Text

Final - Section a Operating Exam (Folder 3)
	ML081330603
Person / Time
Site:	Oyster Creek
Issue date:	03/28/2008
From:	Ludlam G; AmerGen Energy Co
To:	Caruso J; Operations Branch I
	Hansell S
Shared Package
ML072851077	List: IR 05000219/2008301; ML073450458; ML080980369; ML081330603; ML081330610; ML081330618; ML081330623; ML081330625; ML081330642; ML081330652; ML081330656; ML081330659; ML081330660; ML081900466; RA-08-009, Draft - Outlines (Folder 2) (Facility Ltr. Dtd. - 01/16/08), Submittal of Initial Operator Licensing Examination Outline;
References
	50-219/08-301, U01688
	Download: ML081330603 (121)
	v • d • e

w

- Appendix C Job Performance Measure Form ES-C-1 WORKSt-i EET Facility: Oyster Creek-- Task No.: COO00030 __-

Task

Title:

_Review

_ _ - a_Shift

_ ~Turnover

~ Checklist

~ ~ - ___. -

Job Performance Measure No.: NRC JF'M. ADMIN SROl

_ _ __ [SRO)

-_ -~

WA

Reference:

Generic 2.1,3(SRO

-- 3.4) __

Examinee: ~ ~ ~

Examiner: _ -~

Facility Evaluator: ~ - - - [late: _ - __~______ - _- -

Method of Testing:

Simulated Performance - ~ - Actual Performance ~

X Classroom X Simulator ~ ___ - ~ Plant ~ ~ -~

Read to the Examinee:

1 will explain the initial conditions, which stieps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. The plant is at rated power with all Rec:irculation Pumps on.

2. You are the oncoming Unit Supervisor after being off for the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3. Your last shift was completed at 2400 on April 18, 2008.

4. The current datehime is April 19, 2008 at 1200.

Task Standard: The Candidate has reviewed the turnover checklist and noted the discrepancies and any associated actions.

Required Materials: None General

References:

1. OP-OC-100-1002, Main Control Room Turnover Checklist (Operating Mode), revision 5.

2. Technical Specifications 3.7, Auxiliary Electrical Power.

3. Procedure OP-OC-108-104-1001,(Guidancefor Limiting and Administrative Conditions for Operations, revision 0.

4. Procedure 324, Thermal Dilution Pumps, revision 69.

NRC JPM ADMlN SROl Page 1 of 15

' Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: As the oncoming Unit Supervisor, review the completed Main Control Room Turnover Checklist (Operating Mode) and note any discrepancies and/or any required actions. Provide any responses on the handout.

Time Critical Task: No.

Validation Time: 22 minutes NRC JPM ADMIN SRO1 Page 2 of 15

c Appendix C Job Performance Measure Form ES-C-1 WORKSHEET

- _ _ ~-

Performance lriformation Denote critical steps with a check mark 4 Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. Provide the1 completed Turnover Sheet.

Comment:

Note: The following steps may be performed in any order.

J Performance Step: 2 Procedure Step: Reviews thle Turnover Checklist.

Standard: Reviews the Turnover Checklist and notes the following:

The TORUS/DW VENT & PURGE ISOL VLVS HI RAD BYP CHAN 2 switch position is not annotated. (The switch should be in NORMAL.)

Comment:

~ - _ _ _ __ _ _ - - _ _ _ _ - - ~ - - ______ - - ~- -

~ ~ _ _ _ -_- -_ _ - - _-___~-~~ - . -_ _

- - ~ -~ -___ _ _ ._ _

SAT/UNSAT NRC JPM ADMIN SRO1 Page 3 of 15

c Appendix C Job Performance Measure Form ES-C-I WORKSHEET Performance Information J Performance Step: 3

~- ~-

Procedure Step: Reviews the Turnover Checklist.

Standard: Reviews the Turnover Checklist and notes the following:

Technical Specification 3.7.C.2 states that if one diesel generator becomes inoperable during power operation, repairs shall be initiated immediately and the other diesel shall be operated at least one hour every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at greater than 80% rated load until repairs are completed.

Procedure OP-OC-I08-104-1001, Guidance for Limiting and Administrative Conditions for Operations, states that EDG 2 shall be satisfactorily tested by 2000 on April 19, 2008. This is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from when EGD 1 was declared inoperable - not 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from when EDG 1 was tagged out for repair. To comply with Technical Specifications, EDG 2 needs to be tested (636.4.013, EDG 2 Load Test) by 2000 on April 19, 21008.

Comment:

~- ~

SAT/UNSAT NRC JPM ADMIN SRO1 Page 4 of 15

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET performance lriformation J Performance Step: 4 Procedure Step: Reviews the Turnover Checklist.

Standard: Reviews the Reactor Core State Parameters printout and notes the following:

0 IAW Core Thermal Limits Verification of Procedure 202.1, Power Operation, the thermal limits shall be reviewed and compared against Column C of Attachment 202.1-5. This comparison shows that MAPLHGR (currently at 100.01) is above the limiting value of 100. The actions from Column C include the following:

o Follow the requirements of TS 3.10 as applicable; During POWER OPERATION the maximum AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHlGR) for each fuel type as a function of exposure shall not exceed the limits specified in the CORE OPERATING LIMITS REPORT (COLR)

If any time during POWER OPERATION it is determined b y normal surveillance that the limiting value for APL-HGR is being exceeded, action shall be initiated to restore operation to within the prescribed limits. If the APLHGR is not returned to within the prescribed limits within two hours, action shall initiated to bring the reactor to the COLD SHUTDOWN CONDITION within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . During this period surveillance and corresponding action shall continue until reactor operation is within the prescribed limits at which time POWER OPERATION may be continued.

o Notify Manager Reactor Engineering and Director Operat ions.

Comment:

- - - ~- - ~ -~ - ~ -

JPM Stop Time:

NRC JPM ADMIN SRO1 Page 5 of 15

rcI Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: _NRC

- ~ J P Y P(DM!!!-SR!-_-._

Examinees Name: ~ - _ _ _

Examiners Name: _ _ _ - _

Date Performed: _ ~ . __ - _

Facility Evaluator: ~_ __

Number of Attempts: _._____ -~ _~

-rime to Complete: __ _____

Question:

Response

Result: SatisfactoryAJnsatisfactory Examiners Signature and Date: ~_ __ _- - ~ - -

NRC JPM ADMIN SRO1 Page 6 of 15

I . Appendix C Job Performance Measure Form ES-C-1 WORKSI-I1EET Sim ulato r Set up

1. None.

2. Include a cope of Core State Parameters Admin SROl along with the Student Handout and the Turnover sheet to the candidate at the start of this JPM.

NRC JPM ADMIN SROl Page 7 of 15

AppendixC Job Performance Measure Form ES-C-1 WORKSHIEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power with all Recirculation Pumps on.

2. You are the oncoming Unit Supervisor after being off for the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3. Your last shift was completed at 2400 on April 18, 2008.

4. The current datehime is April 19, 2008 at 1200.

Task Cue:

As the oncoming Unit Supervisor, review the completed Main Control Room Turnover Checklist (Operating Mode) arid note any discrepancies and/or any required actions. Provide any responses on the handout.

NRC JPM ADMlN SROl Page 8 of 15

0P-0c-100-1002 Revision 5 DCC FILE if 20.70.01.01.03 MAIN CONTROL ROOM 'TURNOVER CHECKLIST (0PERAT1PJ G MODE)

_ _ _ _ ~ _- __.- _ _ _ ~ _ ___ _ _ _ - -__ - -

i Reactor Hi/Lo Level Bistable Test and Calibration, 619.3 113 I

Survetllance(s) in progress 1 Stack RAGEMS Sample

-- - - and-Effluent

- Flow - Functional Test, 621 3 024 i

I

- 1 1 _ _ _ _ . _ _ _ _7 I

Main Generator

- _ _Exciter Brush Inspection 4

FireHose Station, Plose House and Fire Hydrant Inspection, 645 6.003,-

Activities in progress

---LA I

1 -___-________ Safety System Status -___________

Identify \y\tem or component\ that are in a degraded mode of' o p e r a h pcrnizted by the 1echiiic:ll Specificationr. For each \y$tem, compare the length of time it is degraded with the Technical Specification Action Statcmenl. Specifj the frequency of redundant sj\tem verification or testing and

, APRM 1 is in BYPASS due to failure of the APRM Surveillar.lce Test - Front Panel Check (620.4 002) All other thcdate/tk o f i w ! % E - ~ ~ - _ --_ _ _____

I APRMs

- operable. --_ - - - - -

, EDG 1 tagged - outofservice

_- at53E-on

- - - 4/18/08.

- - ._ 7- - d a y C--O . EDG - 2 testixevery__- 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months - - - . __ -- - -

Compensatory Comments __--

k a n y compenmtory action\ in effect as a result of'l'rocedure CC-AA-112 ('I enip Mod), Procedure WC-AA-101 (On-Line Maintenance). out of wrvice plant eqnipment or components, or as directed by the SM or OS. _____

k D G 2 and associated systems -are --

protected IAW--- Procedure

- _ _ 341 due to -EDG _ _1 inoperable.

t - - - - - - - - -

Recording Offgas Radiation Monitor levels every hour due to AOG

- - -- trip. No adverse

- - - - trends. noted-1 ___-..__

Turnover Comments _____ _____ __.__ ______

EDG 1 declared inoperable at 2000 on 4/18/08, and tagged :)ut for repair at 2300 on 4/18/08 Electrical Maintenance

~ reports a ground in the control system and is continuing to investigate. There IS currently no estimate on the return-to-service time IAW Technical Specifications, EDG 2 must complete a satisfactory surveillance by 2300 on 4119/08 I (AnnuncJators T4bLT5bJ - -- . - - - - -_- - - - --_ __

I -- -- - --- - -- - - - - - -

AOG tripped 1600 4/18/08 and remains outofserice -41required actions completed. (Annunciators 10F3b. 1OXF3d 1 1OXF4d).

NRC JPM ADMIN SRO1 Page 9 of 15

OP -0c-100-1002 Revision 5 DCC FILE # 20.70.01.01.03 1 ~

Shift I

__J--

osfi slsul(

Shift * ' Unit Supervisor

i

Signature acknowledges all qualifications to stand watch are current and any changes in medical status have been reported IAW OP-AA-I05-101.

N R C JPM ADMIN SROl Page 10 of 15

I

. 0P-0c-100-1002 Revision 5 DCC FILE # 20.70.01.010 3 MAIN CON'I'ROL ROOM TURNOVER CHECKLIST

((IONTIN IJEI))

-~

I .

EDG2satus

- - ~-_.__- _______

V-24-29 isolationIsTgnal bypass switch in n o r - a l V-24-30 isolation sigEl bypass switch in normal TORUS/DW VENT & PURGE ISOL VLVS HI RAD BYP CHAN 1 in normal TORUSIDW VENT &PURGE ISOLVLVS H I R BYP CHAN 2 in normal --

- ._- _ ~- - _ - - -~

2anel11R EF 1-8control switch in auto EF 1-9control switch in auto Panel 13R Pond Pump select switch One pump - - in - auto,

- one - - - pump in manual-

- ~ - - -

Panel I ~XR - 1 CNTMT VENT AND PURGE isolATloN X

BYPASS in normal Panel

- 11XR ___.

Main Generator Digital Protective Re1 (DPRS A and 8) operating with n indications ___---____

Panels 12XR, Confirm

~

~-

~

13R714R (rear fans on rear of panels

_~

- _ _ of panels)__

~

operating

-_ 7-7x - l Y j i - ---E_I_--

-- _ !NO -

I NRC JPM ADMIN SROl Page 11 of 15

0P-0c-100-1002 Revision 5 DCC FILE # 20.70.01.01.03 General

- - - Turnover

__ - Checks Core Maneuvering Daily instruction Sheet, Attachment 1001.22-3 and reflectsplant_operati_ngconditions. - -

Control room panel walkdown_perfofmed_neat-end ofshift.

--- ~

Reviewed reasons for annun-ciated-alarms with all operators - _ -- _

Control room panel walkdown performed withoncoming shift_ - ~- Yes Performed light test on alarm windows.

- _ - - ~- ~

Yes NRC JPM ADMlN SROl Page 12 of 15

a : 0P-0c-100-1002 Revision 5 DCC FILE 11 20.70.01.01.03 Control Room ,Alarm Sheet Page 1 Shift 0000 - 1200 Date 41 19/08 A 13 C 1) E I' i r- I 1p-r-r 1 x i t t ; ' I I A 13 C I) E I+'

NRC JPM ADMlN SROl Page 13 of 15

0P-0c-100-1002 Revision 5 DCC FILE # 20.70.01.01.03 Control Room Alarm Sheet Page2 A I3 C D E 17 A I3 C I) E F 9XF A 13 C 1) E F A R C D E F G H K M 1

2 3

4 1011' 5 6

7 8

9 F

10 1 2 3 4 11 12 12F R0 Remarks Reviewed By: -

NRC JPM ADMIN SROl Page 14 of 15

STUDENT HANDOUT Name: Date:

NRC JPM ADMlN SRO1 Page 15 of 15

VI I

eeI k

Y u

e I_

I Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Job Performance Measure No.: NRC JFM ADMIN_SR02/SBFl

~

WA

Reference:

Generic 2.1.141SRO

~- . __ 3.31_ _ __

Facility Evaluator: Date: _________ ---_ --

Method of Testing:

Simulated Performance - - Actual Performance X Classroom _X Simulator - Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Init ial Conditions:

1. A plant startup is in progress.

2. The REACTOR MODE SELECTOR switch is in STARTUP

3. All IRMs indicate midscale on Range 8.

4. All APRMs indicate 1%.

5. Annunciator 9XF7d, 24 VDC PP-A PWR LOST alarmed 20 minutes ago.

6. Electrical maintenance suspects a short circuit.

7. The current datehime is April 19, 2008 at 1000.

8. A recovery plan has not been established.

Task Standard: The Candidate completes the Shift Managers Notification Worksheet IAW OP-AA-106-101, Significant Event Reporting, and determines notification is required due to an unexpected /2 scram and entry into a 5 72-hour shutdown LCO.

Required Materials: None.

NRC JPM ADMlN SR02 Page 1 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET General

References:

1. Technical Specifications. (have available)

2. Procedure OP-AA-106-101, Significant Event Reporting, revision 8.

(handout)

3. Procedure RAP-SXF7d, 24 VDC PP-A LOST, revision 0. (handout)

4. Procedure OP-OC-108-104-1001, Guidance for Limiting and Administrative Conditions for Operations, revision 0.

5. EP-AA-1010, Exelon Nuclear Radiollogical Emergency Plan Annex for Oyster Creek Station, revision 0 (have available)

6. Exelon Reportability Manual Initiating Cue: Complete Attachment 2, Shift Manager's Notification Worksheet, of OP-AA-106-101, Significant Event Reporting, for receipt of the 24 VDC PP-A PWR LOST annunciator. Determine who the Shift Manager notifies of this event and why. Determining the requirement for i i written report and LER will be performed by another Operator.

Time Critical Task: No.

Validation Time: 22 minutes NRC JPM ADMIN SR02 Page 2 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKStIEET Performance Information Denote critical steps with a check mark J Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

Performance Step: 2 Procedure Step: Record datehime of the event on Attachment 2.

Standard: Records datehime of the event on Attachment 2 as 4/19/08 1000.

Note: Completion of the Attachment may be performed in any order Comment:

__ ~- - __- _ _ ___ _ - -_

NRC JPM ADMIN SR02 Page 3 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance lriformation

~ - ~~ ~

Performance Step: 3

~- ___-~

Procedure Step: Records current power/mode on Attachment 2.

Standard: Records current power/mode on Attachment 2 as 1%, Startup, or midscale on Range 8 of the IRMs, Startup.

Note: Only Performance Step 3 or performance Step 4 is critical, with STARTUP mode listed.

Comment:

SAT/U NSAT Performance Step: 4 Procedure Step: Records prior power/mode on Attachment 2.

Standard: Records prior power/mode on Attachment 2 as 1%, Startup, or midscale on Range 8 of the IRMs, Startup.

Comment:

NRC JPM ADMIN SR02 Page 4 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance lriformation Performance Step: 5

~

Procedure Step: Records description.

Standard: Records a short description of the event: receipt of annunciator 24 VDC PP-A LOST, or loss of 24 VDC PP-A, or similar wording. The description may contain the plant impact of YZ scram as well.

Comment:

Performance Step: 6 Procedure Step: Determines, if the event requires an EP declaration.

Standard: Determines that the event does not require an EP declaration.

Comment:

_ - . ~~~- _ - _ ~ _ - . ~

NRC JPM ADMIN SR02 Page 5 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKS ti EET Performance Information Performance Step: 7 Procedure Step: Determines if the event requires reporting to the NRC via ENS or to an outside agency per the Exelon Reportability Reference Manual.

Standard: Determines that the event does not require reporting to the NRC via ENS or to an outside agency per the Exelon Reportability Reference Manual.

Comment:

~ - - . ~ ~ - - ~ _ - - ~-_ -_ --

Performance Step: 8 Procedure Step: Determines if an oil discharge intohpon waters or adjoining shoreline.

Standard: Determines there is no oil discharge intohpon waters or adjoining shoreline.

Comment:

NRC JPM ADMIN SR02 Page 6 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKS ti EET Performance Information Performance Step: 9 Procedure Step: Determines if a leak or discharge of petroleum product or hazardous substance from the warehouse drop tank; or a spill or discharge of hazardous materials in a quantity that constitutes a reportable discharge into or upon surface waters, groundwater, or onto the ground.

Standard: Determines there is no leak or discharge of petroleum product or hazardous substance from the warehouse drop tank; or a spill or discharge of hazardous materials in a quantity that constitutes a reportable discharge into or iupon surface waters, groundwater, or onto the ground.

Comment:

Performance Step: 10

- ~-

Procedure Step: Determines if a release of designated hazardous substances in amounts equal to or in excess of EPA reportable quantity.

Standard: Determines no release of designated hazardous substances in amounts equal to or in excess of EPA reportable quantity.

NRC JPM ADMIN SR02 Page 7 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: Determines if any of the following occurred:

RCRA Program Exception Fieport submitted, or Environmental Noncompliance endangering health or environment.

Standard: Determines none of the following occurred: RCRA Program Exception Report submitted, or Environmental Noncompliance endangering health or environment.

Comment:

Performance Step: 12 Procedure Step: Determines if the event is threatening health or environment or release equal to or in excess of EPA reportable quantity.

Standard: Determines the event is not threatening health or environment or release equal to or in excess of EPA reportable quantity.

Comment:

NRC JPM ADMIN SR02 Page 8 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 13

~

Procedure Step: Determines' if any of the following occurred: loss of 10 or more sirens, or spurious activation signal with 1 or more sirens still sounding.

Standard: Determines none of the following occurred: loss of 10 or more sirens, or spurious activation signal with 1 or more sirens still sounding.

Comment:

SAT/UNSAT J Performance Step: 14 Procedure Step: Determines if any of the following occurred:

reactivity management event; hazardous material incident; fitness for duty; injury resulting in olfsite medical attention; major enforcement action; non-routine communication to/from the NRC; reactor water condition above EPRl Action Level II; any event outside the plant design basis; any event proceeds differently than expected: unexpected '/2 scram, unexpected and significant plant transient, LCO action that will not be met within deadline, initiation of a prompt investigation, or, an unexplained risk change.

Standard: Determines that an unexpected '/2 scram has occurred. Checks YES to perform notifications and notifies the SOS/OD, DSM, and NRC Resident Inspector. The candidate may also determine that an unexplained risk change has occurred.

Comment:

NRC JPM ADMIN SR02 Page 9 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKS HIEET Performance Information J Performance Step: 15

~~

Procedure Step: Determines if any of the following occurred: the event forced entry into a 5 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months shutdown LCO; the event forced a plant shutdown or unplanned power reduction; the event involved a significant breakdown of plant radiological or environmental controls.

Standard: Procedure Step: Determines that the event forced entry into a 5 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months shutdown LCO (loss of this Bus is a 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months shutdown IAW TS 3.7.6. Checks YES to perform notifications and notifies the SOWOD, DSM, and NRC Resident Inspector.

Comment:

.~ .

SAT/U NSAT NRC JPM ADMIN SR02 Page 10 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 16 Procedure Step: Determines if any of the TS 6.9.3 Unique Reportability Requirements (occurred.

Standard: Determines that none of the TS 6.9.3 Unique Reportability Requirements occurred.

Comment:

JPM Stop Time:

NRC JPM ADMlN SR02 Page 11 of 14

Appendix C Job Performance Measure Form ES-C-1 W 0R KSkil EET Va Iidat ion of Comp Iet ion JPM Number: NRC JPM ADMIN SR02 Examinees Name:

Date Performed: ~~ ~ -- ._

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date: - - - _ --

NRC JPM ADMlN SR02 Page 12 of 14

_ __ _ ~ _ _. -

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulato r Setup

1. None.

2. Have a clean copy of Procedure OP-AA-106-101, Significant Event Reporting, and RAP-SXF7d, 24 VDC; PP-A LOST as handouts to the Candidate.

NRC JPM ADMIN SR02 Page 13 of 14

Appendix C Job Performance Measure Form ES-C-1 WORKS I- EET

__ ~~~

STUDENT HANDOUT Initial Conditions:

1 . A plant startup is in progress.

2 . The REACTOR MODE SELECTOR switch is in STARTUP.

3. All IRMs indicate midscale on Range 8 .

4. All APRMs indicate 1%.

5. Annunciator 9XF7d, 24 VDC PP-A PWR LOST alarmed 20 minutes.

6. Electrical maintenance suspects a short circuit.

7. The current datehime is April 19, 2008 at 1000.

8 . A recovery plan has not been established.

Task Cue:

Complete Attachment 2, Shift Managers Notification Worksheet, of OP-AA-106-101, Significant Event Reporting, for receipt of the 24 VDC PP-A PWR LOST annunciator.

Determine who the Shift Manager notifies of this event and why.

Determining the requirement for a written report and LER will be performed by another Operator.

NRC JPM ADMlN S R 0 2 Page 14 of 14

OP-AA-106-101 Revision 8 Page 8 of 14 Attachment 2

- Notification Worksheet Shift Manager's Page 1 of 5 rD&TE/TLME of Event I EVENT DESCRIPTION (use additional paper as necessary)

I J 1

_ ~ _ ____

Does the event / condition require an EP Declaration?

YES, Perform required communications after completing notifications required per site specific EP procedures Notify:

SOS I OD NRC Operations Center Duty Station Manager (DSM)

PM SVP NDO

~.. -

Time Date and Time all notification:

have been completed by DSW Manager, Reg. Assurance Group ANI and INPO (Alert or higher EAL)

N R C Senior Resident Inspector Does the event I condition require reporting to If time permits Independent SRO peer check Time 1 the NRC via ENS or to an outside agency per completed NRC Form 361 Exelon Reportability Reference Manual?

SRO Signature Notify 1 1 YES, Perform the following 3 sos / OD Date and Time all notification:

N R C Operations Center have been completed by DSPu DSM 9 PM 1 SVP NDO I

=

Manager, Reg Assurance Group Manager, Nuclear Oversight Group Communication (as required)

Environmental (as required) 1

1. NRC Senior Resident Inspector

OP-AA-106-101 Revision 8 Page 9 of 14 Att a c PIrnent 2 Shift Mana cj- er's N cltifi cat ion Worksheet

_________ ____- P N-e~ of _

2_ 5_ __.

?

Notify Time Did the following eventsicondition occur?

Oil discharge intoiupon navigable waters o sos / OD adjoining shoreline National Response Center (EPA)

EPA I ] YES, Perform notifications + N R C Operations (3enter DSM

= PM Date and Time all notifications Oyster Creek Only 1 SVP have been completed by D S M NOTE Refer to Attachment 3 for additional notification and reporting iristructionb

' NDO Manager, Reg Assurance Group First Energy (,JCP&L) (Oyster Creek Only)

N R C Senior Resident Inspector Oyster Creek Only Notify. Date N I D b SOS / O D Did any of the following events/conditions State DEP xcur?

Ocean County Hecilth Department NRC Operations Center A leak or discharge of petroleum prod or hazardous substance from the DSM -L--

Date and Time all notifications warehouse drop tank 9 PM have been completed by D S M 1 SVP

Spill or discharge of hazardous mater in a quantity that constitutes a reporta discharge into or upon surface waters groundwater, or onto the ground (incl

.' NDO Manager, Reg. Assurance Group First Energy (..ICP&L)

Petroleum products) 1 YES, Perform notifications 3 NOTE Relcr to Attachment 3 for additional notification and reportinq iristructions NRC Senior Resident Inspector I 1

~.

3id the following eventskondition o c c F Notify T--- Time A

ielease of designated hazardous substant S O S / OD n amounts equal to or in excess of a EPA National Response Center (EPA) eportable quantity State DEP 1 YES. Perform notifications 3 Lacey Twp Police (Oyster Creek Only)

Oyster Creek Only NRC Operations Center DSM Date and Time all notifications PM 1 SVP have been completed by D S M licfcr to Attachmenl 3 for additional notitication and reporting instructions NDO

' Manager, Reg Assurance Group First Energy (JCP&L) (Oyster Creek Only)

N R C Senior Residcbnt Inspector

OP-AA-106-101 Revision 8 Page 10 of 14 Attachment 2 Shift Managers Ncitification Worksheet Page 3 of 5

______ - - _ - _- I _. _ _ __._

Did any of the following events / conditions- Notify. Date Time occur?

SOS / OD RCRA Program Exception Report State DEP Submitted Environmental Noncompliance NRC Operations Center endangering health or Environment DSM 1 PM

-t----I 1 1 YES, Perform notifications 3 1 SVP NDO Manager, Reg Assurance Group have been completed by D S M NRC Senior Resident InsDector Hcferto Attdchrncnt 3 lor additional nclifiLdticndnd reporting Instructions Did any of the following events / conditions- Notify Date Time occur?

SOS / OD Incident threatening health or environment or National Response Center release equal lo or in excess of EPA reportable quantity State DEP NRC Operations Center j 1 YES, Perform notifications 3 3SM 1 PM have been completed by DSM Oyster Creek Only SVP NOTt 1 NDO Manager, Reg Assurance Group Hcfer to Atlachrnerit 3 lor additional notification and reporling instructions VRC Senior Resident Inspector Votlfy. Time Oyster Creek Only 30s I OD 3cean County Police Dispatcher

+--*

Did the following eventsicondition occur?

Loss of ? O or more sirens I R C Operations Ccnter Spurious activation signal with 1 or more ISM sirens still sounding I PM

[ ] YES, Perform notifications 3 SVP NDO Manager, Reg Assurance Group Rcler to Attachrncnt 3 for additional notification and reporting instructions I R C Senior Resident Inspector

OP-AA-106-101 Revision 8 Page 11 of 14 Attachment 2 Shift Managers Notification Worksheet Page 4 of 5 Did any of the following events/conditions occur7 Nutify 1 Reactivity management event per OP-AA-300 1540 SOS I OD 2 HaLardous material incident Date and Time all 3 Sentinal / Oram Risk level is / or is planned to be ORANGE D:;M I/

notifications have been or RED 4 Fitness-for-duty event . PM SVP completed by DSM 5 Injury resulting in offsite medical attention 1 NDO 6 Major enforcement action fine. or other sanction, serious operating event that could result in such action, including Manager, Nuclear Oversighr 7

events which have been or maybe brought to NRC upper management attention Non-routine communications to / from NRC

- Group Communication (as required)

Environmental (as required) 8 Reactor Water Chemistry above or at EPRI Action Level II 4

Any event or operation condition outside plant design basis

I----

9 NKC Semor Resident Inspector 10 Any event that proceeds differently than expected

@ Unexpected Y2 scram b Unexpected, significant plant transient c LCO action that will not be met within deadline d Initiation of a prompt investigation e Unplanned Risk Change I ~ E s Perform

. notifications 3 i l Did the eventkondition force entry into a (72hour Notify - Time shutdown LCO7 SO!; / OD 2 Did the eventlcondition force a plant shutdown or unplanned power reduction7 le Power reductions required due to high discharge DSM J Work Week Manager Director Work Mgmt (via WWM) notifications have been completed by DSM temperature or required to perform an activity such as main Eng Duty Manager condenser backwashing 3 Did the eventicondition involve a significant breakdown of plant radiological or environmental controls7 PM SVP NDO Manager Nuclear Oversight Group

/YES, Perform notifications URI: Senior Resident Inspector J

- _ _ ~ - _ _ - -

OP-AA-106-101 Revision 8 Page 12 of 14 Attachment 2 Shift Manager's Ncltification Worksheet Page 5 of 5 Notify: Time Oyster Creek Only SOS OD Date and Time all notifications Did any of the following TS 6 9 3 Unique Reportability have been completed by D S M Requirement events occur7 Leak test on a sealed source that yielded 20 005 pCi of removable contamination A reportable event pursuant to the ODCM EMRV or Safety Valve challenge or failure (non LER DSM 9

Work Week Manager Director ,Work Mgmt. (via reportable)

WWM) a A challenge is an automatic actuation outside 1 Eng Duty Manager (via purposeful surveillance or testing VdWM)

PM b A special reporl is to be sent to the NRC within 60 ' SVP days 1 hDO Manager, Nuclear Oversight Any of the following SLC (Liquid Poison) Technical Group Specification conditions a .32C3(b) b 32C3(e)(i) c 42E5 Inoperable high-range radioactive noble gas effluent monitor (TS 3 13 H)

[ ] YES, Perform notifications 3 NRC Senior Resident Inspector REQUIRED WRITTEN REPORT I LICENSEE EVENT REPORT CHECK ONE REPORT DUE WITHIN CHECK ONE REPORT DUE WITHIN

-1 REQUIRED U 30DAYS U REQUIRED U 30DAYS

-I NOT REQUIRED I L1 NOTREQUIRED U 60DAYS OTHER _.

3 . AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No.: 2260201402 Task

Title:

Review Acceptance

-~~ _ - -- Criteria_ _ for

_ _a- -Completed

~ Surveillance Test Job Performance Measure No.: _NRC JPlM ADMIN SR03 WA

Reference:

Generic 2.2.12.(SRO - - - 3.4)

Examinee: - - - _ _ Examiner: _. - . __ -

Facility Evaluator: - -

Method of Testing:

Simulated Performance _~ - .~ Actual Performance __ X-Classroom X Simulator ~ - __- Plant ~

Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

1. The plant is at rated power.

2. Surveillance test, 607.4.004, Containment Spray and Emergency Service Water System 1 Pump Operability and C:omprehensive/Preservice/Post-Maintenance Inservice Test, has just belen completed.

3. The test was a normally scheduled test.

Task Standard: The Candidate reviews the surveillance test Acceptance Criteria, recognizes the component discrepancies, and states the required action for each component discrepancy.

Required Materials: None.

General

References:

1 . Procedure 607.4.004, Containment Spray and Emergency Service Water System 1 Pump Operability and Cornprehensive/Preservice/Post-Maintenance Inservice Test, revision 62.

2. AD-AA-101, Processing of Procedures and T&RMs, revision 18.

NRC JPM ADMlN SR03 Page 1 of 10

I . AppendixC Job Performancle Measure Form ES-C-1 WORKSHEET Initiating Cue: Perform the Acceptance Criteria section of the completed surveillance test, 607.4.004. Write your observations on the attached sheets.

State any test discrepancies and any required actions for any noted discrepancy. Some Steps have already been evaluated as Satisfactory and are complete.

State if the step is SAT or UNSAT If UNSAT, state the reason and the required actions Time Critical Task: No.

Validation Time: 20 minutes.

NRC JPM ADMIN SR03 Page 2 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark 4 Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: ~-

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. Provide the Candidate with the section of the completed procedure and the attached sheets.

Comment:

NRC JPM ADMIN SR03 Page 3 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET ACCEPTANCE CRITERIA Step SATNNSAT Required Action if UNSAT/Reason 7.1.1 7.1.2

7.1.3 NOTEKUE

IF the Candidates do not state TS requirements, tell them to list the most limiting TS requirement.

7.1.4 UNSAT Incorrect use of temporary procedure change for TS CRITICAL surveillance acceptance criteria of ESW flow > 3000 gpm. Declare ESW Pump 52A inoperable and apply TS 3.4.C.4 due to low flow (15 day LCO from this inoperable component alone).

7.1.5 SAT None 7.1.6 SAT 7.2.1 SAT None NRC JPM ADMIN SR03 Page 4 of 10

, AppendixC Job Performance Measure Form ES-C-1 WORKSHEET ACCEPTANCE CRITERIA Step SATWNSAT R equired Act ion if UNSAT/R ea son 7.2.2 SAT 7.2.3 UNSAT Containment Spray Pump 51 6 vibration 4A is above the action range. Declare Containment Spray Pump CRITICAL 51 6 inoperable and apply TS 3.4.C.4 { 15 day LCO from this inoperable component alone). But, since more than 1 pump is inoperable in the same loop, the loop must be considered inoperable. IAW TS 3.4.C.3, a 7 day LCO now applies.

7.2.4 UNSAT Valve V-21-17 strokes outside the accept range but C R lTlCAL less than the limiting value. Retest immediately or declare inoperable and apply TS.

__ - - - - -~ ~ - - -- ~- - - - -

7.3 SAT None 7.4 SAT NRC JPM ADMIN SR03 Page 5 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC JPM ADMIN SIR03

-~~ ~ ~~ _ -

Examinees Name: - - _ _ - - __- - __ - - -

Examiners Name: _ _ - -- - - - --

Date Performed:

Facility Evaluator: ~ -~ _~~

Number of Attempts: __ ______

-rime to Complete: ~

Question:

Response :

Result: Satisfactory/Unsatisfactory Examiners Signature and Date: ~- - ._

NRC JPM ADMIN SR03 Page 6 of 10

. AppendixC Job Performance Measure Form ES-C-1 WORKSI-IEET Simulator Setup

1. None.

2. Provide pages 45 through E4-4 ONLY of 607.4.004. (Include a good page E2-1 since this page has been modiiied in the handout)

3. Make the following steps on the test:

a. Step 7.1.4: Lineout 3100 and insert 3000. Include TPC data.

b. On the IST Pump Summary Sheet table, insert ESW 52A flow at 3050 gpm. Have all other flows acceptable.

c. On the vibration table for point 4A for Containment Spray Pump 51 6, insert a value greater than the ACTION limit. Mark all other vibrations below the ALERT values. (0.26 in/sec)

d. In the valve stroke summary table, make the OPENING time for V-21-18 greater than the ACCEPT RANGE, but less than the LIMITING VALUE. Mark all others in the ACCEPT RANGE (37.4 seconds)

e. In the IST Valve Summary Sheet, lineout 3100 gpm and insert 3000 gpm for ESW Pump 52A flow. Initial and date.

NRC JPM ADMIN SR03 Page 7 of 10

~

. AppendixC Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power.

2. Surveillance test, 607.4.004, Containment Spray and Emergency Service Water Sys tem 1 Pump Operability and Comprehens ive/Preserv ice/Post-Maintenance lnservice Test, has just been completed.

3. The test was a normally scheduled test.

Task Cue:

Perform the Acceptance Criteria section of the completed surveillance test, 607.4.004. Write your observations on the attached sheets. State any test discrepancies and any required actions lor any noted discrepancy. Some Steps have already been evaluated as Satisfactory and are complete.

State if the step is SAT or UNSAT If UNSAT, state the reason and the required actions NRC JPM ADMIN SR03 Page 8 of 10

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT biANDOUT ACCEPTANCE CRITERIA Step SATNNSAT Required Act ion if UNSAT/Reason 7.1.1 SAT 7.1.2 SAT 7.1.3 SAT 7.1.4 NRC JPM ADMlN SR03 Page 9 of 10

. AppendixC Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT ACCEPTANCE CRITERIA Step SATNNSAT Required Action if UNSAT/Reason 7.2.2 7.2.4 NRC JPM ADMIN SR03 Page 10of 10

AmerGen An Exelon Company 1 OYSTER CREEK GENERATING STATION F'ROCEDURE Number 607.4.004 Title Revision No.

Containment Spray and Emergency Service Water System I 62 Pump Operability and Comprehensive I Presiervice I Post-Maintenance

- ~ __ - -lnservice

- ~~

Test cv InitiaIIVerifv 6.56 ALIGN heat exchanger instrument valves in accordance with Attachment 607.4.004-6. BB I 6.57 CONFIRM OPEN ESW Flow Gauge DPI-532-5 Isolation Valves V-3-569 and V-3-570. BB

____ I 6.58 RESTORE drywell pressure IAW Procedure 312. BB I 6.59 NOTIFY Chemistry Technician to check and adjust the injection rate of chlorine IAW Procedure 326. BB I 6.60 TRANSFER all pertinent data to Attachment 607.4.004-4. BB I 6.61 REVIEW the results of this test against Section 7.0 Acceptance Criteria. $23 I 6.62 RECORD commentsldiscrepancies on the Surveillance Review Form. BB I 7.0 ACCEPTANCE CRITERIA 7.1 The components tested by this procledure meet Tech. Spec.

operability requirements if the following criteria are met. If any are

-not met, consider the affected component inoperable and follow the requirements of Tech. Spec. Section 3.4.C and Procedure LS-AA-120:

7.1.1 Containment Spray System Discharge Pressure is 160 psig.

7.1.2 The Containment Spray and Emergency Service Water Pumps start and stop when given appropriate signals.

7.1.3 Each Containment Spray Heat Exchanger total differential pressure is (40 psid.

TPC 4231

' V 4/24/u8 1.4 Emergency service water flow rate as indicated on Plant

-7. Sisa& Process Computer Point ESW-12 is 2 m .

Today 30@%Pm I .1.5 Containment Spray water fliow rate is 24000 gpm.

45.8

AmerGen

~n i x c l o i ( u r n p a r y I

! OYSTER CREEK GENERATING STATION F'ROCEDURE Number 607.4.004 I

Title Revision No.

Containment Spray and Emergency Service Water System I Pump Operability and Comprehensive / Preslervice / Post-Maintenance

_ _ - - lnservice __ _ _ _ Test

_ -~ - ~ - ~

! 62 7.1.6 All motor operated valves operate as specified and all valve stroke times do not exceed the Limiting Value listed on Attachment 607.4.004-4.

NOTE When a component is Preservice (baseline) tested per the 1ST Program, new alert and action level values are established for that component. The alert/action levels associated with the old component (Attachment 607.4.004-4) should not be used to determine operability of the new component.

7.2 The components tested by this procedure meet In-Service Test (IST) requirements for operability if the following criteria are met. If any are not met, consider the component inoperable and follow the requirements of Tech Spec Section 3.4.C and Procedure LS-Ab,-120.

7.2.1 Containment Spray Pump flows are between the high and low action ranges as listed on the IST Pump Summary Sheet and IST Valve Summary Sheet (Attachment 607.4.004-4).

7.2.2 ESW pump flow values are between the high and low action ranges as listed on the IST Pump Summary Sheet and IST Valve Summary Sheet (Attachment 607.4.004-4).

7.2.3 ESW and Containment Spray Pump vibration readings are below the action range as listed on the Vibration Data Sheet (Attachment 607.4.004-4).

7.2.4 All valves on Attachment 607.4.004-4 meet the acceptance criteria 7.2.4.1 E a valve fails to stroke to the required position OR if its stroke time exceeds the limiting value of full stroke time specified in Attachment 607.4.004-2, THEN it shall be immediately declared inoperable and the requirements of Technical Specification 3.4C and Procedure LS-AA-120 shall be followed.

46.0

AmerGen I OYSTER CREEIK GENERATING Number Ai' ixelon Conipany STATION PROCEDURE 607.4.004 Title Revision No.

Containment Spray and Emergency Service Water System I 62 Pump Operability and Comprehensive / Presiervice / Post-Maintenance lnservice Test~ _ _ - -

- - - - _ _ - - __ - -__ -- - - __ -- - - -- - - _.I. .-

7.2.4.2 a valve fails to stroke to the required position within its acceptable range as specified in Attachment 607.4.OQ4-2, U T does @t exceed the limiting value of full stroke time specified in Attachment 607.4.004-2, THEN it shall ble immediately retested or declared inoperable, at the direction of the US.

1. -

IF the valve is declared inoperable, THEN the requirements of Technical Specification 3 4C and Procedure LS-AA-120 shall be followed.

2. -

IF ttie valve is retested AND it fails to stroke exceeds the limiting value of full stroke time, THEN it shall be immediately declared inoperable AND the requirements of Technical Specification 3.4C and Procedure LS-AA-120 shall be followed.

3. IF

- the valve is retested AND again fails to stroke within its acceptable range K T does not exceed the limiting value of full stroke tirne, THEN the data shall be analyzed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months to verify that the new stroke time represents acceptable operation, AND the requirements of Procedure LS-AA-120 shall be followed.

47.0

AmerGen, An txelon ( m i n a n y 1 OYSTER CREEK GENERATING STATION F'ROCEDURE Number 607.4.004 Title Revision No.

Containment Spray and Emergency Service 'Water System I 62 Pump Operability and Comprehensive / Preservice / Post-Mai ntenance

~ _ _ _I_nse _ _ _~rvice Test -- __

N0TE:If such verification is not performed within the 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months limit, the valve shall be declared inoperable aind the requirements of Technical Specification 3.4C and Procedure LS-AA-120 shall be met.

4. -

IF the valve is retested AND strokes within its acceptable range, THEN the cause of the initial deviation shall be analyzed and the results documented AND the requirements of Procedure LS-AA-120 shall be followed.

7.2.4.3 E excessive flow is observed from V-3-698, AND operating ESW Pump flow is 13100 gpm THEN the ESW system is operable and the keepfill line is not required to be isolated.

If the following criterion is not met, check the calibration of the affected Containment Spray Heat Exchanger Pressure gauges. If calibration checks are satisfactory, schedule the affected heat exchanger(s) for tube side cleaning as soon as practical.

7.3.1 The Containment Spray Heat Exchanger total AP 520 psid.

If any alert threshold is exceeded, or if the following criteria are met, or if any other deviation from proper operation is noted, initiate a CAP in accordance with Procedure LS-AA-120 (unless i3 CAP was issued previously):

7.4.1 Corner Room cooling fans start on appropriate signals.

7.4.2 All Heat Exchanger tube to shell AP's are 1 5 psid.

7.4.3 There is no leakage from Heat Exchanger Thermal Relief valves V-3-82, V-3-83, V-21-21 and V-21-22.

48.0

AmerGen OYSTER CREEK GENERATING Number A n ixelun rorripdn) STATION PROCEDURE 607.4.004 ~-

~ -

Title Revision No.

Containment Spray and Emergency Service Water System I 62 Pump Operability and Comprehensive / Preservice I Post-Maintenance lnservice -~ Test ~ ~ -~ -~ .~ - -- -

8.0 ATTACHMENT 8.1 607.4.004-1, ESW Pump Vibration Locations 8.2 607.4.004-2, Cont. Spray Pump Vibration Locations 8.3 607.4.004-3, Test Equipment 8.4 607.4.004-4, IST Pump Summary Sheet and IST Valve Summary Sheets 8.5 607.4.004-5, Cont. Spray and ESW Initial Instrumentation Valving.

8.6 607.4.004-6, Cont. Spray and ESW Final Instrumentation Valving 8.7 607.4.004-7, Heat Exchanger Differential Pressure Verification.

8.8 607.4.004-8, IST Valves 8.9 607.4.004-9, Preserv ice/BaseIine/Comp rehe nsive Test Inst ruments 49.0

merven OYSTER CREfiK GENERATING Iuel 1 1 I\UII I

An t d n n C o v p d n b STATION PROCEDURE 607.4.004 Title Revision No.

Containment Spray and Emergency Service Water System I 62 Pump Operability and Comprehensive / Preservice / Post-Maintenance lnservice Test ~~ ~

~-

ATTACH MENT 607.4.004- 1 ESW PUMP VIBRATION LOCATIONS Note: Accelerometer probe locations are the same for all (4) ESW Pumps.

1A 1H (probe faces north-south) (probe faces east-west)

E l -1

merven OYSTER CREEK GENERATING 1 1 I \ U I I luel An txeloti Cornpany STATION PROCEDURE 607.4.004 Title Revision No.

Containment Spray and Emergency Service Water System I 62 Pump Operability and Comprehensive / Preservice / Post-Maintenance

~~ __ - lnservice._Test

- - ~

~

- ~-~ ~- - _.... ..

ATTACHMENT 607.4.004-2 CONT. SPRAY PUMP AND MOTCIR VIBRATION LOCATIONS NOTE: HORIZONTAL POINTS MAY BE TAKEN FROM EITHER SIDE OF THE BEARING HOUSING E2-1

I \ UI 1 Iuel OYSl EH C R t k K t i E N t H A l l N G STATION PROCEDURE 607.4.004 Title Revision No.

Containment Spray and Emergency Service Water System I 62 Pump Operability and Comprehensive / Presiervice / Post-Maintenance

-~

lnservice Test ATTACH MENT 607.4.004-3 TEST EQUIFMENT Preferred Controlled / Calibrated Test Equipment CSI Model 2120 Vibration Instrument 1a-2120 6/2008 I

Wilcoxon AE793 Transducer 1 2A-AE793 I-CSI Model A0760GP Transducer 3A-aO760GT CSI Model A0220HF Transducer

-Wilcoxon Model

-~

_~ -

Wilcoxon Model 793R Transducer

. - ... ~

I ~ . ..-

I- - -

6/2008 tt-I.

- I- _ _

Engineering Alternates - Complete as Necessary Evaluation by: Date:

meruen OYSTER CREE:.K GENERA rlNG 1 I IVUlllUt;I I * -. An t x e oil Conpar y STATION PROCEDURE 607.4.004 Title Revision No.

Containment Spray and Emergency Service Water System I 62 Pump Operability and Comprehensive / Preservice / Post-Maintenance

-~ lnservice -- Test

- . -~ ~ ~ ~.

ATTACHMENT 607.4.004-4 IST PUMP

SUMMARY

SHEET Date of Test CONTAINMENT SPRAY FLOW Comprehensive Measured Comprehensive Lower Limit Pump (Step) Action Alert Flow (GPM) Action 51A (6.14.2 or 6.14.6.2 (4) 3800 1 3948 ,4100 N/A 4326

_I 51 B (6.35.2 or 4100 6.35.6.2 (4) 4326 ESW Fj-OW Comprehensive I

Comprehensive PPC Measured Pump (Step) I Action 1 Alert Flow (GPM) Alert 1 Action 52A (6.24.1.2) 2994 3058 3050 N/A I 3316 528 (6.44.1.2) 3034 3099 N/A 1 3360 E4-1

. *. -. cunerven OYSTER CHEt:K GENERAIING I\IUIIIUt?I Ar Lxelor orrip~r y STATION P ROCEDU RE 607.4.004 Revision No.

62 i

Measured Overall Reading, in/sec Action 51A (6.19. II 3H 3v II 0.22 0.21 I

.26

.24

.624

.576 I 4H I 0.18 I .205 ,492

,492

.306 51 B (6.19.1) I I 3H 0.18 1 .223 .534 I 3v I 0.15 I .183 .438 I 4H I 0.14 .183 .438 I 4v I 0.14 I .19 .456 1 4A I 0.26 I .1 _ I _

.24 _-

52A .224 ,538 (6.20.1)

. 184 ,440 1 2t-i I 0.20 I .220 .529 52B 1H 0.24

.308 I 70 (6.40.1)

I 1A I 0.11 I .158 ,378 I 2H I 0.21 .295 .70 E4--2

I I Iuel

.. -. lunerven O Y s r t R C R E E K ~ ~ E N E H A II \IU N ~~

A n lxelon C o r r ~ w i ry STATION PROCEDURE Title Containment Spray and Emergency Service Water System I 1 Revision No.

Pump Operability and Comprehensive / Preservice / Post-Maintenance lnservice - Test ~ ~ - -

I 62 ATTACHMENT 607.4.004-4 (contit i ued)

IST VALVE

SUMMARY

SHEET COMPONENT / POSITION PARAMETER (STEP) Acce pta nce C riteria TESTED / TESTED Pump 51 A Flow V-21-8 Closed (6.14.2) 4100 GPM V-21-10 Open Water Flowing from V-3-698 (6.16.7) (Initial One) Little or INo V-3-133 Closed X

little or no excessive Pump 51 B Shaft Rotation (6.1 1.8) -yesJno No Shaft Rotation V-21-8 Closed 23 Pump 52A Flow PPC V-3-67 Closed E;

Point ESW-12 J. V-3-68 Open (6.26) 3050 GPM 9?

Pump 525 Shaft Rotation (6.13.4) - y e s X n o No Shaft Rotation V-3-67 Closed Pump 515 Flow V-21-10 Closed (6.35.2) 4100 GPM -

> 4000GPM V-21-8 Open Pump 51A Shaft Rotation (6.32.8) - y e s X n o No Shaft Rotation V-21-10 Closed Pump 52B Flow PPC Point ESW-12 -

> 3100 GPM V-3-68 Closed V-3-67 Open (6.46) 3200 GPM Pump 52A Shaft Rotation (6.34.4) - y e s X n o No Shaft Rotation V-3-68 Closed E4-3

merven I OYSTER CREE:.K tiENERATlNti lvullluel STATION PROCEDURE I -F An Lxeloii r u r n p a n y 607.4.004 Containment Spray and Emergency Service Water System 62 Pump Operability and Comprehensive / Preservice / Post-Maintenance lnservice Test ~ _- _

IST VALVE STROKE TIME

SUMMARY

_ _~ ~ _ _. . - - - _ ~ -~ - - - - - _ _ _ _ ..

I l STEP VALVE DIRECTION ACTUA I- ACCEPT RANGE LIMIT1NG TIME (sec)- -- ( s e a -~ VALUE (sec) ('I I 6.4.4.1

~~

V-21-17 CLOSE 30.1 MIN. 26.4 seconds 38.7 seconds

~~ _~ -

MAX: 35.6 seconds

~ ~~ -

6.4.5.1 V-21-18 OPEN 37.8 MIN: 33.1 seconds 48.6 seconds MAX: 44.7 seconds I

~

6.4.6.1 V-21-18 CLOSE 40.0 MIN: 32.2 seconds 47.3 seconds

- - _ ~_ ~~

MAX: 43.5 ~ -

seconds

~ 6.4.9.1 v-21-11 OPEN 65.2 MIN: 57.6 seconds 84.7 seconds MAX: 77.9 seconds _

I 6.5.1 v-21-11 CLOSE 69.7 MIN: 57.0 seconds 83.7 seconds

-~

MAX: 77.0 seconds 1 6.5.1 V-21-17 OPEN 37.4 MIN: 26.9 seconds 39.5 seconds MAX. 36.3 seconds

~ ~~ -~

(') Values are maximum, unless otherwise specified.

Comments:

Persons Performing Test:

Date

Appendix C Job Performance Measure Form ES-C-1 7 , I WORKSHEET Facility: Oyster Creek . Tiask NO.: - ___ -.

Job Performance Measure No.: NRC JPM ADMIN . SR04 (SRO) -

WA

Reference:

Generic

-~ _2.3.41SRO

~ _ __ __ - -.3.1)-

Examiner: __

Facility Evaluator: _.__ ___-

Method of Testing:

Simulated Performance Alctual Performance __ .

X..

Classroom _ _ X Simulator - ~ -

Plant _~~~ - -.

Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. The plant was at rated power when a severe earthquake occurred.

2. Chemistry has confirmed fuel failures.

3. Many plant systems have either failed to automatically isolate or are currently leaking from breaks or incomplete system isolations.

4. An emergency has been declared by the Shift Manager but no emergency operating facilities have been activatled.

5. The RP Manager has forwarded 3 Authorization for Emergency Exposure forms to you for your approval. Personal information on the volunteers to perform the 3 different jobs is also provided.

Task Standard: Determines that only the Authorization for Emergency Exposure form for Chris Cat should be authorized, and that the others should not be authorized.

Required Materials: Completed Authorizaticln for Emergency Exposure Forms.

NRC JPM ADMIN SR04 Page 1 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET General

References:

1. EP-AA-113, Personnel Protective Actions, revision 8

2. EP-AA-113-F-02,Authorization For EImergency Exposure, revision 6 Initiating Cue: Review for authorization the 3 Authorization For Emergency Exposure forms provided to you from the RP Manager. If not approved, state why.

Time Critical Task: No.

Validation Time: 9 minutes NRC JPM ADMIN SR04 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance lriformation Denote criticaI steps with a check mark J Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. Provide the Candidates the completed Authorization for Emergency Exposure forms.

Comment:

_._ _ _ _ ~ _ _ _ ~ -

~- ~~ ~ ~ - ~~_ ~ ~ ~~ ~~ -

SAT/UNSAT Note: The determinations may be made in any order.

J Performance Step: 2 Procedure Step: 3.2, 3.3 Determines that authorization should not be provided to Alan Able (JOB A) since it will only result in a dose of 4 Rem (1/2 hour x 8 Rem/hr).

Standard:

Comment:

SATNNSAT NRC JPM ADMIN SR04 Page 3 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 3

- ~

Procedure Step: 4.3.3 Determines that authorization should not be provided to Bob Blake (JOB B) since he already has had an emergency exposure of >25 Rem before.

Standard: Determines that authorization should not be provided to Bob Blake (JOB 8) since he already has had an emergency exposure of >25 Rem before.

Comment:

J Performance Step: 4 Procedure Step: Determines that authorization should be authorized for Chris Cat. He has had no prior emergency exposure > 25 Rem, and his expected exposure is > 5 Rem (416 x 20 = 13.3 Rem)

Standard: Determines that authorization should be authorized for Chris Cat.

He has had no prior emergency exposure > 25 Rem, and his expected exposure is > 5 Rein (4/6x 20 = 13.3 Rem)

SAT/UNSAT JPM Stop Time:

NRC JPM ADMIN SR04 Page 4 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: -NRC_ _JPM

- _ _ _ ADMIN

~ _ - _ - SR04

~-

Examinee's Name: ~ -___ _-._______

Examiner's Name:

Date Performed: _ _ ~

Facility Evaluator: ~ ~- _ ~-

Number of Attempts: ~ -

Time to Complete: ~ -- - -~ - -

Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's Signature and Date:

NRC JPM ADMIN SR04 Page 5 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup

1. None.

NRC JPM ADMIN SR04 Page 6 of 8

. *' . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

1. The plant was at rated power when a severe earthquake occurred.

2. Chemistry has confirmed fuel failure:;.

3. Many plant systems have either failed to automatically isolate or are currently leaking from breaks or incomplete system isolations.

4. An emergency has been declared by the Shift Manager but no emergency operating facilities have been activated.

5. The RP Manager has forwarded 3 Authorization for Emergency Exposure forms to you for your approval. Personal information on the volunteers to perform the 3 different jobs is also provided.

Task Cue:

Authorize or NOT authorize the 3 Authorization For Emergency Exposure forms provided to you from the RP Manager. If not approved, state why.

NRC JPM ADMIN SR04 Page 7 of 8

. j . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Personal information on the volunteers to perform the 3 different jobs.

I

~ PURPOSE: To enter the Trunion Room to manually close the MSlVs to secure the steam leak into the Turbine Building.

A DOSE RATE: 8 R/hour.

I ~ _ _ -~

Volunteer:

JOB DURATION: 30 minutes Alan Able Age:

44

~ -_- ~- - -

Prior Lifetime

- - ~ -

No Employee 001 11 Emergency Exposure?

1 ID:

I Dose:

1775 mrem PURPOSE: To rescue an unconscious worker in the Drywell.

JOB B DOSE RATE: 32 R/hour.

JOB DURATION: 50 minutes Volunteer: Bob Blake Age: 47 Prior Lifetime Yes Employee 00222 Emergency Exposure? 27 Rem ID:

Current 1050 mrem Dose:

PURPOSE: To close the RWCIJ isolation valve to stop flooding in the Reactor Building.

JOB C DOSE RATE: 20 R/hour.

JOB DURATION: 40 minutes

- _~ __

Volunteer: Chris Cat Age: 40 Prior Lifetime No Employee 00333 Emergency Exposure?

ID:

Current 1350 mrem Dose:

NRC JPM ADMIN SR04 Page 8 of 8

EP-AA-113-F-02 Exeian Revision B Page 1 of 1 Nuclcar AUTHORIZATION FOR EMERGENCY EXPOSURE Name: Alan Able

~_.___.__ -~ ___- - - ~ __ Datle / Time: -Today

_______ __ _Now

__ -~

Employee ID Number: _001

_ ~11

_ _ ~ _ Current Annual Exposure: 1775 - mrem

Reason for Request

JOB

- A: To enter the Trunion Room to manually close the

-~ MSlVs to secure the steam leak

-- - - ~ -

~- ~- ___. - ___

REQUESTING AUTHORIZATION TO EXCEED:

5 REM TEDE (Authorized t o receive greater than 5 Rem TEDE but less than 10 Rem TEDE) a 10 REM TEDE (Authorized t o receive greater than 10 Rem TEDE but less than 25 Rem TEDE) a 25 REM TEDE (Authorized to receive greater than 25 Rem)

. loday/xow

. ~-.-

Emergency Worker Signature Date /Time

Emergency Worker Exposure Limits and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.

John Redia

- _--_ -- -- ~ ~ ~- -__ lodaJ/gow Rad. Protection Management (Review) Date / Time

~

Station Emergency Director (Authorization) Date / Time Authorize? Y e s / No If NO, why not: __

EP-AA-113-F-02 Exelan, Revision 6 Page 1 of 1 Nuciear AUTHORIZATION FOR EMERGENCY EXPOSURE Name: Bob Blake~- ~ ___ Date / Time: -

Today

____ -~ - ..Now Employee ID Number: ~~00222-Current Annual Exposure: 1050 -- mrem

Reason for Request

- JOB_-

- B: To

__ rescue an unconscious worker in

-the Drywell.-

REQUESTING AUTHORIZATION TO EXCEED:

5 REM TEDE (Authorized t o receive greater than 5 Rem TEDE but less than 10 Rem TEDE) 10 REM TEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE) 25 REM TEDE (Authorized to receive greater than 25 Rem)

Emergency Worker Signature Date / Time

Emergency Worker Exposure Limits and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.

jofin K e d a

~ - -___ Iod2/Now Rad. Protection Management (Review) Date / Time Station Emergency Director (Authorization) Date / Time Authorize? Yes / No If NO, why not: - ~______~ __

~ . -___ ~-

Your Name: .-

- '* . EP-AA-113-F-02 Exelan I Revision 6 Page 1 of 1 Nudear AUTHORIZATION FOR EMErRGENCY EXPOSURE Name: Chris Cat

. _~

- Date II Time: Today

_ _ _.~ - - Now Employee ID Number: 00333

__ _ ~ _ _ _ Curirent Annual Exposure: 1350--__ mrem

Reason for Request

JOB C: To close the RWCU isolation valve

~ to stolp

______._ i n the Reactor___Building.

f l o o d D____

REQUESTING AUTHORIZATION TO EXCEED:

a 5REMTEDE (Authorized to receive greater than 5 Rem TEDE but less than 10 Rem TEDE) a 10REMTEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE) a 25REMTEDE (Authorized to receive greater than 25 Rem)

Emergency Worker Signature Date / Time

Emergency Worker Exposure Limits and Associ'ated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are! understood.

John

~ _

Reds

_ .- ~

_____.___ _ _ .~ - T*/%OW Rad. Protection Management (Review) Date / Time

- -~

Station Emergency Director (Authorization) Date /Time Authorize? Yes / No If NO, why not: __ _ - ~- ~ ~

I T AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Determine Emergency C1,assificationand Protective Action Task

Title:

Recommendations___. _~___ ___~_ ~ __________

Job Performance Measure No.: NRC JPlVl ADMIN SR05 (SR0)-

WA

Reference:

Generic 2.4.29 (SRO

~ -- 4.0)

Method of Testing:

Simulated Performance - - Actual Performance X ~-

Classroom X ~ Simulator - Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

The plant was at rated power when an autornatic scram occurred 45 minutes ago. The following conditions currently exist:

0 All but 8 control rods indicate full-in e APRMs indicate downscale e Reactor Engineering has determined that the reactor will remain shutdown under all conditions without boron e RPV water level is -60 with Core Spray injecting 0 Drywell pressure is 28 psig e Drywell temperature is 270 O F e Main Stack RAGEMS indicates 4.1 pCi/cc HRN e Drywell hydrogen indicates 3.1o/o e CHRRMS #1 indicates 1320 R/hr 0 CHRRMS #2 is downscale due to a loss of power e Dose assessment shows the highest dose at or beyond the site boundary is 115mRem NRC JPM ADMlN SR05 Page 1 of 8

\ AppendixC Job Performance Measure Form ES-C-1 WORKSHIEET Task Standard: The emergency has been classified and the PARS have been determined.

Required Materials: None.

General

References:

1. EP-AA-1010, Radiological Emergency Plan Annez for Oyster Creek Station, revision 0.

2. EP-AA-111, Emergency Classification and Protective Action Recommendations, revision 13.

3. EP-AA-111-F-10, Oyster Creek Plant Based PAR Flowchart, revision A.

Initiating Cue: Classify the emergency event (include the EAL designation). State the reason for this classification.

Time Critical Task: Yes.

Validation Time: 12 minutes Part 1 10 minutes Part 2 NRC JPM ADMIN SR05 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET

-~

Performance Information Denote critical steps with a check mark J Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. Handout first page of STUDENT HANDOUT.

Comment:

J Performance Step: 2 d d

~ _ . ~.

Procedure Step: Clas ifies t ,le emergency as a General Emergency (FG1).

Standard: Classifies the emergency as a General Emergency (FG1). This classification is made within I 5 minutes from the JPM Start Time.

Reasons: Loss of Fuel Clad barrier (RPV water level < -20); Loss of Reactor Coolant barrier (qPV water level < 0 ) ; and Potential Loss of Primary Containment barrier (CHRRMS =r 1210 R/hr less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after shutdown)

Note: Record time that the first page of the STUDENT HANOUT is received from each Candidafle.

Comment:

NRC JPM ADMIN SR05 Page 3 of 8

- a - - --

. . Appendix C Job Performanice Measure Form ES-C-1 WORKSHEET STUDENT HANDOUT Initial Conditions:

The plant was at rated power when an (automatic scram occurred 45 minutes ago. The following conditions currently exist:

e All but 8 control rods indicate full-in e APRMs indicate downscale e Reactor Engineering has determined that the reactor will remain shutdown under all conditions without boron e RPV water level is -60" with Corle Spray injecting e Drywell pressure is 28 psig e Drywell temperature is 270 "F e Main Stack RAGEMS indicates 4.1 vCi/cc HRN e Drywell hydrogen indicates 3.1o/o e CHRRMS #1 indicates 1320 R/hr e CHRRMS #2 is downscale due to a loss of power e Dose assessment shows the highest dose at or beyond the site boundary is 1 15 mRem Additional Initial Conditions:

Environmental conditions show that the wind is from 50" at 20 mph There are no travel impediments There are no Sea Breezes Task Cue: THIS IS A TIME CRITICAL JPM Determine the Protective Action Recomrnendations (PARS).

Protective Action Recommendations:

Name: -__.__ Time:

(NRC Only)

NRC JPM ADMIN SR05 Page 8 of 8

I , AppendixC Job Performanlce Measure Form ES-C-1 WORKSHEET Facility: Ojster

.~ ___ __Creek

-_ .. Task NO.: . 2000301401

- ~~ - __ - -

Task

Title:

Comglete the Technical Specifications Log Sheet

-_____________ . ~ _ _ _ _ _ _ _ _ _

Job Performance Measure No.: NRC JPM ADMIN R01 (RO)~-

K/A

Reference:

Generic 2.1 .I 8 (RO ____2.9J Examinee: ~~ .~. Examiner: ~ - . .

Method of Testing:

Simulated Performance - - Actual Performance - ~ __X _- . ~

Classroom -. . . Simulator ~ X ~ Plant ~ _ _

Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

1. The plant is rated power.

2. You are the on-shift Reactor Operator on the 4-12 shift.

3. The current datehime is April 20, 2008 at 1700.

Task Standard: Page E l - 1 of the Technicad Specifications Log Sheet is correctly completed and the discrepancies are noted. No remarks are made of in-specification readings.

Required Materials: A completed page E l - 1 (for the 11-7 and 7-3 shifts) of Procedure 681.4.004, Technical Specification Log Sheet.

General

References:

1. Procedure 681.4.004, Technical Specifications Log Sheet, revision 12.

NRC JPM ADMIN R01 Page 1 of 11

. AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Initiating Cue: Complete page E l -1 only of the Technical Specification Log Sheet, Procedure 681.4.004, Technical Specification Log Sheet. Notify the Unit Supervisor when complete and of any discrepancies or actions that may be required.

Time Critical Task: No.

Validation Time: 10 Minutes.

NRC JPM ADMIN R 0 1 Page 2 of 11

. AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Denote critical steps with a check mark 4 Note 1: The values may be recorded in any order.

Note 2: The discrepancies noted while cornpleting the log may be reported at the time of discovery or some other time during the JPM.

Note 3: Hand the Candidate the partially completed procedure.

Performance Step: 1

_ ~-

Procedure Step: Provides repeat back of initiating cue.

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

JPM Start Time:

Comment:

SAT/UNSAT

~_ ~~ ~~

Performance Step: 2 Procedure Step: Records position of AOG valve V-7-31.

Standard: Records position of valve AOG V-7-31 as closed on Panel 1OXF SAT/UNSAT NRC JPM ADMIN R 0 1 Page 3 of 11

. AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 3 Procedure Step: Records Torus water level from the following instruments:

LT-37 LT-38 Narrow Range on Panel 9XR Standard: Records Torus water level irom the following instruments as on the KEY:

LT-37 (Indicator on Panel 1F/2F)

LT-38 (Indicator on Panel 1F/2F)

Narrow Range Recorder on Panel 9XR Comment:

SAT/U NSAT Performance Step: 4 Procedure Step: Records Torus water temperature from the following indicators:

DIV I DIV II Standard: Records Torus water temp'erature from the following indicators as on the KEY: (Indicator on F'anel 1F/2F)

DIV I DIV II SAT/UNSAT NRC JPM ADMlN R 0 1 Page 4 of 11

- AppendixC Job Performance Measure Form ES-C-1 WORKSI-IEET Performance Step: 5 Procedure Step: Records Isolation Condenser area temperatures from the following instruments:

0 IB06A 0 IB06B IB06C IB06D Standard: Records Isolation Condenser area temperatures from the following instruments as on the KEY: (Panel 10R)

IB06A 0 IB06B IBO6C 0 IB06D Comment: . .. ~- . .-

..- .. ~~- ....

SAT/UNSAT Performance Step: 6 Procedure Step: Records Isolation Condenser levels from the following instruments:

IG06A IG06B Standard: Records Isolation Condenser levels from the following instruments as on the KEY: (Indicator on Panel 1F/2F)

IG06A IG06B Comment: .. . - ~ - .. . ~ ~.

SAT/U NSAT NRC JPM ADMlN R 0 1 Page 5 of 11

. AppendixC Job Performance Measure Form ES-C-1 WORKS+iEET

-~

J Performance Step: 7

~ ~

Procedure Step: Record Nii.rogen Makeup and calculate nitrogen use for the shift and for the day.

Standard: Records Nitrogen Makeup i3nd calculates nitrogen use for the shift, as on the KEY.

Calculates and records nitrogen use for the day by subtracting the previous day 3-1 1 integrator reading from the current 3-11 integrator reading, as on the KEY.

Recognizes/reports that the daily nitrogen use is > 250 units.

Comment:

Performance Step: 8 Procedure Step: Record RIB 119 radiation levels from:

Radiation monitor B-9 Radiation monitor C-9 Standard: Records RB 119 radiation levels from:

Radiation monitor B-9 Radiation monitor C-9 as on the key.

Comment:

SATNNSAT NRC JPM ADMIN R 0 1 Page 6 of 11

. AppendixC Job Performance Measure Form ES-C-1 WORKSI-iEET Performance Step: 9 Procedure Step: Record RE! Vent Radiation Monitor levels:

Radiation monitor Channel 1 Radiation monitor Channel 2 Standard: Procedure Step: Records RB Vent Radiation Monitor levels:

Radiation monitor Channel 1 Radiation monitor Channel 2, as on the KEY.

SAT/UNSAT Performance Step: 10 Procedure Step: Record the Shutdown Cooling Room lowest temperature.

Standard: Records the Shutdown Cooling Room lowest temperature, as on the KEY. (Panel 10R)

NRC JPM ADMIN R 0 1 Page 7 of 11

. AppendixC Job Performarice Measure Form ES-C-1 WORKS HEET

- ~-

Performance Step: 11 Procedure Step: Calculate IFuel Pool Slab AT Standard: Calculates Fuel Pool Slab AT by subtracting the Shutdown Cooling Room temperature from the Fuel Pool temperature, as on the key.

J Performance Step: 12 Procedure Step: Record the previous day lowest Torus water level, todays highest Torus water level, and the differential.

Standard: Records the previous day lowest Torus water level, todays highest Torus water level, and the differential, as on the KEY.

Reports the differential level is greater than allowed (actual is 5 0.2 allowed).

Cue: The previous days lowest Torus water level from Panel 9XR is 150.0.

Comment:

JPM Stop Time:

NRC JPM ADMIN R 0 1 Page 8 of 11

. AppendixC Job Performance Measure Form ES-C-1 WORKS t i EET Validation of Completion JPM Number: NRC

- __ JPM - _ _ _ADMIN

- - _ F301 Examinees ~ ~ ~ _ e Examiners Name: - _ - - _ __

Date Performed: - __

Facility Evaluator: _ _ - ____ _. - - -

Number of Attempts: - _-_--

Time to Complete:

Question:

Result: Satisfactory/U nsat isfactory Examiners Signature and Date:

NRC JPM ADMIN R 0 1 Page 9 of 11

.. . Appendix C Job Performanlce Measure Form ES-C-1 WORKSHEET Simulator.Setur,

1. Reset to full power IC-65

2. Insert the following:

a. SWI-RMS050A to 1.1 (RB 119 B9 rad)

b. SWI-RMS063A to 1.1 (RN 119 rad C9)

e. SWI-RMS066A to 1.O (RB vent rad mon)

d. SWI-RMS067A to 1.O (RB veirlt rad mon)

3. Have ready a 681.4.004 Attachment 1, completed for the 11-7 and 7-3 shifts (see Completed 681.4.004)

NRC JPM ADMIN R 0 1 Page 10 of 11

I AppendixC Job Performarce Measure Form ES-C-1 WORKS 1-1EET STUDENT H.ANDOUT Initial Conditions:

1. The plant is rated power.

2. You are the on-shift Reactor Operator on the 4-12 shift

3. The current date/tirne is April 20, 2008 at 1700.

Task Cue:

Complete page E l - 1 only of the Technical Specification Log Sheet, Procedure 681.4.004, Technical Speciftication Log Sheet. Notify the Unit Supervisor when complete and of any discrepancies or actions that may be required.

NRC JPM ADMIN R 0 1 Page 11 of 11

AmerGen,.

An Exelon Company 1 OYSTER CREEK GENERATING STATION PROCEDURE I Number 681.4.004 Title Technical Specification Log Sheet I Revision No.

12 TECHNICAL SPECIIzICATIONLOG SHEET DATE Todav SUB AOG TORUS STATION V-7-31 LEVEL (9XR) Normal TEMP TouP**

SHIFT Closed LT-37 LT-38 NARROW 1144 Divl DivI- Limit 11-7 Closed 152 152 150.2 -

< I53" 82 82 -<95"F (1)

For Limit 7-3 Closed 152 152 150.3 See 82 82 m* m Attachment 3-11 Closed 152 152 150.4 312.9-7 82 82 iolation Condenser Area Tei QS (10R Units Limit Differ.

Units 11-7 I I 7-3 [ 75 [ 74 0816489 t-+j-r 3-11

- I I Temp ~65°F 270

- Action 6 Daily: (3-11) (prev. 3-1I)

VIOLATED I

R.B. El. 1l ! Y RB Vent Rad (Meters) SD Hx RIM Fuel Pool Previous current Differential SHIFT 6-9 C-9 CHI CH2 Temp Lalw Slab AT Day's Day's Level in the Limit < 50"++ Lowest Highest Torus 11-7 1.0 1.0 var50 1.0 1.0 Var9 69 27 Torus Torus mRlHr mRlHr Level Level 7-3 1.0 1.0 Max 100 1.0 1.0 69 27 9XR 9XR Limit 1.2" MWHr 3-11 1.0 1.0 InRlHr 1.0 1.0 69 27 150.0 150.4 0.4 VIOLATED Elev. 119' EDG Comments:

Fuel Pool Fuel Oil Tank SHIFT Temp Lvl. 1 NOTE: Red readings indicate values to place on the LOQ- Sheet provided to the 1 1 Candidate in IC-65.

Limit Limit 7-3 96 5125" 14950 -

> 4KI Makeup z 250 units Gal.

F Calculated in accordance with Procedure 312.9 which also contains notification requirements.

)

Calculated in accordance with Procedure 312.11

rr Conducted in accordance with 681.4.005. NA when generator is off line.

mr Maximum 3°F difference between various Torus temperature indications.

+

ID.-AA..- -49 a\ 16 niiicnr ....-..ir\ _--

If both DWEDT pumps are inoperable, use 3.0 gpm for identified leakage and subtract from the 1-8 value

,.......,hill . +.-. -.....in\

? > Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek "ask No.: 2000101404 Task

Title:

Perform a Manual Core tieat- Balance Calculation Job Performance Measure No.: _NRC JP'M-ADMLN-RO2 (RQ WA

Reference:

-Generic 2.1.201_RO -~ -4.3)

Facility Evaluator: C:) ate : _____- ___-

Method of Testing:

Simulated Performance - -~ Actual Performance -~

X Classroom X

- - Simulator . - - - Plant - .

Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the taslk successfully, the objective for this job performance measure will be satisfied.

1. The reactor has been steady at full power for several hours.

2. The PPC is currently unavailable.

3. All prerequisites to perform this procedure have been met.

4. Calculating RWCU system differential temperature is not required.

5. The following indications are provided:

a. APRMs indicate 100% power

b. RPV water level instrument NR GEMAC indicates 161"

c. Local total Feedwater AP from the venturi transmitter (FT-422-1) indicates 492.5 inches of water

d. Core AP indicates 16.5 psid

e. Reactor pressure (NR recorder Panel 5F/6F) indicates 1020 psig

f. Feedwater temperature (recorder Panel 5F/5F) indicates 31 1 "F

g. Total steam flow (recorder Panel 5F/6F) indicates 7.1 Mlb/hr

h. Total recirculation flow (recorder Panel 3F) indicates 15 x 1O4 gpm

i. RWCU flow (recorder Panel 3F) indicates 400 gpm

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

NRC JPM ADMIN R 0 2 Page 1 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Standard: A manual core heat balancle has been completed IAW Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range.

Required Materials: Calculator.

General

References:

1. Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation -

Power Range, revision 27.

Initiating Cue: Calculate core thermal power (CTP) IAW Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range.

Time Critical Task: No.

Validation Time: 19 minutes NRC JPM ADMIN R 0 2 Page 2 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET

~ - _

-~ ~

Performance It i f o rmation Denote critical steps with a check mark 4 Performance Step: 1 Procedure Step: Provides repeal back of initiating cue JPM Start Time: -

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

____~

SAT/UNSAT Performance Step: 2 Procedure Step: Reviews Precautions and Limitations.

Standard: Reviews Precautions and Limitations.

Note: The expected values are provided in the KEY.

NRC JPM ADMIN R 0 2 Page 3 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSt-ilEET Performance Information J Performance Step: 3

- - ~

Procedure Step: 5.1.1.1 Records local total Feedwater AP in inches of water from the venture transmitter (FT-422-1) in the Feedwater Pump Room.

Standard: Directs EO to read local total Feedwater AP in inches of water from the venture transmitter (FT-422-1) in the Feedwater Pump Room, and records on the Feedwater Flow Calculation Worksheet, Line A.

Cue: As the EO, report reading on the venture transmitter (FT-422-1) in the Feedwater Pump Room as 492.5 inches.

Comment:

J Performance Step: 4 Procedure Step: 5.1.1.2 Record Feedwater temperature (ID 101) from Panel 5F/6F recorder to the nearest whole degree.

Standard: Reads Feedwater temperature (ID 101) from Panel 5F/6F recorder to the nearest whole degree and records on the Feedwater Flow Calculation Worksheet, Line B.

Comment:

NRC JPM ADMlN R 0 2 Page 4 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance lrilformation J Performance Step: 5 Procedure Step: 5.1.1.3 Obtain the specific volume (v) at the Feedwater at 1100 psia and the temperature recorded in Step 5.1.1.2 from Attachment 1001 3 or ASME approved steam tables.

Standard: Obtain the specific volume (v) at the Feedwater at 1100 psia and the temperature recorded in Step 5.1.1.2 from Attachment 1001.6-3 or ASME approved steam tables, and records on the Feedwater Flow Calculation Worksheet, Line C.

Comment:

~ ~ ~ _ ~- - . -- ___ __ _ _ ~ _

J Performance Step: 6 Procedure Step: 5.1.1.4 Calculates total Feedwater flow using the following equation:

F = 0.0429387 SQRT (AP/v)I Standard: Calculates total Feedwater flow using the following equation:

F = 0.0429387 SQRT (AP/v) and records on the Feedwater Flow Calculation Worksheet, Line D.

Comment:

_ ~-

SATNNSAT NRC JPM ADMIN R 0 2 Page 5 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 7 Procedure Step: 5.2.1 Record reactor pressure to the nearest whole pound (Narrow range recorder - Panel 5F/6F)

Standard: Reads reactor pressure to the nearest whole pound (Narrow range recorder - Panel 5F/6F) and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line A.

Comment:

- - - ~ ~~- ~ - ~- -- ~ -~ - __- - -

SAT/U NSAT J Performance Step: 8 Procedure Step: 5.2.2 Record Feedwater temperature to the nearest whole degree (Recorder Panel 5F/6F)

Standard: Reads Feedwater temperature to the nearest whole degree (Recorder Panel 5F/6F) or transfers the Feedwater temperature obtained earlier, and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line B.

Comment:

SATNNSAT NRC JPM ADMIN R 0 2 Page 6 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 9 Procedure Step: 5.2.3 Record recirculation flow to the nearest thousand gpm (Recorder Panel 3F).

Standard: Reads recirculation flow to the nearest thousand gpm (Recorder Panel 3F), and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line C.

Comment:

J Performance Step: 10 Procedure Step: 5.2.4 Calculate the reactor absolute pressure by adding the value of step 5.2.1 + 14.7 pounds prt,assure.

%mdard: Calculate the reactor absolute pressure by adding the value of step 5.2.1 + 14.7 pounds pressure, and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line D.

Comment:

_-__ ~~ _ _ _ ~ ~ - ~

SAT/U NSAT NRC JPM ADMIN R 0 2 Page 7 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSt-IEET Performance Information J Performance Step: 11 Procedure Step: 5.2.5 Record Main Steam enthalpy from Attachment 1001.6-5 or an ASME approved steam table, at saturated conditions using calculated absolute pressure.

Standard: Reads Main Steam enthalpy from Attachment 1001.6-5 or an ASME approved steam table, at saturated conditions using calculated absolute pressure in step 5.2.4 and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line E Comment:

~, -_ -

SATAJNSAT J Performance Step: 12

~ ~~ -

Procedure Step: 5.2.6 Record the Feedwater enthalpy from Attachment 1001.6-6 or ASME approved steam table for compressed water at 1100 psia using Feedwater temperature.

Standard: Reads the Feedwater enthalpy from Attachment 1001.6-6 or ASME approved steam table for compressed water at 1100 psia using Feedwater temperature in step 5.2.2, and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line F.

Comment:

_ _ ~ ~

SATNNSAT NRC JPM ADMlN R 0 2 Page 8 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information

~~ ~

J Performance Step: 13

._~

Procedure Step: 5.2.7 Calculate the difference of the Main Steam and Feedwater enthalpies.

Standard: Calculates t h e difference of Ihe Main Steam and Feedwater enthalpies by subtracting Feedwater enthalpy in step 5.2.6 from Main Steam enthalpy in step 5.2.5, and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line G.

Comment:

- - - - ~ __ --

J Performance Step: 14 Procedure Step: 5.2.8 Record total Feedwater flow FLO (tot) for differential pressure 3 loop and/or local venture (single element) methods from the Feedwater Flow Calculation Worksheet.

Standard: Copies total Feedwater flow FLO (tot) for differential pressure 3 loop and/or local venture (single element) methods from the Feedwater Flow Calculation Worksheet, Line D, onto the Heat Balance Data, Calculation, and Analysis Worksheet, Line H.

Comment:

- __ ~-

NRC JPM ADMIN R 0 2 Page 9 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 15 Procedure Step: 5.2.9 Calculate the product of the Feedwater flow and the enthalpy difference to obtain MBTU/hr.

Standard: Calculates the product of the Feedwater'flow in step 5.2.8 and the enthalpy difference in step 5.2.7 to obtain MBTU/hr, and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line I.

Comment:

~ ~ ~~

J Performance Step: 16 Procedure Step: 5.2.10 Convert MBTU/hr to Megawatts (MBTU/hr x 0.293).

Standard: Converts MBTU/hr to Megawatts by multiplying MBTU/hr in step 5.2.9 by 0.293, records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line J.

Comment:

NRC JPM ADMIN R 0 2 Page 10 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET

-~ ~

Pe rfor ma nce I1 format io n J Performance Step: 17 Procedure Step: 5.2.1 1 Record RWCU flow to the nlearest gpm (recorder Panel 3F) on Line K of Attachment 1001.6-2.

Standard: Reads RWCU flow to the nearest gpm (recorder Panel 3F) and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line K.

Comment:

SAT/UNSAT

- ~ ~ - ~- ~

J Performance Step: 18 Procedure Step: 5.2.12 Calculate the CRD, recirc. pump power, RWCU and ambient losses adjustment (Fixed Losses), per the following equation.

Enter the appropriate value for Fixed Losses on Line L of Attachment 1001.6-2.

Fixed Losses = [(K) x 0.01361 + 9.0 Standard: Calculates the CRD, recirc. pump power, RWCU and ambient losses adjustment (Fixed Losses), per the following equation, and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line L.

Fixed Losses = [(Line K) x 0.01361 + 9.0 Comment:

~ __ . ~ -~ __ ~ _ - _ ~ __~ ~ __ __ ~~ -

NRC JPM ADMIN R 0 2 Page 11 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Pe rfo rmance Iri f o r mat ion J Performance Step: 19 Procedure Step: 5.2.13 Add the Fixed Losses from L.ine L to the Megawatts from Line J and record the Calculated C'TP on Line N.

Standard: Adds the Fixed Losses from step 5.2.12 to the Megawatts from step 5.2.10 and record the Calculated CTP on Line N on the Heat Balance Data, Calculation, and Analysis Worksheet.

Comment:

-~ - -

Performance Step: 20 Procedure Step: 5.2.14 Record PPC Core Thermal Power (CTP) in Line M.

Standard: This step is NA since the PPC is unavailable.

Comment:

NRC JPM ADMIN R 0 2 Page 12 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance lriiformation Performance Step: 21 Procedure Step: 5.2.1 5 Subtract the Calculated CTP from the PPC Core Thermal Power

[Line M - Line N]. If this value is positive, the comparison is considered conservative. If negative, the comparison is non-conservative. Place an X in the appropriate box.

Standard: This step is NA since the PPC is unavailable.

Comment:

~ - -~- - __ ~ -- - - -~ - ~ _ __ _ _ ~

_ - ~. -

JPM Stop Time:

NRC JPM ADMIN R 0 2 Page 13 of 16

Appendix C Job Performancle Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: NRC JPM ADMIN R 0 2 Examinees Name: ~- - - ~ ~-

Examiners Name: - - - - __ -~~ ~ -- -

Date Performed: __ ~ _ _ _ - -~ - ~ --

Facility Evaluator: ___ ~~ __ - - ~ -

Number of Attempts: - -- ~ - -

Time to Complete: -- - -_ -

Question:

-~ - ~

Response

Result: Satisfactory/Unsatisfactory Examiners Signature and Date: ... -~ ._- - ~ ---

NRC JPM ADMIN R 0 2 Page 14 of 16

'. . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulato r $et up

1. None.

NRC JPM ADMIN R 0 2 Page 15 of 16

Appendix C Job Performance Measure Form ES-C-1 WORKSHIEET STUDENT H[\NDOUT Initial Conditions:

1. The reactor has been steady at full power for several hours.

2. The PPC is currently unavailable.

3. All prerequisites to perform this procedure have been met.

4. Calculating RWCU system differential temperature is not required.

5. The following indications are provided:

a. APRMs indicate 100% power

b. RPV water level instrument NR GEMAC indicates 161

c. Local total Feedwater AP from .the venturi transmitter (FT-422-1) indicates 492.5 inches of water

d. Core AP indicates 16.5 psid

e. Reactor pressure (NR recorder Panel 5F/6F) indicates 1020 psig

f. Feedwater temperature (recorder Panel 5F/5F) indicates 31 1 F

g. Total steam flow (recorder Panel 5F/6F) indicates 7.1 Mlb/hr

h. Total recirculation flow (recorder Panel 3F) indicates 15 x 1O4 gpm

i. RWCU flow (recorder Panel 3F) indicates 400 gpm Task Cue:

Calculate core thermal power (CTP) IAW Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Flange.

NRC JPM ADMIN R 0 2 Page 16 of 16

ATTACHMENT 1001.6-1 FEEDWATER FLOW CALCULATION WORKSHEET Preparer: Date: Time:

Prerequisites met:

A 5.1.1.1 DP From Total Flow Venturi Transmitter (FT-422-1) Local Transmitter DP Reading 492.5 in H20 B 5.1.1.2 Feedwater Temperature (ID 101) Panel 5F/6F Recorder 31I deg F C 5.1.1.3 Specific Volume at 1100 psia and (B) Attachment 1001.6-3 or ASME Steam Tables 0.01748 ft3/lbm D 5.1.1.4 TOTAL FEEDWATER FLOW FT = 0.0429387 x SQRT[(A) / (C)] 7.207 Mlbm/hr iB&& 2: J" Loop F;ow-caicii;afion A Loop 5 Loop c Loop 1 D= A= B= E= C= F=

E 5.1.2.1 Feedwater Pump Room Nozzle DP Gauges (RV45) in H20 F 5.1.2.2 Average Nozzle DP in H20 Pos 15 = Pos 16 = Pos 17 =

G 5.1.2.3 Loop Temperature: Recorder 13R-005 deg F H 5.1.2.4 Loop Specific Volume at 1400 psia: ft3/lbm Attachment 1001.6-4 or ASME Steam Tables I 5.1.2.5 Nozzle Discharge Coefficient x Conversion Factor 0.02252 0.02291 0.02269 Loop Flow:

J 5.1.2.5 FA= Fg = Fc = Mlbmlhr

= (I) x SQRT[(F) / (H)]

K 5.1.2.6 TOTAL FEEDWATER FLOW FT = FA+ FB + Fc Mlbm/hr Comments:

ATTAC NT 1001.6-2 Revi 27 HEAT BALANCE DATA, CALCULATION, AND ANALYSIS WORKSHEET A 5.2.1 Reactor Pressure (ID-45) Panel 5Fl6F Narrow Range Recorder 1020 6 5.2.2 Feedwater Temperature (ID 101) Panel 5Fl6F Recorder 311 deg F C 5.2.3 Recirculation Flow Panel 3F Recorder 15 io4gpm D 5.2.4 Reactor Absolute Pressure (A) + 14.7 1034.7 psia E 5.2.5 Main Steam Enthalpy (hMs) Attachment 1001.6-5 or ASME Steam Tables 1191.61 BTU/Ibm F 5.2.6 Feedwater Enthalpy (hFW) Attachment 1001.6-6 or ASME Steam Tables 282.91 BTUIIbm G 5.2.7 Enthalpy Difference (bus - hFw) (E) - (F) 908.7 BTU/lbm H 5.2.8 Total Feedwater Flow Attachment 1001.6-1, (0) or (K) 7.207 Mlbrnlhr I 5.2.9 Feedwater Flow x Enthalpy Difference (H) x (GI 6549.00 MBTU/hr J 5.2.10 Conversion to M W T ~ 0.293X/I) 1918,853 I

K 1 5.2.11 I RWCU Flow Panel 3F Recorder 400 I I

~ ~~

L 5.2.12 Fixed Losses [(K) x 0.01361 + 9.0 14.44 M 1 5.2.14 I PPC Core Thermal Power (CTP) PPC CTP 15 Minute Average N 5.2.13 Calculated Core Thermal Power (J) + (L) 1933.297 I I I I 0 5.2.15 Core Thermal Power Comparison U Positive Value -+

Conservative Negative Value -+

Non-Conservative I Date: I Time:

1 , AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek- Task No.: 21501______.__

01023 Task

Title:

Perform

___ APRM

__ Drawer Clount Job Performance Measure No.: NRC JPlVl ADMIN

~ --- R 0- 3 (RO)

K/A

Reference:

Generic 2.2.12 (RO 3.0) -

~~- ~ -.

Examinee: ___ .__ -_ ~-E.xam ine r : ~

Facility Evaluator: Date: -____

Method of Testing:

Simulated Performance ~- Actual Performance ___- X Classroom - ___- Simulator _- X _._Plant

-~ ~ -

Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

1. The plant is at rated power.

Task Standard: Section 2 of Attachment 202.1 -1, APRM Status Check, for APRM 8 is complete and LPRM 44-25D does not iindicate bypassed.

Required Materials: A completed attachment 403-2, with no APRMs bypassed, and LPRMs 36-17B, 28-09D and 44-25D shown as bypassed.

General Refe rences:

1. Procedure 202.1, Power Operation, revision 109.

2. Procedure 403, LPRM-APRM System Operations, revision 13.

Initiating Cue: Perform Section 2 of Attachment 202.1-1, APRM Status Check, for APRM 8. Notify the Unit Supervisor of your results.

Time Critical Task: No.

Validation Time: 13 minutes NRC JPM ADMlN R 0 3 Page 1 of 11

. AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark J

~~~~

Performance Step: 1 Procedure Step: Provides repeat back of initiating cue.

JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. Provide the Candidate Section 2 of Attachment 202.1-1 and Attachment 403-2.

Comment:

SATNNSAT

~-

Performance Step: 2 Procedure Step: 1 of Attachment 202.1-1.

Place an X in the box next to the LPRMs that are Bypassed.

Standard: Places an X in the box next to LPRMs 36-176, 28-09D, and 44-25D in the APRM 8 colurrin.

NRC JPM ADMIN R 0 3 Page 2 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 3 Procedure Step: 2 of Attachment 202.1 -1.

Place the number of un-bypassed inputs in the last row.

Standard: Places the number of un-bypassed inputs (5) in the last row for APRM 8, marked UN-BYPASSED.

Comment:

Performance Step: 4 Procedure Step: 5.3.3.8.1 of Procedure 403.

Obtains permission from the US for LPRM input to APRM drawer count.

Standard: Obtains permission from the US for LPRM input to APRM drawer count.

CUE: The candidate may or may riot ask permission since he was directed to perform the task. If the candidate does ask, state that they have permission to perform the APRM drawer count.

Comment:

NRC JPM ADMIN R 0 3 Page 3 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 5 Procedure Step: 5.3.3.8.2 of Procedure 403.

Bypass the APRM channel if allowed by Attachment 403-2.

Standard: Verifies that Attachment 403-2 allows bypass of APRM 8. Places the APRM BYPASS joystick to the CH 8 position (critical step).

Verifies APRM 8 HI-HI, HIGH, and DN SCL OR INOP lights ON.

Comment:

SAT/UNSAT J Performance Step: 6 Procedure Step: 5.3.3.8.3 of Procedure 403.

Rotate drawer INPUT switch clockwise to COUNT.

Standard: Rotates APRM 8 drawer INPUT switch clockwise to COUNT.

Note/Cue: Based upon the initial draweir indication, the count indication should display 50 when placed in count, but will show 60 (ie, only 2 LPRMs are bypassed). The candidate may mention this result now and may stop the test. Acknowledge the report and direct the candidate to continue the test.

Comment:

SAT/U NSAT NRC JPM ADMlN R 0 3 Page 4 of 11

. AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 7 Procedure Step: 5.3.3.8.3.a of Procedure 403.

Continue to rotate input switch clockwise to read LPRM values input to the APRM drawer.

Standard: Continues to rotate APRM 8 drawer input switch clockwise to position 8, position 7, etc., up to position 1 to read LPRM values input to the APRM drawer.

Note/Cue: Positions 1 and 6 will indicate 0 due to being bypassed from the APRM. Position 7 should show 0, but will indicate a reading similar to the other LPRMs not bypassed. All other positions will show the LPRM reading input (not 0). The candidate may mention this result now and may stop the test. Acknowledge the report and direct the candidate to continue the test.

Comment:

SAT/U NSAT J Performance Step: 8

~~

Procedure Step: 5.3.3.8.3.b of Procedure 403.

Rotate input switch clockwise until AVERAGE is selected.

Standard: Rotates APRM 8 drawer input switch clockwise until AVERAGE is selected.

Comment:

NRC JPM ADMIN R 0 3 Page 5 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 9 Procedure Step: 5.3.3.8.3.c of Procedure 403.

Un-bypass the APRM channel if the APRM channel was bypassed.

Standard: Un-bypass APRM 8 by placing the ARPM BYPASS joystick to the mid-position (critical step). Verifies APRM 8 HI-HI, HIGH, and DN SCL OR INOP lights OFF.

Comment:

~~

Performance Step: 10

~ . - .~

Procedure Step: 5.3.3.8.4 of Procedure 403 Repeat 5.3.3.8(2) through 5.3.3.8(3c) for other APRMS as required.

Cue: No other APRMS testing is required.

Standard: Determines no other APRMs, will be tested..

Comment:

NRC JPM ADMlN R 0 3 Page 6 of 11

. ,* . AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Performance Step: 11 Procedure Step: 5.3.3.8.5 of Procedure 403.

Verify all drawers INPUT switches in AVERAGE.

Standard: Verifies all drawers INPUT switches in AVERAGE.

Comment:

SAT/UNSAT

~ -~ ~

J Performance Step: 12 Procedure Step: 4 of Attachiment 202.1-1.

Verify number of inputs correct.

Standard: Verifies number of inputs carrect. The candidate should state, if not done already, that the nlJmber of inputs (6) does not match the expected number of inputs (5).

Cue: Acknowledge the report.

Comment:

NRC JPM ADMIN R 0 3 Page 7 of 11

. I . AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 13

~~

Procedure Step: 5 of Attachment 202.1-1.

Verify bypassed LPRM inputs are correct.

Standard: Verifies bypassed LPRM inputs are correct. The candidate should state, if not done already, that LPRM 44-25D is does not show bypassed.

Cue: Acknowledge the report.

Comment:

JPM Stop Time:

NRC JPM ADMIN R 0 3 Page 8 of 11

1 . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation of Completion JPM Number: ~

NRC JPM ADMON R03 - _-

Examinees Name: - - _- _-- - ~ -

Examiners Name: ~ _ _

Date Performed: -

Facility Evaluator: - - -

Number of Attempts: _ - ~~ - ~- ___

Time to Complete: - .~

Question:

- - - - -- -- _ ~- _ - - - -

Result: Satisfactory/U nsatisfactory Examiners Signature and Date: _

NRC JPM ADMIN R 0 3 Page 9 of 11

, *, . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator 3etuD

1. Reset to full power IC-65.

2. Bypass LPRM 36-1 7B from APRM el (red knob and silver toggle).

3. BypassLPRM 28-09D from APRM I (red knob and silver toggle).

4. Insert the following:

a. SW I-NISI53T to ON; This will light the BYPASS white light for LPRM 44-25D on APRM 8 drawer (DONT NEED red)

b. SWI-NIS153CR to OFF; This will stick the bypass switch for LPRM 44-25D to the un-bypassed position. (Not required)

c. IND-NIS020B to ON; This will place LPRM 44-25D amber light to ON on Panel 4F.

5. Have a blank copy of just attachment 202.1 -1 Section 1 and 2 (pages E l -

1 and E l -2), with APRMs 1-7 N/Ad.

6. Have a copy of 403 Section 5.3, completed and NA as appropriate up to the COUNT section: section 5.3.3.6.

7. Have a completed attachment 403-2 with the LPRMs marked.

8. Close APRM drawers.

NRC JPM ADMIN R 0 3 Page 10 of 11

I 1. , Appendix C Job Performancle Measure Form ES-C-1 WORKSHEET STUDENT HqrNDOUT Initial Conditions:

1. The plant is at rated power.

Task Cue:

Perform Section 2 of Attachment 202.1-1, APRM Status Check, for APRM 8.

Notify the Unit Supervisor of your results.

NRC JPM ADMlN R 0 3 Page 11 of 11

t * . Appendix C Job Performance Measure Form ES-C-1 WORKSHIEET Facility: Oyster Creek- Task NO.: 2000501433 Task

Title:

Determine RPV Water Level Instrument

- - ~ Availability_-

Job Performance Measure No.: -NRC.JPM _ ADMIN

- - R 0 4- (ROl

~_ _

WA

Reference:

Generic

-~ 2.4.21 (RO -~3.7)

Examinee: - ._ _ - Examiner:

Facility Evaluator: - - . Date: .

Method of Testing:

Simu lated Perform ance _ - .~ Actual Performance X Class room X

- Simulator Plant Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. The Plant was at rated power when a LCCA occurred in the Primary Containment.

2. The Primary Containment Control EOP has been entered.

3. RPV pressure is 200 psig and stable.

4. The table below contains data recorded from Recorder TR-IA55 on Panel 8R, for the instrument reference leg vertical riun temperatures, along with the current water level indications:

--- - _ - _. ~ - - -

RPV Water Te rrg-Instrument Level Reading Instrument NO.

-~

Point 89 -

TE-103-450 340 91 TE-103-451 130 -~

TE-103-452

.____ ~~

42 360 I

84 TE-103-453 43 405

~ YARWAYB 83 TE-103-454 ~ 44 ~ 375 NRC JPM ADMIN R 0 4 Page 1 of 8

> ' . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Standard: IAW the reference provided:,the Candidate has determined that only NR GEMAC B is available for RPV water level indication.

Required Materials: None.

General

References:

1 . EMG-SP28, Level Instrumentation Availability, revision 0.

Initiating Cue: IAW EMG-SP28, Level Instrumentation Availability, and the information provided, state whether each R I V water level instrument is available for RPV water level indication or is not available.

Time Critical Task: No.

Validation Time: 7 minutes NRC JPM ADMIN R 0 4 Page 2 of 8

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Denote critical steps with a check mark 4 Performance Step: 1

- _ _ ~ ~_ ~

Procedure Step: Provides repeat back of initiating cue.

JPM Start Time:

Standard: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Comment:

___ --- _ _ _ _ - -~ _ ~ --~ __ _ __ - -

J Performance Step: 2 Procedure Step: 3.4 Verify that the instrument reference leg temperatures are in the SAFE REGION of the RPV Saturation Temperature Curve.

Standard: Compares the provided reference leg temperatures for all level instruments at the given RPV pressure against the RPV Saturation Temperature curve. Determines that YARWAY A is not in the SAFE REGION and thus is not available for RPV water level instrumentation.

Comment:

.- ~ __ - _ ~ -~ _ _ ~ - .

NRC JPM ADMlN R 0 4 Page 3 of 8

. . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 3 Procedure Step: 3.5 For each instrument below, the instrument reads in the Safe Region of its respective curve.

Standard: Compares the NR GEMAC Pi and NR GEMAC 6 indicated water levels at the given reference leg temperatures on the GEMAC NARROW RANGE curve. Determines that NR GEMAC A is not in the Safe Region and thus is not available for RPV water level instrumentation.

Determines that NR GEMAC. B is in the Safe Region and thus is available for RPV water level instrumentation.

Comment:

J Performance Step: 4 Procedure Step: 3.5 For each instrument below, the instrument reads in the Safe Region of its respective curve.

Standard: Compares the YARWAY 6 iirldicated water level at the given reference leg temperatures on the YARWAY curve. Determines that YARWAY 6 is not in the Safe Region and thus is not available for RPV water level instrumentation.

Comment:

NRC JPM ADMIN R 0 4 Page 4 of 8

D' . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information

~

J Performance Step: 5

~ ~~

Procedure Step: 3.5 For each instrument below, the instrument reads in the Safe Region of its respective curve.

Standard: Compares the WR GEMAC rndicated water level at the given reference leg temperatures on the GEMAC Wide Range curve.

Determines that WR GEMAC is not in the Safe Region and thus is not available for RPV water level instrumentation.

Comment:

JPM Stop Time:

NRC JPM ADMIN R 0 4 Page 5 of 8

Y -

Appendix C Job Performance Measure Form ES-C-1 WORKSHIEET Va Iidat io n of Co mplet ion JPM Number: NRC JPM ADMIN

_ - - R04 Examinees Name: __ _ _ ~ ~~~~

Examine rs Nam e : -~ - - ~ ~-

Date Performed: ~

Facility Evaluator. ~ _ ~-

Number of Attempts: ____ ~_ ~~ __ -

Time to Complete: _ _ ~_~ ___

Question:

Response

Result: Satisfactory/U nsatisfactory Examiners Signature and Date: ~~ .

NRC JPM ADMIN R 0 4 Page 6 of 8

V

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator ?;etuD

1. None.

2. Have a blank copy of Support Procedure 28, EMG-SP28, Level Inst r urn entat ion Availability ready.

NRC JPM ADMlN R 0 4 Page 7 of 8

Appendix C Job Performarice Measure Form ES-C-1 WORKSHEET STUDENT tjANDOUT Initial Conditions:

1. The Plant was at rated power when a LOCA occurred in the Primary Containment.

2. The Primary Containment Control EfOP has been entered.

3. RPV pressure is 200 psig and stable.

4. The table below contains data recorded from Recorder TR-IA55 on Panel 8R, for the instrument reference leg vertical run temperatures, along with the current water level indications:

Level Instrument 1

- 1 Level Readinq

_ Instrument No.

__ -~ Point

~~- -

1 1 ---

F 1 I -

~ _ _ ~-

NR GEMAC B NRCEMACA ii ~- -

89 91 TE-103-450-TE-103-451

- -~

40

~

41-I-

1 340 335 --I 1

1 1

I WRGEMAC YARWAYA YARWAYB-.

- -1 I I

130 84 83

- I 1 -

TE-103-452

-TE-103-453 TE- 103-454 42 43 44

~

I

~

360 405 375 -~

I1 Task Cue:

IAW EMG-SP28, Level Instrumentation Availability, and the information provided, state whether each RPV water level instrument is available for RPV water level indication or is not available.

Available? Yes/No NRC JPM ADMIN R 0 4 Page 8 of 8

ML081330603

Contents

Text

Title:

Reference:

References:

Response

Reference:

References:

Response

Title:

Reference:

References:

7.1.3 NOTEKUE

SUMMARY

SUMMARY

SUMMARY

Reference:

References:

Response

Reason for Request

Reason for Request

Reason for Request

Title:

Reference:

References:

Title:

Reference:

References:

Title:

Reference:

References:

Response

Title:

Reference:

Title:

Reference:

References:

Response

Navigation menu

ML081330603

Text

Title:

Reference:

References:

Response

Reference:

References:

Response

Title:

Reference:

References:

7.1.3 NOTEKUE

SUMMARY

SUMMARY

SUMMARY

Reference:

References:

Response

Reason for Request

Reason for Request

Reason for Request

Title:

Reference:

References:

Title:

Reference:

References:

Title:

Reference:

References:

Response

Title:

Reference:

Title:

Reference:

References:

Response

Navigation menu

Search