Text

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)
	v • d • e

NO. 541 JPM NO.

REV. NO.3 REV. NO. 3 PAGE 1 of6

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PlANT JPM NUMBER: 541 Admin Conduct of Operations TITLE: Determine Adequate Performance of License Reactivation PROVIDE CANDIDATE WITH A COpy COPY OF: OPDP-10 (Only If Requested)

SUBMITTED BY: DATE:

DATE:_ _ __

VALIDATED BY:BY: DATE:

DATE:_ __ __ __ __

APPROVED BY: BY: DATE: _ __ __ __ __

TRAINING PLANTCONCURRENCE:~__________________

PLANT CONCURRENCE: ---=-==-:-==0=---- DATE: _ __ __ _ _ __

OPERATIONS

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

JPM NO. 541 REV. NO.NO.3 3 PAGE PAGE2of6 2 of6

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 08/28/05 All Initial issue 1 02/16/06 All Procedure Revision, Added references 2 12/22/07 All General Revision & Procedure change 3 03/14/09 All New Procedure (changed from OPDP-1 to OPDP-

10) and reformat and modified critical data

JPM NO. 541 REV. NO.3 PAGE 3 30f6 016 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ____________________________________________

RO SRO DATE:__________

JPM NUMBER: 541 TASK TITLE: Determine Adequate Performance 01 of License Reactivation KIA NUMBER:

KJA 2.1.4 KJA KIA RATING RATING:: RO 3.3 SRO 3.8 TASK STANDARD: Determine which olthe of the reactivating personnel have correctly completed the reactivation requirements.

requirements.

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

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::

RESULTS SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _____________________

_ _ _ _ _ _ _ _ _ _ _DATE: _ ____________

JPM NO. 541 REV. NO.

NO.3 3 PAGE PAGE4of6 4 of6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EXAMINER'S KEY INITIAL CONDITIONS: 5 licensed personnel have returned 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 perfonmed, 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 Bhrs 8 hrs Bhrs PerSM Lead U-1 U-2 U-2 U-2 U-3 U-3 instructions with Ops SRO SRO SRO SRO SRO SRO U-2 Desk UO Superintendent (RO)

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

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

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

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

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

reactivation.

JPM NO. 541 REV. NO.3 REV.

PAGE 5 of6 50f6

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

reactivation .

SR01 did not interview with the Ops Training Manager and performed his tour with an RO.

RO.

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

R01 did not interview with the Ops Superintendent and worked one activation shift with RO, this position does not qualify (after three (3) 12 hr shifts, the tagging RO, 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 addITional shift - 8 hrs, hrs, however, the plant tour discussion was with the US instead of the SM.

START TIME STOP TIME END OF TASK

PAGE 6 of6 60f6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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, licensee, tours performed, 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 8 hrs 8 hrs B Per SM PerSM Lead U-1 U-2 U-2 U-2 U-3 U-3 instructions Ops SRO SRO SRO SRO SRO SRO wlth 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 wee 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 Bhrs B8 hrs PerSM Manager U-3 U-3RO U-1 RO tagging U-2RO U-2 RO U-2RO U-2 RO instructions Shift Manager RO UO UORO RO with STA (SRO)

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

UO(RO)

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

reactivation.

JPM NO.

NO. 510 REV.

REV. NO.3 PAGE 1 of 14 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER:

JPMNUMBER: 510 TITLE:

TITLE: EVALUATE RECOMBINER PERFORMANCE ADMIN:

ADMIN: Equipment Control PROVIDE CANDIDATE WITH A COpy COPY OF: OF: 3-01-66, section 6.1 SUBMITTED BY: DATE :_ _

DATE: __ ___

VALIDATED BY: BY: DATE: _ _ __

APPROVED BY: DATE:. ___ __ __ _ _

TRAINING PLANTCONCURRENCE:

PLANTCONCURRENCE: _ ____________________

_~~~~~_ ___ _ DATE:. _____

OPERATIONS

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

JPM NO. 510 REV. NO.3 NO. 3 PAGE 2 of 14

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 08/08/02 All Initial issue 1 06/22/07 All Procedure revision 2 01/02/08 01 /02/08 All General revision 3 05/18/09 All General revision & re-format

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

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ____________________________________________

RO SRO ___________

DATE: __________

JPM NUMBER: 510 TASK TITLE: EVALUATE RECOMBINER PERFORMANCE KIA NUMBER:

KJA 2.1 .7 2.1.7 KIA KJA RATING:

RATING: RO 44.4

.4 SRO 4.7 TASK STANDARD:

STANDARD: EVALUATE OFF-GAS RECOMBINER PERFORMANCE

PERFORMANCE LOCATION: LOCATION :

REFERENCES/PROCEDURES NEEDED: 3-01-66, Rev 57 CLASS --=...:Xo.-_

ROOM: __---"X'---_

CLASSROOM:

VALIDATION TIME: CLASSROOM:

CLASSROOM: 12:00 MAX. TIME ALLOWED: ________

_ _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? ATIACHED? YES ___ NO RESULTS:

RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ___________________

_ _ _ _ _ _ _ _ _ _ _,DATE: DATE: _ __ __ _ __ __ ___

JPM NO. 510 REV. NO.3 PAGE 4 of 14

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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, 3-01-66, 6.1..

Section 6.1

3-TI-66-75A 3-TI-66-758 3-TI-66-75B 3-TRS-66-77 A Center temp 3-TRS-66-77A 393 OF 393°F 320 OF of 618 OF of 3-TRS-66-778 Center temp 3-TRS-66-77B 380 OF of Rx Power Thermal 3430 mwth 3-H2R-66-96 operable - both pens reading readinQ .24% H, H2

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 x

[1] PERFORM a recombiner performance evaluation as follows:

[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.

STANDARD:

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

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

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

[1.2]

CRITICAL NOT CRITICAL DETERMINE the in-service recombiner operating (center) x temperature as indicated on RECOM81NER 3A/38 TEMPERATURE recorder, 3-TRS-66-77, Panel 3-9-53.

STANDARD:

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:

[1.4]

CRITICAL NOT CRITICAL DETERMINE the reactor thermal power (MWt) from process x

computer.

STANDARD:

Determined reactor thermal power from the handout.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

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

STANDARD:

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

N/A _ _ COMMENTS: _ _ _ _ __

SAT UNSAT

NO. 510 JPM NO.

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

[1 .6]

[1.6]

CRITICAL x NOT CRITICAL VERIFY point on illustration 1 is above or equal to the appropriate line (HWC in service or HWC out of service)

STANDARD:

Determines from Illustration 1 that calculated LIt Delermines ~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:

COMMENTS: _ _ __ __ __ ___

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

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

*************************************************kkkkkkk********************************************

PERFORMANCE STEP:

[2]

CRITICAL NOT CRITICAL IF the in-service recombiner performance is below the minimum allowable, x

THEN:

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

STANDARD:

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:

[2.3]

CRITICAL IF both hydrogen analyzers are inoperable, THEN NOT CRITICAL x NOTIFY Chemistry to obtain a grab sample to determine hydrogen concentration.

STANDARD:

Determined Step [2.3] is N/A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

STANDARD:

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

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.

NO. 510 REV. NO.3 REV.

PAGE 11 of14of 14 PERFORMANCE STEP:

[3]

CRITICAL IF off-gas hydrogen rises above 1%, THEN NOT CRITICAL xx REFER TO 3-AOI-66-1.

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

Determines off-gas hydrogen has NOT risen above 1 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%, 4%, THEN DO NOT TAKE any action that will change off-gas valve positions until after the unit is down.

shut down.

JPM NO. 510 NO. 3 REV. NO.

PAGE 12 of 14 PERFORMANCE STEP:

[4]

CRITICAL xx NOT CRITICAL IF analysis or hydrogen analyzers show hydrogen concentration is below

."., '" 'k.* **

4%,

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.

TIME_ _ _ __

JPM NO. 510 REV. NO.3 PAGE 13 of 14

Illustration 1 (Page 1 of 1)

Recombine Performance evaluation - AT to Reactor Power 250 200 /'"

~

V _".J-150 /'

L .. '

V ,,-",A" 100

~

v..

" .. " < ' _ ~ ~.

A ' '

t: IIIJ1VUZlUf V \ ];Y ... "

~

o 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 AT ~ 190°F HWC out Of service AT ~242°F CURVE FACTORS Normal Water Chemistry (NWC) AT =O.070°F per MVVt Hydrogen water Chemistry (HVVC) AT =O.055°F per MVVt

PAGE 14 of 14 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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.

properly.

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

6.1.

3-TI-66-75A 3-TI-66-7SA 393 393°FOF 3-TI-66-7SB 3-TI-66-758 320 320°Fof 3-TRS-66-77 A Center temp 618 of OF 3-TRS-66-778 Center temp 3-TRS-66-77B of 380 OF Rx Power Thermal 3430 mwth 3-H2R-66-96 operable - both pens reading .24% H, H2

JPM NO.

NO. 120F NO. 2 REV. NO.

PAGE 1 of 28 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER: 120F TITLE:

TITLE: PERFORM 2-SR-3.4.2.1 2-SR-3.4.2.1 JET PUMP MISMATCH AND OPERABILITY TASK NUMBER: U-068-SU-05 SUBMITTED BY: BY: DATE: _ _ __

VALIDATED BY:BY: DATE:_ _ __

DATE:

APPROVED BY: DATE: _ _ __

DATE:

TRAINING PLANTCONCURRENCE: __ ===:::-:-:;:;-___

PLANT CONCURRENCE: ____________________ _ DATE:

DATE:_ _ __

OPERATIONS

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

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

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 06/03/07 All Initial issue 1 06/27/08 06/27108 All General revision & re-format 2 05/01/09 05/01 /09 All Procedure revision

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

OPERATOR: __________________________________________

RO SRO DATE:__________

JPM NUMBER: 120F TASK NUMBER: U-068-SU-05 TASK TITLE:

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

KiA 2.2.12 KiA 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 CLASSROOM.x PLANT _ CTRL ROOM _

REFERENCES/PROCEDURES NEEDED: 2-SR-3.4.2.1, Rev 25 2-SR-3.4.2.1.

VALIDATION TIME:TIME: CLASSROOM: 30:00 LOCAL: ______ _ _ ___ _

MAX. TIME ALLOWED: ________

_ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME: 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::

RESULTS SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________________

_ _ _ _ _ _ _ _ _ _ _DATE:__________ _ _ _ _ ___

JPM NO.

NO. 120F REV. NO.2 REV.

PAGE 4 of 28

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

I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, 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".

Correct". (OR "That's Incorrect", if applicable).

applicable). When you have completed your assigned task, task, you will say, say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: Operator. Unit 2 is operating at 100% power You are a Unit 2 Operator.

for 280 Days on line,. 2-SR-3.4.2.1, Jet Pump Mismatch and Operability, Operability, is in progress and complete up to Step 7.2[lJ.

7.2[1]. Candidate should contact Examiner for any necessary feedback or info and or to indicate task completion.

completion.

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

7.2[1].

JPM NO. 120F REV. NO.2 PAGE 5 of of28 28 START TIME _ _ _ __ __ ___

Note: All of the following steps will require daUng dating each page of the SR and initialing/"N/A"ing initiallngf'N/A"ina as appropriate.

aDDroDrlate.

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. Log.

(N/A if ICS is not available)

STANDARD:

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

SAT UNSAT N/A _ _ COMMENTS:

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 NOT CRITICAL x

[3] RECORD the Total Core flow.

Total Core Flow (Red Pen) 2-XR-68-50 87.0 Mlb/hr STANDARD:

Records Total Core Flow 2-XA-68-50 (From Data Sheet).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

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

NOTES

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:

7.2.2 Recirculation Pump Loops CRITICAL NOT CRITICAL x

[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 e ReClrc . Pump D'ISCharge fl ows.

Loop 2A Loop 28 2-FI-68-5 2-FI-68-81

[3]

45.0 gpm X 1000 RECORD th e ReClrc Loop 2A 44.0 gpm X 1000

. Ioop 2A an d 28 J et P umpum~ FI ow.

Loop 28 2-FI-68-46 2-FI-68-48 45 Mlb/hr 44 Mlb/hr STANDARD:

Records Data in steps [1 ],[2], and [3] (From Data Sheet).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 120F REV. NO.2 PAGE 9 of 28

marked as N/A.

NOTE If a Recirculation Pump is not in service then the associated instrumentations can can be PERFORMANCE STEP: CRITICAL NOT CRITICAL x 7.2.3 Jet Pump Loops

[1 J

[1] RECORD the following Differential Pressure readings below: below:

Loop2A 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:_ __ __ _ __ __ ___

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

NOTES

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

(~+102.5) X 100 = 84.88

[2] 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 STANDARD:

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

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

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

[3]

CRITICAL IF %WT is < 70% as recorded in Step 7.3[1], THEN NOT CRITICAL x 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]:

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

[2] 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

[3]

RECORD below.

I Plot falls between the bold lines Yes Using Steps 7.4.1 [1] and 7.4.1 [2] from above:

D No I:&:l 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.

[3]

I Plot falls between the bold lines Yes Using Steps 7.4.2[1] and 7.4.2[2] from above:

[g] No 0 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.

[3]

28 Individual DP's are between the bold lines.

Using Steps 7.4.3[1] and 7.4.3[2]

Yes 0 No !XI 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 15 of 28

CAUTION 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:

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 NIA if not required.)

STANDARD:

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 Attachment 2 Engineering Judgement/Review x NOT CRITICAL Date:

CAUTION 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 ] Mark the condition that applies:

Following Refueling Outage. 0 The Reactor is in Single Loop Operation 0 Point(s) plotted in sections 7.4.1, or 7.4.2 or 7.4.3 fall outside the bolded lines [8]

[2] REQUEST System Engineering to perform an Engineering Judgement/Review.

[3] 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 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 STANDARD:

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.

REV. NO.2 PAGE 17 170f28of 28

I CUE: Attachment 2 has come back from Engineering martc:ed marked NO

- - - - 11,," "':11,,:11:11:11***********

PERFORMANCE STEP: CRITICAL xx NOT CRITICAL I

7 .4.5 Operability Determination 7.4.5

[1]

[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 [3] and 7.4.2[3J 7.4 .1[3J 7.4.2[3] Both Jet Pump Loops 0 [lS]

[&] 0 steps are marked as YES 7.4.3[3]

7.4 .3[3J Jet Pump DP to criteria is 0 [&]

[lS] 0 marked as YES.

Attachment 2 Engineering Evaluation 0 [&]

[lS] 0 is marked as YES. YES.

STANDARD:

Marks Steps 7.4.1 7.4.1[3]

[3J and 7.4.2[3]

7.4.2[3J NO, Step 7.4.3[3J 7.4.3[3] NO and An ATT 2 NO (after cue).

SAT UNSAT N/A _ _ COMMENTS: _ __ __ __ __ _ __

- - - - 11 '" ****'" **************************************************

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[2]

[2J Using the Criteria Results in Step 7.4.5[1J 7.4.5[1]

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

STANDARD:

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

SAT UNSAT N/A _ _ COMMENTS: _ _ _ __ __ ___

JPM NO. 120F REV. NO.2 REV. NO. 2 PAGE 18 of 28 PERFORMANCE STEP: CRITICAL NOT CRITICAL xx 7.5 Completion and Notifications

[1] IF an Engineering Judgment/Review was performed, 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.

complete.

STANDARD:

N/A SAT UNSAT N/A _ _ COMMENTS:_ _ _ _ _ ___

I CUE: completes this task.

CUE: That complete. I

JPM NO. 120F REV. NO.2 PAGE 19 of 28 PERFORMANCE STEP: CRITICAL PERFORMER demonstrated the use of SELF CHECKING during this JPM NOT CRITICAL x STANDARD:

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

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

- - - - A AAAAAA 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

PAGE 27 of of28 28

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE PlANT IN-SIMULATOR: I will explain the initial conditions and state the task to be performedperformed..

I will provide initiating cues and reports on other actions when directed by you. When you complete co mplete the task successfully, the objective for this job performance measure will be satisfied satisfied.. When your task is given, you will repeat the task and I will acknowledge Incorrect" , if applicable).

"That's Correct". (OR "That's Incorrect", 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.

completion.

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

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 2-PDI-68-07 2-PDI-68-08 2-PDI-68-10 JET PUMP 15 JET PUMP 16 JET PUMP 17 JET PUMP 18 LOOP2A LOOP2A LOOP2A LOOP2A 8.5 PSID 9.0 PSID 9.0 PSID 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 1 of7 of 7

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

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

SUBMITIED BY: ____

DATE:______ _

VALIDATED BY: DATE:_____

DATE:. ____ _ _

APPROVED BY: BY: ____

DATE:. _____ _ _

TRAINING PLANTCONCURRENCE:

PlANTCONCURRENCE: ___________________

____~~~~~------ _ ____

DATE:_____ _ _

OPERATIONS

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

PAGE 2 of 7

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

PAGE 3 of 7

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ______________________________________________ __

RO SRO DATE: ____________

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

authority.

KJA NUMBER:

KIA NUMBER: 2.3.4 KJA RATING:

KIA RO 3.2 SRO 3.7

- - - - 11 II II II'" "'*******************************************************

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

PERFORMANCE LOCATION: LOCATION: __-"X,--_

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

CLASSROOM REFERENCES/PROCEDURES NEEDED: NEEDED: EPIP-15 Rev (If asked for)

VALIDATION TIME: TIME: CLASSROOM: _ _ ___

MAX. TIME ALLOWED:

ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS A ITACHED?

ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ ___________________

_ _ _ _ _ _ _ _ _ _ _ DATE: __________ _ _ _ _ ____

PAGE 4 of 7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

- - - - '***************** 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 staffed slaffed The following tasks are required to be performed:perfonmed:

TASK

1 2

3 Determine allowed stay time to operate equipment in a constant 25 Rlhr field (assume No dose incurred while traveling to and from work location)

Complete Appendix B 8 of EPIP-15 Determine who has the authority to approve the emergency exposure INITIATING CUES:

Refer to the above infonmation.

information.

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

2. Complete Appendix B 8 of EPIP-15 3.

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

PAGE50f7 PAGE 50f7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE EXAMINER'S KEY 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.

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

4. You have received 500 mR TEDE this year 5.

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

performed :

TASK 1 Determine allowed stay time to operate equipment in a constant 25 Rlhr R1hr field (assume No dose incurred while traveling to and from work location) 2 Complete Appendix 8 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 8 B of EPIP-15

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

PAGE 6 of?

EXAMINER KEY (Do NOT give to Candidate)

STEP 1: Determine allowable dose remaining for Protection of Valuable Property activities.

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

10R- .5R = 9.5 R COMMENTS:

STEP 2: Determine time available for the AUO to complete CRITICAL STEP task without exceeding allowable dose limit.

STANDARD: Stay time is calculated to be: _SAT 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)

_UNSAT

(+/- 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 CRITICAL STEP emergency exposure lies with the Shift Manager (SED)

SAT

_UNSAT

PAGE 70f7 7 of 7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE Classroom STUDENT HANDOUT INITIAL CONDITIONS 1

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:

performed:

TASK 1 Determine allowed stay time to operate equipment in a constant 25 Rlhr field Detennine (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.

information.

1. How long do You have to complete task without exceeding his Emergency Dose Limits 2.

2. Complete Appendix B of EPIP-15

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

JPM NO. 487TC NO. 0 REV. NO.

REV.

PAGE 1 of 21

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER: 487TC TITLE:

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 SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

DATE:

TRAINING PLANTCONCURRENCE:

PLANT CONCURRENCE: - ____________________

- - = = - : = : - : : - : - 0 : : - - -_- DATE:_______

OPERATIONS

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

JPM NO. 487TC REV. NO. 0 REV.

PAGE 2 of21 of 21 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 03/16/09 All Initial issue

JPM NO. 487TC REV. NO. 0 PAGE 3 0121 of21 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ____________________________________________ __

RO SRO DATE:__________

DATE: _ _ _ _ _ __

NUMBER:

JPM NUMBER: 487TC TASK NUMBER: S-000-EM-21 (SRO ONLY)

TASK TITLE: CLASSIFY THE EVENT PER THE REP (SAE - PRIMARY SYS.

LEAKAGE (Suppression Chamber Pressure) EXCEEDING PSP CURVE) ON UNIT 3 KIA NUMBER: 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. 4. BASED ON EXCEEDING PSP CURVE.

MAKE NOTIFICATIONS SUCH THAT; THAT: (TIME ODS NOTIFIED)-

(TIME DECLARED)"

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

(TIME DECLARED) S 60 MINUTES PERFORMANCE LOCATION: SIMULATOR X PLANT _ __ CONTROL ROOM_

ROOM __

REFERENCES/PROCEDURES NEEDED: EPIP-1 44, EPIP-4, REV 31 EPIP-1,, REV 44, VALIDATION TIME: SIMULATOR: 20 min LOCAL: ______

MAX. TIME ALLOWED:

ALLOWED: ..;;;.5,-=/6-,,-0_

__-"5",,/6,,,0 ___

_ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME: TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS A ITACHED?

ATTACHED? YES ___ NO RESULTS:

RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _______________

_ _ _ _ _ _ _ _ _ _ _ _DATE: DATE: ________

JPM NO.

NO. 487TC REV. NO. 0 PAGE 4 of21 of 21 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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 com complete plete 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",

Correct". (OR "That's Incorrect",

Incorrect" , if applicable). When you have completed your assigned task, task, you will say, "my task is complete" and I will acknowledge that your task is complete.

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.

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 Tornado. tomado hitting the switchyard. 0-AOI-57-1A is in progress due to the loss of All Offsite Power. Power. 480V Shutdown Board 3B has also been lost due to overcurrent conditions. EOI-1 and 2 are Orywell causing High Drywell in progress due an unidentified leak in the Drywell 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 Drywell Orywell Powe~' .. MSIV's are closed and SRV's are being utilized to and the Loss of "All Offsite Power" maintain reactor pressure between 800-1000 psig. psig. Drywell Orywell PressurefTemperature and Torus PressurefTemperature are trending upwards. The crew has been unable to get a Orywell 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 staffed.. (NOTE:

Unit 3 conditions are deteriorating.)

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

OW Radiation DW RR-90-256 slowly rising (prior to isolation)

OW DW Leakage Rate unknown at this time OW DW Temperature 242 0 F and slowly rising Torus Temperature 245 0 F Torus Pressure 30 psig and rising Torus Level 15 feet Wind Speed 5 mph from the SW Venting Torus per APP 12 (SOME portions of this JPM are TIME CRITICAL)

JPM NO. 487TC REV. NO. 0 PAGE 50f21

START TIME _ _ _ _ __

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: _ _ _ _ __

JPM NO. 487TC REV. NO. 0 PAGE 6 of21

BROWNS FERRY 3.0 SITE AREA EMERGENCY EMERGENCY CLASSIFICATION ACTIONS 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 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)

STANDARD:

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 IDAMAGED THE SWITCHYARD HAS PASSED THROUGH AND THE WEATHER IS

.JI I NOW CLEAR.

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 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, Range, reactor pressure 885 psig, OW pressure 30 psig and slowly rising rising,, OW temperature 242°F 242'F and slowly rising, rising , Torus Temperature 245°F and Torus Pressure 30 psig with a Torus Level of 15 feet. EOI EOl11 and 2 are in progress.

progress. Venting the TORUS per EOI-2 is also in progress. Unit 3 conditions are deteriorating. Wind speed is 5 mph from the SW. SW. (Classification of event is critical, description is not.)

SAT UNSAT N/A _ _ COMMENTS::. _

COMMENTS __ __ ___ __ ___

JPM NO.

NO. 487TC REV. NO.

REV. NO. 0 PAGE 9 of 21 of21 PERFORMANCE STEP: CRITICAL xx NOT CRITICAL 3.2.2

3. 2.2 NOTIFY ... .. .the ODS, ODS, utilizing the "Direct Ring-Down" Ring-Down "

telephone or at extension 5-751-1700 or 5-751-2495.

5-751-2495 ,

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

AND FAX ...

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

5-751-8620.

I CUE:

CUE: Faxing to the ODS will be simulated STANDARD:

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 3.2.3 IF ... the ODS was contacted, NOT CRITICAL x THEN ... the State of Alabama notification action is complete.

AND RE-ENTER at Step 3.3. Otherwise continue.

STANDARD:

Continues to step 3.3.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 487TC REV. NO. 0 PAGE 11 of 21 PERFORMANCE STEP: CRITICAL NOTE NOT CRITICAL x

The State of Alabama shall be contacted within 15 minutes of the emergency classification.

3.2.4 IF ... the ODS cannot be contacted within 10 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.

STANDARD:

N/A - ODS was contacted.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO.

NO. 487TC REV. NO. 0 PAGE 12 of21of 21 PERFORMANCE STEP: CRITICAL NOT CRITICAL x 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 completed.. Do this concurrently with the implementation of this procedure.

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

STANDARD:

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

SAT UNSAT N/A _ _ COMMENTS:_ _ _ _ __ ___

JPM NO. 487TC REV. NO. 0 PAGE 13 of21 CAUTION 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 x 3.4 Notification of Site Personnel 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.

STANDARD:

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: _ _ _ _ __

JPM NO. 487TC REV. NO. 0 PAGE 140f21 14 of 21 CAUTION Do not initiate Assembly / Accountability when:

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

Rapid

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

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

with this procedure.

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

procedure.

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

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

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

Acknowledges that STA is performing EPIP-8 and continues to step 3.6 SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __ ___

JPM NO. 487TC REV.

REV. NO.NO.O0 PAGE 15 of 21 PERFORMANCE STEP: CRITICAL NOT CRITICAL x 3.6 Dose Assessment EVALUATE ... the need for dose assessment.

IF ... dose assessment is needed needed,,

THEN ... CONTACT, if operational, operational , the Central Emergency Control Center (CECC) at 5-751-1614.

OR operational, 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 Is not operational at this time. I STANDARD:

SRO/SED acknowledges that the CECC is not staffed and contacts the Radiological Protection Shift Supervisor and request the implementation of EPIP-1 EPIP-13 3 if deemed necessary.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ __ __ ___

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

3.7 CRITICAL x Notification of the Nuclear Regulatory Commission (NRC)

NOT CRITICAL 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.

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.

STANDARD:

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 xx 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.

instructed. This action may be delegated.

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, completed ,

placekeeping place keeping blocks checked as instructed instructed..

SAT UNSAT N/A _ _ COMMENTS:

COMMENTS: _ _ _ __ __ ___

JPM NO.

NO. 487TC REV.

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

plant conditions.

Utilize Appendix C to monitor/re-evaluate and communicate plant conditions and significant changes.

changes. Significant changes in plant conditions are at a minimum when other EAL conditions exist indicating the current classification.

emergency classification.

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

END OF TASK STOP TIME _ _ _ _ ___

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

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

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

SAT UNSAT N/A _ _ COMMENTS: _ __ __ __ __ _ ___

- - - - "II ' ' It A****A AIt It A1t'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 20 of 21

I Browns Ferry SITE AREA EMERGENCY Appendix A EPIP-4 Page 1 of 1 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 o Releases above federally approved limits 1 limits 1

.Release information not known

Release information not known CTech Specs) 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

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

IN*SIMULATOR:

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).

applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

complete.

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

INITIAL CONDITIONS: You are the Shift Manager. Unit 3 was operating at 100% 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~' 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. conditions. EOI-1 and 2 are in progress due an unidentified leak in the Drywell Orywell causing High Drywell Orywell pressure that is trending upwards.

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 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. Drywell Orywell PressurefTemperature and Torus PressurefTemperature are trending upwards, upwards. The crew has been unable to get a Orywell or Torus spray system to operate. Using the following parameters provided to Drywell 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 staffed.. (NOTE:

Unit 3 conditions are deteriorating.)

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

OW Radiation RR-90-256 slowly rising (prior to isolation)

OW Leakage Rate unknown at this time OW Temperature 242 0 F and slowly rising Torus Temperature 245 0 F Torus Pressure 30 psig and rising Torus Level 15 feet Wind Speed 5 mph from the SW Venting Torus per APP 12 (SOME portions of this JPM are TIME CRITICAL)

ML092870774

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