after subtracting the to-date annual accrued dose.

COMMENTS:

STEP 2:

10R-.5R = 9.5 R Determine time available for the AUO to complete task without exceeding allowable dose limit.

STANDARD: Stay time is calculated to be:

Available Dose =

9.5 R Dose Rate = 25 Rlhr 9.5 Rl25 Rlhr = 0.38 hr (0.38 hr X 60 min/1 hr = 22.8 minutes)

(+/- 1 minute)

Examiner note: If candidate does not subtract his/her to-date annual accrued dose of.5 R, they will come up with 24 minutes which is UNSAT COMMENTS:

With the TSC NOT staffed, the authority to approve the emergency exposure lies with the Shift Manager (SED)

PAGE 6 of?

CRITICAL STEP

_SAT

_UNSAT CRITICAL STEP SAT

_UNSAT STEP 1:

EXAMINER KEY (Do NOT give to Candidate)

Determine allowable dose remaining for Protection of Valuable Property activities.

STANDARD: Determine allowable dose remaining after subtracting the to-date annual accrued dose.

COMMENTS:

STEP 2:

10R-.5R = 9.5 R Determine time available for the AUO to complete task without exceeding allowable dose limit.

STANDARD: Stay time is calculated to be:

Available Dose =

9.5 R Dose Rate = 25 Rlhr 9.5 Rl25 Rlhr = 0.38 hr (0.38 hr X 60 min/1 hr = 22.8 minutes)

(+/- 1 minute)

Examiner note: If candidate does not subtract his/her to-date annual accrued dose of.5 R, they will come up with 24 minutes which is UNSAT COMMENTS:

With the TSC NOT staffed, the authority to approve the emergency exposure lies with the Shift Manager (SED)

PAGE 6 of?

CRITICAL STEP

_SAT

_UNSAT CRITICAL STEP SAT

_UNSAT

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 7 of 7 Classroom STUDENT HANDOUT INITIAL CONDITIONS 1.

Unit 2 LOCA inside containment with fuel failure

2.

Emergency Dose Limits for Protection of Valuable Property are in effect

3.

Dose rate in affected area is 25 Rlhr (assume No dose incurred while traveling to and from work location)

4.

You have received 500 mR TEDE this year

5.

The Tech Support Center HAS NOT been staffed The following tasks are required to be performed:

TASK 1

Determine allowed stay time to operate equipment in a constant 25 Rlhr field (assume No dose incurred while traveling to and from work location) 2 Complete Appendix B of EPIP-15 3

Determine who has the authority to approve the emergency exposure INITIATING CUES:

Refer to the above information.

1.

How long do You have to complete task without exceeding his Emergency Dose Limits

2.

Complete Appendix B of EPIP-15

3.

Under the current conditions, who has the authority to approve the emergency exposure?

Classroom BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 70f7 STUDENT HANDOUT INITIAL CONDITIONS

1.

Unit 2 LOCA inside containment with fuel failure

2.

Emergency Dose Limits for Protection of Valuable Property are in effect

3.

Dose rate in affected area is 25 Rlhr (assume No dose incurred while traveling to and from work location)

4.

You have received 500 mR TEDE this year

5.

The Tech Support Center HAS NOT been staffed The following tasks are required to be perfonned:

TASK 1

Detennine allowed stay time to operate equipment in a constant 25 Rlhr field (assume No dose incurred while traveling to and from work location) 2 Complete Appendix B of EPIP-15 3

Determine who has the authority to approve the emergency exposure INITIATING CUES:

Refer to the above infonnation.

1.

How long do You have to complete task without exceeding his Emergency Dose Limits

2.

Complete Appendix B of EPIP-15

3.

Under the current conditions, who has the authority to approve the emergency exposure?

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 487TC REV. NO. 0 PAGE 1 of 21 JPM NUMBER:

487TC TITLE:

CLASSIFY THE EVENT PER THE REP (SAE - PRIMARY SYS.

LEAKAGE (Suppression Chamber Pressure) EXCEEDING PSP CURVE) ON UNIT 3 TASK NUMBER:

S-OOO-EM-21 (SRO ONLY)

SUBMITIED BY:

DATE: ___

VALIDATED BY:

DATE: ___

APPROVED BY:

DATE: ___

TRAINING PLANTCONCURRENCE: ____________________ _

DATE: _______ _

OPERATIONS Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER:

487TC JPM NO. 487TC REV. NO. 0 PAGE 1 of 21 TITLE:

CLASSIFY THE EVENT PER THE REP (SAE - PRIMARY SYS.

LEAKAGE (Suppression Chamber Pressure) EXCEEDING PSP CURVE) ON UNIT 3 TASK NUMBER:

S-OOO-EM-21 (SRO ONLY)

SUBMITTED BY:

DATE: ___

VALIDATED BY:

DATE: ___

APPROVED BY:

DATE: ___

TRAINING PLANT CONCURRENCE: ---==-:=:-::-:-0::----

OPERATIONS DATE: ___

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

Revision Effective Number Date 0

03/16/09 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue JPM NO. 487TC REV. NO. 0 PAGE 2 of21 Revision Effective Number Date 0

03/16/09 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Pages Description Affected Of Revision All Initial issue JPM NO. 487TC REV. NO. 0 PAGE 2 of 21

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 487TC REV. NO. 0 PAGE 3 of21 OPERATOR: ________________________________________ ___

RO SRO DATE: __________ _

JPM NUMBER:

487TC TASK NUMBER:

S-000-EM-21 (SRO ONLY)

TASK TITLE:

CLASSIFY THE EVENT PER THE REP (SAE - PRIMARY SYS.

KIA NUMBER:

LEAKAGE (Suppression Chamber Pressure) EXCEEDING PSP CURVE) ON UNIT 3 2.4.38 KIA RATING:

RO 2.2 SRO 4.0 TASK STANDARD: CLASSIFY THE EVENT AS AN SAE (2.1-S) AND PERFORM ACTIONS OF EPIP 4. BASED ON EXCEEDING PSP CURVE.

MAKE NOTIFICATIONS SUCH THAT; (TIME ODS NOTIFIED)-

(TIME DECLARED) S 5 MINUTES and (TIME NRC NOTIFIED)-

(TIME DECLARED) S 60 MINUTES PERFORMANCE LOCATION:

SIMULATOR X PLANT _

CONTROL ROOM_

REFERENCES/PROCEDURES NEEDED:

EPIP-1, REV 44, EPIP-4, REV 31 VALIDATION TIME:

SIMULATOR:

20 min LOCAL: ______ __

MAX. TIME ALLOWED:

__..;;;.5,-=/6-,,-0 ___ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS A IT ACHED?

YES ____ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _______________ DATE: ________ _

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 487TC REV. NO. 0 PAGE 3 0121 OPERATOR: ____________________________________________ __

RO SRO DATE: ______ _

JPM NUMBER:

487TC TASK NUMBER:

S-000-EM-21 (SRO ONLY)

TASK TITLE:

CLASSIFY THE EVENT PER THE REP (SAE - PRIMARY SYS.

KIA NUMBER:

LEAKAGE (Suppression Chamber Pressure) EXCEEDING PSP CURVE) ON UNIT 3 2.4.38 KIA RATING:

RO 2.2 SRO 4.0 TASK STANDARD: CLASSIFY THE EVENT AS AN SAE (2.1-S) AND PERFORM ACTIONS OF EPIP 4. BASED ON EXCEEDING PSP CURVE.

MAKE NOTIFICATIONS SUCH THAT: (TIME ODS NOTIFIED)-

(TIME DECLARED)" 5 MINUTES and (TIME NRC NOTIFIED)-

(TIME DECLARED) S 60 MINUTES PERFORMANCE LOCATION:

SIMULATOR X PLANT __ CONTROL ROOM __

REFERENCES/PROCEDURES NEEDED:

EPIP-1, REV 44, EPIP-4, REV 31 VALIDATION TIME:

SIMULATOR:

20 min LOCAL: ____ _

MAX. TIME ALLOWED:

__ -"5",,/6,,,0 __ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED?

YES ___ NO RESULTS:

SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________ DATE: ______ __

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 487TC REV. NO. 0 PAGE 4 of 21 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are the Shift Manager. Unit 3 was operating at 100%

(BOL) when the Unit 3 US received a call from the Security Chief of a tornado warning in the vicinity of Browns Ferry. The Unit 2 Supervisor has implemented 0-AOI-100-7 Tornado. A few minutes later the plant lost "All Offsite Power" due to the tornado hitting the switchyard. 0-AOI-57-1A is in progress due to the loss of All Offsite Power. 480V Shutdown Board 3B has also been lost due to overcurrent conditions. EOI-1 and 2 are in progress due an unidentified leak in the Orywell causing High Orywell pressure that is trending upwards. The Operators are venting the Torus per EOI-2. (Unit 1 and 2 also scrammed from 100% power and are responding normally.)

INITIATING CUES:

The Unit 3 US has informed you of the leak in the Orywell and the Loss of "All Offsite Power". MSIV's are closed and SRV's are being utilized to maintain reactor pressure between 800-1000 psig. Orywell PressurefTemperature and Torus PressurefTemperature are trending upwards. The crew has been unable to get a Orywell or Torus spray system to operate. Using the following parameters provided to you by the control room operating crew, CLASSIFY THE EVENT according to the EPIPs and perform any required actions. The TSC and CECC are not staffed. (NOTE:

Unit 3 conditions are deteriorating.)

Reactor Level Reactor Pressure OW Pressure OW Radiation OW Leakage Rate OW Temperature Torus Temperature Torus Pressure Torus Level Wind Speed Venting Torus

-25 on Emergency Range 885 psig 30 psig and rising (unable to Spray due to multiple valve failures.)

RR-90-256 slowly rising (prior to isolation) unknown at this time 242 0 F and slowly rising 245 0 F 30 psig and rising 15 feet 5 mph from the SW per APP 12 (SOME portions of this JPM are TIME CRITICAL)

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NO. 487TC REV. NO. 0 PAGE 4 of21 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct", (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

• _********_********_** __ ***********_*************_******************** __ ****************All INITIAL CONDITIONS:

You are the Shift Manager. Unit 3 was operating at 100%

(BOL) when the Unit 3 US received a call from the Security Chief of a tornado warning in the vicinity of Browns Ferry. The Unit 2 Supervisor has implemented 0-AOI-100-7 Tornado. A few minutes later the plant lost "All Offsite Power" due to the tomado hitting the switchyard. 0-AOI-57-1A is in progress due to the loss of All Offsite Power. 480V Shutdown Board 3B has also been lost due to overcurrent conditions. EOI-1 and 2 are in progress due an unidentified leak in the Drywell causing High Drywell pressure that is trending upwards. The Operators are venting the Torus per EOI-2. (Unit 1 and 2 also scrammed from 100% power and are responding normally.)

INITIATING CUES:

The Unit 3 US has informed you of the leak in the Drywell and the Loss of "All Offsite Powe~'.

MSIV's are closed and SRV's are being utilized to maintain reactor pressure between 800-1000 psig. Drywell PressurefTemperature and Torus PressurefTemperature are trending upwards. The crew has been unable to get a Drywell or Torus spray system to operate. Using the following parameters provided to you by the control room operating crew, CLASSIFY THE EVENT according to the EPIPs and perform any required actions. The TSC and CECC are not staffed. (NOTE:

Unit 3 conditions are deteriorating.)

Reactor Level Reactor Pressure DW Pressure DW Radiation DW Leakage Rate DW Temperature Torus Temperature Torus Pressure Torus Level Wind Speed Venting Torus

-25 on Emergency Range 885 psig 30 pSig and rising (unable to Spray due to multiple valve failures.)

RR-90-256 slowly rising (prior to isolation) unknown at this time 242 0 F and slowly rising 245 0 F 30 psig and rising 15 feet 5 mph from the SW per APP 12 (SOME portions of this JPM are TIME CRITICAL)

START TIME _____

JPM NO. 487TC REV. NO. 0 PAGE 50f21 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL Refers to EPIP-1 to classify the emergency event STANDARD:

SRO/SED refers to EPIP 1, Section 2.1, Primary Containment Pressure and declares an SAE (2.1-S) based on being unable to maintain Suppression Chamber Pressure in the safe area of Curve 2.1-S.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL Implements EPIP-4, SITE AREA EMERGENCY STANDARD:

SRO/SED recognizes/implements an SAE per EPIP-4.

SAT UNSAT N/A __

COMMENTS: _____

START TIME _____

JPM NO. 487TC REV. NO. 0 PAGE 50f21 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL Refers to EPIP-1 to classify the emergency event STANDARD:

SRO/SED refers to EPIP 1, Section 2.1, Primary Containment Pressure and declares an SAE (2.1-S) based on being unable to maintain Suppression Chamber Pressure in the safe area of Curve 2.1-S.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL Implements EPIP-4, SITE AREA EMERGENCY STANDARD:

SRO/SED recognizes/implements an SAE per EPIP-4.

SAT UNSAT N/A __

COMMENTS: _____

BROWNS FERRY SITE AREA EMERGENCY 3.0 EMERGENCY CLASSIFICATION ACTIONS JPM NO. 487TC REV. NO. 0 PAGE 6 of21 EPIP-4 This section of the procedure is utilized for actions to be taken when the initial Site Area Emergency classification is originating from the Control Room. If the Technical Support Center is operational, utilize the instructions found in Appendix E of this procedure for actions to be taken upon the Site Area Emergency classification being declared.

3.1 Activation of the Emergency Response Organization (ERO)

CAUTION Ongoing or anticipated security events may present a danger to normal staffing of the Emergency Response Organization. Select the "Staging Area" option when events are ongoing or anticipated that may present a danger to normal ERO staffing as determined by the SED and/or Nuclear Security.

NOTE Normally Appendix B, "Unit Operator Notifications", is conducted by a Unit 1, Unit Operator, Depending upon the affected unit, this action may be delegated to a Unit Operator on an unaffected unit.

BROWNS FERRY SITE AREA EMERGENCY 3.0 EMERGENCY CLASSIFICATION ACTIONS JPM NO. 487TC REV. NO. 0 PAGE 6 of21 EPIP-4 This section of the procedure is utilized for actions to be taken when the initial Site Area Emergency classification is originating from the Control Room. If the Technical Support Center is operational, utilize the instructions found in Appendix E of this procedure for actions to be taken upon the Site Area Emergency classification being declared.

3.1 Activation of the Emergency Response Organization (ERO)

CAUTION Ongoing or anticipated security events may present a danger to normal staffing of the Emergency Response Organization. Select the "Staging Area" option when events are ongoing or anticipated that may present a danger to normal ERO staffing as determined by the SED and/or Nuclear Security.

NOTE Normally Appendix B, "Unit Operator Notifications", is conducted by a Unit 1, Unit Operator, Depending upon the affected unit, this action may be delegated to a Unit Operator on an unaffected unit.

JPM NO. 487TC REV. NO. 0 PAGE 7 of 21 TIME EVENT DECLARED ___

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL STANDARD:

3.1.1 NOTIFY... a Unit Operator of the Site Area Emergency Classification, AND 3.1.2 DIRECT... the Unit Operator to implement Appendix B, activating the paging system using option; DRILL EMERGENCY STAGING AREA (See caution note above)

DIRECTS Unit Operator to make notifications per Appendix B.

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 487TC REV. NO. 0 PAGE 7 of 21 TIME EVENT DECLARED ___

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL STANDARD:

3.1.1 NOTIFY... a Unit Operator of the Site Area Emergency Classification, AND 3.1.2 DIRECT... the Unit Operator to implement Appendix B, activating the paging system using option; DRILL EMERGENCY STAGING AREA (See caution note above)

DIRECTS Unit Operator to make notifications per Appendix B.

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 487TC REV. NO. 0 PAGE 8 of 21 r

CUE: NUCLEAR SECURITY INFORMS YOU THAT THE TORNADO WHICH

.JI I DAMAGED THE SWITCHYARD HAS PASSED THROUGH AND THE WEATHER IS I NOW CLEAR.

3.2 Operations Duty Specialist (ODS) Notification / State of Alabama Notification Note The ODS should be notified within 5 minutes after the emer ency has been declared.

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 3.2.1 Complete Appendix A (Initial Notification Form)

STANDARD:

APPENDIX A is complete with EAL Designator 2.1-S SAE status. Unidentified leak in Unit 3 Drywell with level at -25 on the Emergency Range, reactor pressure 885 psig, OW pressure 30 psig and slowly rising, OW temperature 242°F and slowly rising, Torus Temperature 245°F and Torus Pressure 30 psig with a Torus Level of 15 feet. EOI 1 and 2 are in progress. Venting the TORUS per EOI-2 is also in progress. Unit 3 conditions are deteriorating. Wind speed is 5 mph from the SW. (Classification of event is critical, description is not.)

SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 487TC REV. NO. 0 PAGE 8 of 21 CUE: NUCLEAR SECURITY INFORMS YOU THAT THE TORNADO WHICH DAMAGED THE SWITCHYARD HAS PASSED THROUGH AND THE WEATHER IS NOW CLEAR.

3.2 Operations Duty Specialist (ODS) Notification I State of Alabama Notification Note The ODS should be notified within 5 minutes after the emergency has been declared.

PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 3.2.1 Complete Appendix A (Initial Notification Form)

STANDARD:

APPENDIX A is complete with EAL Designator 2.1-S SAE status. Unidentified leak in Unit 3 Drywell with level at -25 on the Emergency Range, reactor pressure 885 psig, OW pressure 30 psig and slowly rising, OW temperature 242'F and slowly rising, Torus Temperature 245°F and Torus Pressure 30 psig with a Torus Level of 15 feet. EOl1 and 2 are in progress. Venting the TORUS per EOI-2 is also in progress. Unit 3 conditions are deteriorating. Wind speed is 5 mph from the SW. (Classification of event is critical, description is not.)

SAT UNSAT N/A __

COMMENTS :. ______ _

JPM NO. 487TC REV. NO. 0 PAGE 9 of 21 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 3.2.2 NOTIFY... the ODS, utilizing the "Direct Ring-Down" telephone or at extension 5-751-1700 or 5-751-2495.

AND REPORT... to the ODS the information recorded on Appendix A.

AND FAX... a copy of Appendix A to the ODS for confirmation of information at 5-751-8620.

I CUE: Faxing to the ODS will be simulated STANDARD:

NOTIFIES the ODS within 5 minutes and provides the information from Appendix A and Faxes a copy of Appendix A. (Only the notification within 5 minutes is critical)

SAT UNSAT N/A __

COMMENTS: _____

RECORD TIME ODS NOTIFIED _____

JPM NO. 487TC REV. NO. 0 PAGE 9 of21 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 3.2.2 NOTIFY... the ODS, utilizing the "Direct Ring-Down" telephone or at extension 5-751-1700 or 5-751-2495, AND REPORT... to the ODS the information recorded on Appendix A.

AND FAX... a copy of Appendix A to the ODS for confirmation of information at 5-751-8620.

I CUE: Faxing to the ODS will be simulated STANDARD:

NOTIFIES the ODS within 5 minutes and provides the information from Appendix A and Faxes a copy of Appendix A. (Only the notification within 5 minutes is critical)

SAT UNSAT N/A __

COMMENTS: _____

RECORD TIME ODS NOTIFIED _____

JPM NO. 487TC REV. NO. 0 PAGE 10 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL STANDARD:

3.2.3 IF... the ODS was contacted, THEN... the State of Alabama notification action is complete.

AND RE-ENTER at Step 3.3. Otherwise continue.

Continues to step 3.3.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 487TC REV. NO. 0 PAGE 10 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL STANDARD:

3.2.3 IF... the ODS was contacted, THEN... the State of Alabama notification action is complete.

AND RE-ENTER at Step 3.3. Otherwise continue.

Continues to step 3.3.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 487TC REV. NO. 0 PAGE 11 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL NOTE The State of Alabama shall be contacted within 15 minutes of the emergency classification.

STANDARD:

3.2.4 IF... the ODS cannot be contacted within 1 0 minutes, THEN... NOTIFY the State of Alabama at:

24 Hours Primary: 9-1-205-280-2310 Backup: 9-1-800-843-0699 Backup: 9-1-334-324-0076 AND REPORT... the information recorded on Appendix A.

AND FAX... a copy of Appendix A to the State of Alabama for confirmation of information at 9-1-205-280-2495.

N/A - ODS was contacted.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 487TC REV. NO. 0 PAGE 11 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL NOTE The State of Alabama shall be contacted within 15 minutes of the emergency classification.

STANDARD:

3.2.4 IF... the ODS cannot be contacted within 1 0 minutes, THEN... NOTIFY the State of Alabama at:

24 Hours Primary: 9-1-205-280-2310 Backup: 9-1-800-843-0699 Backup: 9-1-334-324-0076 AND REPORT... the information recorded on Appendix A.

AND FAX... a copy of Appendix A to the State of Alabama for confirmation of information at 9-1-205-280-2495.

N/A - ODS was contacted.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 487TC REV. NO. 0 PAGE 12 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL 3.3 ODS State of Alabama Notification Confirmation Receive a confirmation call from the ODS verifying that the notification of the State of Alabama was completed. Do this concurrently with the implementation of this procedure.

x CUE: (3 minutes after fax) Request simulator console operator to call and confinn that the ODS has received the fax and notified the State.

STANDARD:

Continues in procedure until conformation call is received and acknowledges receipt.

SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL 3.3 ODS State of Alabama Notification Confirmation JPM NO. 487TC REV. NO. 0 PAGE 12 of21 NOT CRITICAL Receive a confirmation call from the ODS verifying that the notification of the State of Alabama was completed. Do this concurrently with the implementation of this procedure.

x CUE: (3 minutes after fax) Request simulator console operator to call and confirm that the ODS has received the fax and notified the State.

STANDARD:

Continues in procedure until conformation call is received and acknowledges receipt SAT UNSAT N/A __

COMMENTS: _____

CAUTION JPM NO. 487TC REV. NO. 0 PAGE 13 of21 Ongoing or anticipated security events may present a danger to site personnel. Do not conduct the notification of site personnel PA message during an ongoing or anticipated security event. All pertinent site personnel PA messages will be conducted per AOI-100-8 for security events.

• • • • • • • • • • • • • • • • 11< * * *********************************************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 3.4 Notification of Site Personnel STANDARD:

CONDUCT a Plant PA announcement similar to the following:

(Dial 687 to obtain the Plant PA)

Let me have your attention please.

This is (name) _____ _

A Site Area Emergency, Emergency Classification has been declared.

We are currently implementing EPIP-4.

If you have not already done so, please report to your assigned emergency center at this time.

x P. A. Announcement was made giving name, SAE status on Unit 3, and informs plant personnel that EPIP-4 is being implemented and directs plant personnel to report to their assigned Emergency Response Facility, if they haven't already done so.

SAT UNSAT N/A __

COMMENTS: _____

CAUTION JPM NO. 487TC REV. NO. 0 PAGE 13 of21 Ongoing or anticipated security events may present a danger to site personnel. Do not conduct the notification of site personnel PA message during an ongoing or anticipated security event. All pertinent site personnel PA messages will be conducted per AOI-100-8 for security events.

• • • • • • • • • • • • • • • • 11< * * *********************************************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 3.4 Notification of Site Personnel STANDARD:

CONDUCT a Plant PA announcement similar to the following:

(Dial 687 to obtain the Plant PA)

Let me have your attention please.

This is (name) _____ _

A Site Area Emergency, Emergency Classification has been declared.

We are currently implementing EPIP-4.

If you have not already done so, please report to your assigned emergency center at this time.

x P. A. Announcement was made giving name, SAE status on Unit 3, and informs plant personnel that EPIP-4 is being implemented and directs plant personnel to report to their assigned Emergency Response Facility, if they haven't already done so.

SAT UNSAT N/A __

COMMENTS: _____

CAUTION Do not initiate Assembly / Accountability when:

JPM NO. 487TC REV. NO. 0 PAGE 14 of 21

1. A severe weather condition exists or is projected on-site, such as a Tornado.

2. An on-site security risk condition exists that may present a danger to site personnel during the Assembly / Accountability process as determined by SED/Nuclear Security.

3. Rapid Evacuation of the Protected Area REPA has been conducted.

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 3.5 Assembly / Accountability 3.5.1 IF... Assembly I Accountability has not been conducted, THEN... IMPLEMENT EPIP-8, Appendix C concurrently with this procedure. This action may be delegated.

3.5.2 IF... an order to evacuate non-emergency responders has not been issued, THEN... upon completion of Assembly / Accountability, INITIATE the order to "Evacuate Non-Emergency Responders," through implementation of EPIP-8, Appendix F, concurrently with this procedure.

3.5.3 IF... conditions exist that do not allow for an Assembly /

Accountability or Evacuation at this time, THEN... CONTINUE to assess the situation, implementing EPIP-8 as applicable.

I CUE: The STA Is implementing EPIP-8 as needed.

STANDARD:

Acknowledges that STA is performing EPIP-8 and continues to step 3.6 x

SAT UNSAT N/A __

COMMENTS: _____

CAUTION Do not initiate Assembly / Accountability when:

JPM NO. 487TC REV. NO. 0 PAGE 140f21

1. A severe weather condition exists or is projected on-site, such as a Tornado.

2. An on-site security risk condition exists that may present a danger to site personnel during the Assembly / Accountability process as determined by SED/Nuclear Security.

3. Ra id Evacuation of the Protected Area REPA has been conducted.

PERFORMANCE STEP:

CRITICAL NOT CRITICAL 3.5 Assembly / Accountability 3.5.1 IF... Assembly / Accountability has not been conducted, THEN... IMPLEMENT EPIP-8, Appendix C concurrently with this procedure. This action may be delegated.

3.5.2 IF... an order to evacuate non-emergency responders has not been issued, THEN... upon completion of Assembly / Accountability, INITIATE the order to "Evacuate Non-Emergency Responders," through implementation of EPIP-8, Appendix F, concurrently with this procedure.

3.5.3 IF... conditions exist that do not allow for an Assembly /

Accountability or Evacuation at this time, THEN... CONTINUE to assess the Situation, implementing EPIP-8 as applicable.

I CUE: The STA Is Implementing EPIP-8 as needed.

STANDARD:

Acknowledges that STA is performing EPIP-8 and continues to step 3.6 x

SAT UNSAT N/A __

COMMENTS: _____

I

JPM NO. 487TC REV. NO. 0 PAGE 15 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL 3.6 Dose Assessment EVALUATE... the need for dose assessment.

IF... dose assessment is needed, THEN... CONTACT, if operational, the Central Emergency Control Center (CECC) at 5-751-1614.

OR IF... the CECC is not operational, THEN... CONTACT, the Radiological Protection Shift Supervisor or designee at 7865 and request the implementation of EPIP-13 for dose assessment.

I CUE: The CECC is not operational at this time.

STANDARD:

SRO/SED acknowledges that the CECC is not staffed and contacts the Radiological Protection Shift Supervisor and request the implementation of EPIP-13 if deemed necessary.

x SAT UNSAT N/A __

COMMENTS: _____

JPM NO. 487TC REV. NO.O PAGE 15 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL 3.6 Dose Assessment EVALUATE... the need for dose assessment.

IF... dose assessment is needed, THEN... CONTACT, if operational, the Central Emergency Control Center (CECC) at 5-751-1614.

OR IF... the CECC is not operational, THEN... CONTACT, the Radiological Protection Shift Supervisor or designee at 7865 and request the implementation of EPIP-13 for dose assessment.

I CUE: The CECC Is not operational at this time.

STANDARD:

SRO/SED acknowledges that the CECC is not staffed and contacts the Radiological Protection Shift Supervisor and request the implementation of EPIP-1 3 if deemed necessary.

x SAT UNSAT N/A __

COMMENTS: _____

I

JPM NO. 487TC REV. NO. 0 PAGE 16 of 21 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 3.7 Notification of the Nuclear Regulatory Commission (NRC)

CAUTION Ensure that previous declared emergency classifications have been communicated to NRC, specifically in fast breaking events, where emergency classifications are rapidly changing.

NOTE If possible, when making notifications to the NRC, utilize the Emergency Notification System (ENS). Dial the first number listed on the sticker affixed to the ENS telephone by dialing 9 "The Ten Digit Number Listed on the ENS Telephones". If the number is busy, then select in order, the alternate numbers until a connection is achieved. No access codes should be re uired.

STANDARD:

NOTIFY... the NRC immediately but no later than one hour after the emergency has been declared.

IF... REQUESTED by the NRC to maintain an open and continuous line of communications, THEN... MAINTAIN an open and continuous line of communications as directed by NRC.

SRO/SED notified NRC within 60 minutes on the Simulator by calling the console operator and requesting NRC.

SAT UNSAT N/A __

COMMENTS: _____

RECORD TIME NRC NOTIFIED _____

JPM NO. 487TC REV. NO. 0 PAGE 16 of 21 PERFORMANCE STEP:

CRITICAL x

NOT CRITICAL 3.7 Notification of the Nuclear Regulatory Commission (NRC)

CAUTION Ensure that previous declared emergency classifications have been communicated to NRC, specifically in fast breaking events, where emergency classifications are rapidly changing.

NOTE If possible, when making notifications to the NRC, utilize the Emergency Notification System (ENS). Dial the first number listed on the sticker affixed to the ENS telephone by dialing 9 "The Ten Digit Number Listed on the ENS Telephones". If the number is busy, then select in order, the alternate numbers until a connection is achieved. No access codes should be re uired.

STANDARD:

NOTIFY... the NRC immediately but no later than one hour after the emergency has been declared.

IF... REQUESTED by the NRC to maintain an open and continuous line of communications, THEN... MAINTAIN an open and continuous line of communications as directed by NRC.

SRO/SED notified NRC within 60 minutes on the Simulator by calling the console operator and requesting NRC.

SAT UNSAT N/A __

COMMENTS: _____

RECORD TIME NRC NOTIFIED

JPM NO. 487TC REV. NO. 0 PAGE 17 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL 3.8 Review of Procedure Review this procedure to ensure that all steps and actions have been completed and all place keeping blocks have been checked or denoted as instructed. This action may be delegated.

I CUE: No-one is available to review the procedure for you.

STANDARD:

SRO/SED reviews procedure to ensure all steps and actions have been completed, placekeeping blocks checked as instructed.

x SAT UNSAT N/A __

COMMENTS: _____

PERFORMANCE STEP:

CRITICAL 3.8 Review of Procedure JPM NO. 487TC REV. NO. 0 PAGE 17 of 21 NOT CRITICAL Review this procedure to ensure that all steps and actions have been completed and all place keeping blocks have been checked or denoted as instructed. This action may be delegated.

I CUE: No-one is available to review the procedure for you.

STANDARD:

SRO/SED reviews procedure to ensure all steps and actions have been completed, place keeping blocks checked as instructed.

x SAT UNSAT N/A __

COMMENTS: _____

3.9 Monitor / Re-evaluate the Event JPM NO. 487TC REV. NO. 0 PAGE 18 of 21 Monitoring and reevaluation of plant events along with communicating significant changes should be performed continuously as a function of the emergency response. Methods used to communicate significant changes are not formalized and may vary depending upon staffing levels as well as availability of personnel or equipment. Appendix C provides a systematic approach to monitor/reevaluate and communicate significant changes in plant conditions.

Utilize Appendix C to monitor/re-evaluate and communicate plant conditions and significant changes. Significant changes in plant conditions are at a minimum when other EAL conditions exist indicating the current emergency classification.

CUE: The Emergency Centers are staffed and the assistant Plant Manager (duty SED, SRO) Is here to relieve you. That completes this JPM.

END OF TASK STOP TIME ____

3.9 Monitor I Re-evaluate the Event JPM NO. 487TC REV. NO. 0 PAGE 18 of 21 Monitoring and reevaluation of plant events along with communicating significant changes should be performed continuously as a function of the emergency response. Methods used to communicate significant changes are not fonmalized and may vary depending upon staffing levels as well as availability of personnel or equipment. Appendix C provides a systematic approach to monitor/reevaluate and communicate significant changes in plant conditions.

Utilize Appendix C to monitor/re-evaluate and communicate plant conditions and significant changes. Significant changes in plant conditions are at a minimum when other EAL conditions exist indicating the current emergency classification.

CUE: The Emergency Centers are.staffed and the assistant Plant Manager (duty SED, SRO) Is here to relieve you. That completas this JPM.

END OF TASK STOP TIME ____

JPM NO. 487TC REV. NO. 0 PAGE 19 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

x SAT UNSAT N/A __

COMMENTS: ______ _

• • • • • • • • • • • • • • "II' It A****A A It It A 1t'II*********************************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A __

COM ME NTS: _____

JPM NO. 487TC REV. NO. 0 PAGE 19 of 21 PERFORMANCE STEP:

CRITICAL NOT CRITICAL PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

x SAT UNSAT N/A __

COMMENTS: _____

• • • • • • • • • • • • • • "II' It A****A A It It A 1t'II*********************************************************************

PERFORMANCE STEP:

CRITICAL NOT CRITICAL x

PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A __

COM ME NTS: _____

I Browns Ferry SITE AREA EMERGENCY Appendix A Page 1 of 1 JPM NO. 487TC REV. NO. 0 PAGE 20 of 21 EPIP-4 SITE AREA EMERGENCY INITIAL INFORMATION FORM 1.* This is a Drill o This is an Actual Event - Repeat - This is an Actual Event

2. This is Name. Browns Ferry has declared a SITE AREA EMERGENCY affecting:

0 Unit 1 o Unit 2

• Unit 3 o Common

3. EAL Designator(s): __

-=2:,:...1.:...-=S ______

---

=-. (Critical)

4. Brief description of event: Unidentified leak in Unit 3 Drywell with level at -25 on the Emergency Range, reactor pressure 885 pSig. OW pressure 30 psig and slowly rising, OW temperature 242 degrees F and slowly rising, Torus Temperature 245 0 F and Torus Pressure 30 psig with a Torus Level of 15 feet. EOl1 and 2 are in progress.

Venting the TORUS per EOI-2 is also in progress. Unit 3 conditions are deteriorating.

Wind speed is 5 mph from the SW.

5. Radiological Conditions: (Check one under both Airborne and Liquid column)

Airborne Releases Offsite Liquid Releases Offsite DMinor releases within federally approved DMinor releases within federally approved limits 1 limits 1 DReleases above federally approved limits 1

.Release information not known CTech Specs) o Releases above federally approved limits 1

• Release information not known CTech Specs)

6. Event Declared:

Time:

Time. Date: Today

7. Provide Protective Action Recommendation:

None.

8. Please repeat the information you have received to ensure accuracy.

9. Fax to ODS at 5-751-8620 or State of Alabama at 9-1-205-280-2495 per Section 3.2 I Browns Ferry SITE AREA EMERGENCY Appendix A Page 1 of 1 JPM NO. 487TC REV. NO. 0 PAGE 20 of 21 EPIP-4 SITE AREA EMERGENCY INITIAL INFORMATION FORM 1.* This is a Drill o This is an Actual Event - Repeat - This is an Actual Event

2. This is Name. Browns Ferry has declared a SITE AREA EMERGENCY affecting:

0 Unit 1 o Unit 2

• Unit 3 o Common

3. EAL Designator(s): __

-=2:,:...1.:...-=S ______

---

=-. (Critical)

4. Brief description of event: Unidentified leak in Unit 3 Drywell with level at -25 on the Emergency Range, reactor pressure 885 pSig. OW pressure 30 psig and slowly rising, OW temperature 242 degrees F and slowly rising, Torus Temperature 245 0 F and Torus Pressure 30 psig with a Torus Level of 15 feet. EOl1 and 2 are in progress.

Venting the TORUS per EOI-2 is also in progress. Unit 3 conditions are deteriorating.

Wind speed is 5 mph from the SW.

5. Radiological Conditions: (Check one under both Airborne and Liquid column)

Airborne Releases Offsite Liquid Releases Offsite DMinor releases within federally approved DMinor releases within federally approved limits 1 limits 1 DReleases above federally approved limits 1

.Release information not known CTech Specs) o Releases above federally approved limits 1

• Release information not known CTech Specs)

6. Event Declared:

Time:

Time. Date: Today

7. Provide Protective Action Recommendation:

None.

8. Please repeat the information you have received to ensure accuracy.

9. Fax to ODS at 5-751-8620 or State of Alabama at 9-1-205-280-2495 per Section 3.2

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 21 of 21 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are the Shift Manager. Unit 3 was operating at 1 00%

(BOL) when the Unit 3 US received a call from the Security Chief of a tornado warning in the vicinity of Browns Ferry. The Unit 2 Supervisor has implemented 0-AOI-100-7 Tornado. A few minutes later the plant lost "All Offsite Power" due to the tornado hitting the switchyard. 0-AOI-57-1A is in progress due to the loss of All Offsite Power. 480V Shutdown Board 3B has also been lost due to overcurrent conditions. EOI-1 and 2 are in progress due an unidentified leak in the Orywell causing High Orywell pressure that is trending upwards. The Operators are venting the Torus per EOI-2. (Unit 1 and 2 also scrammed from 100% power and are responding normally.)

INITIATING CUES:

The Unit 3 US has informed you of the leak in the Orywell and the Loss of All Offsite Power. MSIV's are closed and SRV's are being utilized to maintain reactor pressure between 800-1000 psig. Orywell PressurefTemperature and Torus PressurefTemperature are trending upwards. The crew has been unable to get a Orywell or Torus spray system to operate. Using the following parameters provided to you by the control room operating crew, CLASSIFY THE EVENT according to the EPIPs and perform any required actions. The TSC and CECC are not staffed. (NOTE:

Unit 3 conditions are deteriorating.)

Reactor Level Reactor Pressure OW Pressure OW Radiation OW Leakage Rate OW Temperature Torus Temperature Torus Pressure Torus Level Wind Speed Venting Torus

-25 on Emergency Range 885 psig 30 psig and rising (unable to Spray due to multiple valve failures.)

RR-90-256 slowly rising (prior to isolation) unknown at this time 242 0 F and slowly rising 245 0 F 30 psig and rising 15 feet 5 mph from the SW per APP 12 (SOME portions of this JPM are TIME CRITICAL)

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PAGE 21 of 21 IN*SIMULATOR: I will explain the initial conditions and state the task to be performed.

I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

• __ ******************.A.** ** *.*****************************************~*********************

INITIAL CONDITIONS:

You are the Shift Manager. Unit 3 was operating at 100%

(BOL) when the Unit 3 US received a call from the Security Chief of a tornado warning in the vicinity of Browns Ferry. The Unit 2 Supervisor has implemented 0-AOI-100-7 Tornado. A few minutes later the plant lost "All Offsite Powe~' due to the tornado hitting the switchyard. 0-AOI-57-1A is in progress due to the loss of All Offsite Power. 480V Shutdown Board 3B has also been lost due to overcurrent conditions. EOI-1 and 2 are in progress due an unidentified leak in the Drywell causing High Drywell pressure that is trending upwards. The Operators are venting the Torus per EOI-2. (Unit 1 and 2 also scrammed from 100% power and are responding normally.)

INITIATING CUES:

The Unit 3 US has informed you of the leak in the Drywell and the Loss of All Offsite Power. MSIV's are closed and SRV's are being utilized to maintain reactor pressure between 800-1000 psig. Drywell PressurefTemperature and Torus PressurefTemperature are trending upwards, The crew has been unable to get a Drywell or Torus spray system to operate. Using the following parameters provided to you by the control room operating crew, CLASSIFY THE EVENT according to the EPIPs and perform any required actions. The TSC and CECC are not staffed. (NOTE:

Unit 3 conditions are deteriorating.)

Reactor Level Reactor Pressure OW Pressure OW Radiation OW Leakage Rate OW Temperature Torus Temperature Torus Pressure Torus Level Wind Speed Venting Torus

-25 on Emergency Range 885 psig 30 psig and rising (unable to Spray due to multiple valve failures.)

RR-90-256 slowly rising (prior to isolation) unknown at this time 242 0 F and slowly rising 245 0 F 30 psig and rising 15 feet 5 mph from the SW per APP 12 (SOME portions of this JPM are TIME CRITICAL)