ML081330652

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Draft - Section a Operating Exam (Folder 2)
ML081330652
Person / Time
Site: Oyster Creek
Issue date: 02/29/2008
From: Ludlam G
AmerGen Energy Co
To: Caruso J
Operations Branch I
Hansell S
Shared Package
ML072851077 List:
References
50-219/08-301, U01688
Download: ML081330652 (97)
v • d • e


Text

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Reference:

Generic 2.1.18 (RO 2.9) Examinee: Examiner:

_- - Facility Evaluator: - .- I - Date: _- Method of Testing: X - - - - - I Simulated Performance Actual Performance Simulator x- Plant Classroom

_. - 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 El-1 of the Technical Specifications Log Sheet is correctly completed and the discrepancies are noted. Required Materials:

A completed page El -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.

initiating Cue: Complete page El -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.

NRC JPM ADMIN R01 Page 1 of 11 1' Appendix C x I*- -%-- Job Performance Measure Form ES-C-1 WORKSHEET - Time Critical Task: No. Validation Time: 10 Minutes. NRC JPM ADMlN R01 Page 2 of 11 Appendix C Job Performance Measure WORKSHEET Form ES-C-1 Denote critical steps with a check mark J Note 1 : The values may be recorded in any order. Note 2: The discrepancies noted while completing the log may be reported at the time of discovery or some other time during the JPM. Note 3: Hand the Candidate the partially clompleted procedure.

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

Evaluafor acknowledges the repeat back. __ -~ Standard:

JPM Start Time: Comment: Performance Step: 2 Procedure Step: Records position of AOG valve V-7-31. Records position of valve AOG V-7-31 as closed on Panel 1 OXF - Standard:

-. Comment: NRC JPM ADMIN R01 Page 3 of 11 Appendix C 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 Records Torus water level from the following instruments as on the KEY: 0 Standard:

LT-37 (Indicator on Panel 1 F/2F) LT-38 (Indicator on Panel 1 F/2F) Narrow Range Recorder on Panel 9XR - Performance Step: 4 Procedure Step: Records Torus water temperature from the following indicators:

DIV I DIV II Standard: Records Torus water temperature from the following indicators as on the KEY: (Indicator on Panel 1 F/2F) DIV I DIV II Comment: -- - SAT/U NSAT NRC JPM ADMIN R01 Page 4 of 11

..~.. .-. "I ,. . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Step: 5 Procedure Step: Records Isolation Condenser area temperatures from the following instruments: - - __ 1B06A 0 IB06B IB06C IB06D Standard:

Records Isolation Condenser area temperatures from the following instruments as or] the KEY: (Panel 10R) IB06A 0 IB06B IBO6C IB06D -~ - - SATlUNSAT Performance Step: 6 Procedure Step: Records Isolation Condenser levels from the following instruments:

IG06A 0 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 R01 Page 5 of 11

.L

  • Appendix C Job Performance Measure Form ES-C-1 WORKSFEET J Performance Step: 7 - ~ - - Procedure Step: Record Nitrogen Makeup and calculate nitrogen use for the shift and for the day. Standard: Records Nitrogen Makeup and 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 3-1 1 integrator reading, as on the KEY. Recognizes/reports that the daily nitrogen use is > 250 units. - Comment: Performance Step: 8 Procedure Step: Record RB 119' radiation levels from: __ 0 Radiation monitor 8-9 Radiation monitor C-9 0 Radiation monitor 6-9 Standard:

Records RB 119' radiation levels from: Radiation monitor C-9 as on the key. - ___ ~ - ~~ - - ~ - --- Comment: - - -_ .- SAT/UNSAT NRC JPM ADMlN R01 Page 6 of 11

.i. Appendix C Job Performance Measure WORKS t-I EET Form ES-C-1 Performance Step: 9 Procedure Step: Record RE!, Vent Radiation Monitor levels: ~~ ___ Radiation monitor Channel 1 Radiation monitor Channel 2 Standard:

Procedure Step: Records HB Vent Radiation Monitor levels: Radiation monitor Channel 2, as on the KEY. Radiation monitor Channel 1 0 Com ment:

Performance Step: 10 Procedure Step: Record the Shutdown Cooling Room lowest temperature. ~~ ~ __ Standard:

Records the Shutdown CcjoJing Room lowest temperature, as on the KEY. (Panel 10R) NRC JPM ADMIN R01 Page 7 of 11 I. Appendix C Job Performance Measure Form ES-C-1 WORKSHEET - __ Performance Step: 11 Procedure Step: Calculate Fuel Pool Slab AT Calculates Fuel Pool Slab AT by subtracting the Shutdown Cooling Room temperature from the Fuel Pool temperature, as on the key. Standard:

Comment: __ __ - ~- J Performance Step: 12 -- -- Procedure Step: Record the previous day lowest Torus water level, today's highest Torus water level, and the differential.

Records the previous day lowest Torus water level, today's highest Torus water level, and the differential, as on the KEY. Reports the differential level is greater than allowed (actual is > 250 Units allowed).

Standard:

Cue: Comment. The previous day's lowest Torus water level from Panel 9XR is 150.0 OF. - - Terminating Cue: Page El -1 of the Technical Specifications Log Sheet is correctly completed and the discrepancies are noted. JPM Stop Time: NRC JPM ADMlN R01 Page 8 of 11

. '. . Appendix C Job Performance Measure WORKSHEET Form ES-C-1 Validation of Completion JPM Number: ~~- NRC -~ JPM ADMIN R01 ~__ _ Examinee's Name: __ ~ __ _ Exam in e r' s N am e: Date Performed:

Facility Evaluator: - __ __ - _~ - - Number of Attempts:

~-- ~ Time to Complete:

___ ~- _ ~- Question: - ~. Result: ~ .~ ~ Sat isfactory/U nsat isfactory Examiner's Signature and Date: NRC JPM ADMIN R01 Page 9 of 11

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

1. Reset to full power IC-65
2. Insert the following:
a. SW I-RMS050A to 1.1 (RB 1 19 E39 rad) b. SWI-RMS063A to 1.1 (RN 119 rad C9) c. SWI-RMS066A to 1 .O (RB vent rad mon) d. SWI-RMS067A to 1 .O (RB vent 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 R01 Page 10of 11

=. - Appendix C Job Performance Measure WORKS tl EET Form ES-C-1 STUDENT HANDOUT Initial Conditions:

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 Cue: Complete page El -1 only of the Techni,cal 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.

NRC JPM ADMIN R01 Page 11 of 11

_Oyster ~. - Creek Task No.: 20001 01404 Task Title: ~- Perform - a _-_ Manualcore Heat Balance-Calculation-

~ _-___~ ~ - Job Performance Measure No.: NRC JPM -- -. ADMIN -~- R02_(RO)_--

WA

Reference:

~ Generic __- _- 2.1.20 ~ (RO __ 4.3) E3 xam in e r : -- _--_- ---~ Examinee:

Facility Evaluator: - __ Method of Testing: X - Simulated Performance Actual Performance 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 reactor has been steady at full power for several hours. 2. The PPC is currently unavailable but is expected back shortly. 3. All prerequisites to perform this Frocedure have been met. Task Standard:

A manual core heat balarice 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: Perform a manual core heat balance IAW Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range. Compare this calculation to the reactor power displayed on the PPC when the PPC is returned to service. NRC JPM ADMIN R02 Page 1 of 17 I ' AppendixC Form ES-C-1 Job Performance Measure WORKS t-i EET ~ ~~ Time Critical Task: No Validation Time:

19 minutes NRC JPM ADMIN R02 Page 2 of 17

' Appendix C Job Performance Measure Form ES-C-1 WORKS t-i EET P e rfo rm a n ce Information Denote critical steps with a check mark 4 -- - Performance Step:

1 Procedure Step: Provides repeat back of initiating cue. ~ ._ Standard:

Provides repeat back of initiating the repeat back. JPM Start Time: - cue. Evaluator acknowledges Performance Step: 2 Procedure Step: Reviews Precautions and Limitations. - - ~___ Standard: Reviews Precautions and Limitations.

Comment: ~ - SAT/U NSAT Note: The expected values are provided in the KEY. NRC JPM ADMIN R02 Page 3 of 17

' AppendixC Job Performance Measure Form ES-C-1 WORKSI-IEET 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. - ~~ ~ J Performance Step: 4 _ Procedure Step: 5.1.1.2 Record Feedwater temper!ature (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 6 Comment: ~ __ _ _ ~ SAT/U NSAT NRC JPM ADMlN R02 Page 4 of 17

" AppendixC Job Performance Measure Form ES-C-1 WORKSHEET P e rf o r m a n ce I '1 f o r m a t i o n J Performance Step:

5 Procedure Step: 5.1.1.3 Obtain the specific volume (v) at the Feedwater at 110 psia and the temperature recorded ir.1 Step 5.1.1.2 from Attachment 1001.6- 3 or ASME approved steam tables. Obtain the specific volume (v) the temperature recorded iri 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. w= Standard: the Feedwater at 110 psia and \ J Performance Step:

6 ~--._ Procedure Step:

5.1.1.4 Calculates total Feedwater flow using the following equation:

F = 0.0429387 SQRT (QPh) Standard: Calculates total Feedwater flow using the following equation:

F = 0.0429387 SQRT (APiv) and records on the Feedwater Flow Calculation Worksheet, Line D. Comment: NRC JPM ADMlN R02 Page 5 of 17 AppendixC 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)

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. ~~~ ~ Standard:

Comment: ~ ~~__~ ~ ~ ~- ~ -. ~ ~~ _- - ~ 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: ~ .. NRC JPM ADMIN R02 Page 6 of 17

  • AppendixC Job Performance Measure WORKSHEET Form ES-C-1 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. S AT/U N SAT 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 pressure.

Calculate the reactor absoilute 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. Standard:

Comment: SATlUNSAT NRC JPM ADMIN R02 Page 7 of 17

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. _- S AT/U N SAT 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 11 00 psia using Feedwater temperature.

Standard: Reads the Feedwater enthalpy from Attachment 1001.6-6 or ASME approved steam table for compressed water at 11 00 psia using Feedwater temperature in step 5.2.2, and records on the Heat Balance Data, Calculation, and Analysis Worksheet, Line F SAT/U NSAT NRC JPM ADMIN R02 Page 8 of 17

~~ -~ ~ Performance Information J Performance Step:

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

Standard: Calculates the difference of the 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: ~ ~~ ~ - ~_. - ~ -~ S AT/U N SAT 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 ADMlN R02 Page 9 of 17

. ' AppendixC Job Performance Measure Form ES-C-1 WORKS ti E ET Performance Information J Performance Step:

15 Procedure Step: 5.2.9 Calculate the product of the Feedwater flow and the enthalpy difference to obtain MBTUIhr.

~~ 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:

5.2.1 0 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: SAT/UNSAT NRC JPM ADMlN R02 Page 10 of 17 AppendixC

., Job Performance Measure Form ES-C-1 WORKS-IEET Performance Information J Performance Step:

17 ~- - Procedure Step:

5.2.1 1 Record RWCU flow to the nearest gpm (recorder Panel 3F) on Line K of Attachment 1001 6-2. Standard:

Reads RWCU flow to the nlearest gpm (recorder Panel 3F) and records on the Heat Balanc:e Data, Calculation, and Analysis Worksheet, Line K. ~ ~ ~ S AT/U N SAT J Performance Step: 18 Procedure Step:

5.2.1 2 Calculate the CRD, recirc. pump power, RWCU and ambient losses adjustment (Fixed L.osses), per the following equation. Enter the appropriate value for Fixed Losses on Line L of Attachment 1001.6-2. Fixed Losses

= [(K) x 0.01 :36] + 9.0 Standard:

Calculates the CRD, recirc. pump power, RWCU and ambient losses adjustment (Fixed L.osses), 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: SAT/UNSAT NRC JPM ADMlN R02 Page 11 of 17

. *. . Appendix C Job Performance Measure Form ES-C:-1 WORKS H E ET Performance Information J Performance Step: 19

~~ Procedure Step:

5.2.13 Add the Fixed Losses from Line L to the Megawatts from Line J and record the Calculated CTP on Line N. Standard:

Adds the Fixed Losses frorn 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: - . .- S AT/U N SAT Cue: J Performance Step:

20 ~. Procedure Step: 5.2.14 Record PPC Core Thermali Power (CTP) in Line M. Standard:

The PPC has been returned to service long enough to establish the 15 minute average Core Thermal Power (CTP). The current CTP value is 1927 MWth. Records the PPC 15 minute average Core Thermal Power (CTP) on the Heat Balance Data, Calculation, and Analysis Worksheet, Line M. Comment: NRC JPM ADMIN R02 Page 12 of 17

. *.

  • Appendix C Job Performarice Measure WORKSIHEET

-~~ Form ES-C-1 Performance Information J -- Standard:

Comment: 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.

It negative, the comparison is non- conservative. Place an X in the appropriate box. Subtracts Calculated Core Power in step 5.2.1 3 from the PPC Core Thermal Power in step 5.2.14 and records on the Heat Balance Data, Calculation and Analysis Worksheet, Line 0. Checks the negative value

-4 Non-Conservative box on the Heat Balance Data, Calculation, and Analysis Worksheet.

Cue: Performance Step:

22 Procedure Step:

5.3 Verify that the RWCU system differential temperature is < 80 deg F. .. . Another Operator will verify the RWCU system differential temperature is < 80 deg F. This complete this JPM. Standard:

Comment: - ~~ S AT/U N SAT NRC JPM ADMIN R02 Page 13 of 17

. 1, . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information Terminating Cue: A manual core heat balance has been completed IAW Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range. JPM Stop Time: NRC JPM ADMIN R02 Page 14 of 17

" *. a Appendix C Job Performance Measure W 0 R KS H E ET Form ES-C-1 Validation of Completion NRC JPM ._ -~ ADMIN ~ R02 . ~- JPM Number: -~ Examinee's Name: - Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

~ Time to Complete:

Question:

.- Result: Sat isfactory/U nsatisfactory Examiner's Signature and Date:

NRC JPM ADMIN R02 Page 15 of 17

1. Appendix C Job Performar*ice Measure Form ES-C-1 WORKSHEET Simulator Setup 1. Reset to full power IC-65. 2. Insert the following:
a. SWI-NSS021 A to 1020.0 psig (Reactor press recorder 5F/6F) b. SWI-CFW002A to 31 1 "F (FW temperature recorder 5F/6F) c. SWI-NIS001 B to 150090 Ib/hr (recirculation flow recorder 3F)
d. SWI-RCU002A to 400.1 gprri (RWCU flow recorder 3F) 3. Have a blank copy of procedure 1001.6 ready. 4 Provide the Candidate a calculator.

NRC JPM ADMIN R02 Page 160f 17

. -. . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET STUDENT biANDOUT Initial Conditions:

1. The reactor has been steady at full power for several hours. 2. The PPC is currently unavailable but is expected back shortly. 3. All prerequisites to perform this procedure have been met. Task Cue: Perform a manual core heat balance IAW Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range.

Compare this calculation to the reactor power displayed on the PPC when the PPC is returned to service. NRC JPM ADMIN R02 Page 17 of 17

7. ' AppendixC Job Performance Measure Form ES-C-1 W 0 R KS t-i E ET Facility:

__ Oyster Creek ~ Task No.: 21 ~~ 501 01 _. 023 - ~ ___ - Task Title:

Perform APRM Drawer Count Job Performance Measure No.: NRC JF:)M ADMlN R03 (RO) WA

Reference:

Generic 2.2.1 2 -~ (RO 3.0) Exam in e r : ~- ~ ~ __~ Examinee:

~ _ __ ~ Facility Evaluator: ~ ~ __ - [late: 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 indicate bypassed.

Required Materials: A completed attachment 403-2, with no APRMs bypassed, and LPRMs36-17B, 28-090 and 44-25D shown as bypassed.

Gene ra I References

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 R03 Page 1 of 11

' ' AppendixC Job Performance Measure WORKSHEET Form ES-C-1 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:

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

~-~ ~ 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 LPRMs36-176,28-09D, and 44-25D in the APRM 8 column. Comment: ~ SAT/U NSAT NRC JPM ADMIN R03 Page 2 of 11

' AppendixC Job Performance Measure WORKSHEET Form ES-C-1 ~ -- 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: -- __ _. S AT/U N SAT Performance Step: 4 Standard:

CUE: Comment: Procedure Step:

5.: Obtains permission count. Obtains ermissioq count. P I The can idate ma directed go pe rfo rd they havie permissic I I I .------r I I SAT/U NSAT I I I I i ' ~ I I NRC JPM ADMIN RO~ 3.8.1 of Procedure 403. 'om tbg US for LPRM input to APRM draw 'om the US for LPRM input to APRM draw 11 not ask permission since he was :. If the candidate does ask, state th dorm the APRM drawer count. _~_ Page 3 o 11

- I. 4 Appendix C Job Performar-ice Measure Form ES-C-1 W ORKSH *ET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power. Task Cue: Perform Section 2 of Attachment 202.1-1, APHM Status Check, for APRM 8. Notify the Unit Supervisor of your results. NRC JPM ADMlN R03 Page 11 of 11

. P,. . Appendix C Job Performance Measure Form ES-C-1 WORKS t-i EET Facility: Oysler Creek T'ask No.: 2000501 433 Task Title:

Determine

~ - RPV Water -- Level Instrument Availability - Job Performance Measure No.: NRC JF'M ADMIN R04 -~ (RO) K/A

Reference:

f:! xa m in e r : Examinee:

~~ - Facility Evaluator:

[late: Method of Testing: Simulated Performance

~~ 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 LOCA occurred in the Primary Containment.
2. The Primary Containment Control EOF' 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:

I Temp. ~ Recorder lnstr7iment NO. Point 1 I t i- 1 I ~ TE-103-450 1 40 ' TE- 103-451 41 42- I t TE-103-452 TE- 103-453 I 43 TE-103-454 1 44 1 1- c 1 ~ 1- -- -1 L-- ~ - __~- . -. .- Temperature I "F I NRC JPM ADMIN R04 Page 1 of 8

, ,* . Appendix C Job Performance Measure Form ES-C-1 W ORKSI-I EET 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 F3PV 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 R04 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:

Comment: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. - -- 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:

Comment: 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.

SAT/U NSAT NRC JPM ADMlN R04 Page 3 of 8

.. 0 Appendix C Job Performarce 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 A and NR GEMAC B 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 B indicated water level at the given reference leg temperatures on the YARWAY curve. Determines that YARWAY B is not in the Safe Region and thus is not available for RPV water level instrumentation.

Comment: SAT/UNSAT NRC JPM ADMIN R04 Page 4 of 8

>#. 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 indicated 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: ~ ~ -. SAT/U NSAT Terminating Cue: IAW the reference provided, the Candidate has determined that only NR GEMAC B is available for RPV water level indication.

JPM Stop Time: - NRC JPM ADMlN R04 Page 5 of 8

.?- Appendix C Job Performarice Measure WORKSHEET Form ES-C-1 Validation of Completion NRC JPM __~ ADMIN 1304 - _ JPM Number: __ Examinee's Name: - -- -- -- Examiner's Name: ~ -~ - --. - Date Performed:

_ Facility Evaluator:

-_~ __ Number of Attempts: ~ ~ __~ -_. - Time to Complete: - Question:

Result SatisfactoryAJnsatisfactory Examiner's Signature and Date: - ~ NRC JPM ADMIN R04 Page 6 of 8 I -4 Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Simulator Setup 1. None. 2. Have a blank copy of Support Procedure 28, EMG-SP28, Level In st r u menta tion Availability ready. NRC JPM ADMIN R04 Page 7 of 8

.. a, Appendix C Job Performarlce Measure WORKSHEET Form ES-C-1 STUDENT tjANDOUT Initial Conditions:

1. The Plant was at rated power when a LOCA 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 run temperatures, along with the current water level indications:

I i Level Instrument 1 RPVWater ! Temp. 1 Recorder 1 TemDerature "F 1 Level Readinq Instrument No. Point -- I- ~ -- [- - 89" 1 340 i --- 1 TE-103-450 1 40 1 TE-103-452 42 360 - -1 1 TE-103-451 335 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. NRC JPM ADMIN R04 Page 8 of 8

,? -

-- ~~ ~- - - _~_ __ ~ Job Performance Measure No.: ---- NRC - JPM - - _ ADMlN -- SROJ LSRO) __ - - WA

Reference:

-Ge-neric 2.1.3 (SRO 3.41- _~ _ _~ Examiner: - Examinee:

_ - _. - - ..__ ._ - Date: Facility Evaluator:

-~ ____ - Method of Testing: X S im u lated Performance - Actual Performance - __ - __ - 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 is at rated power. 2. You are the oncoming Unit Supervisor after being off for the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3. Your last shift was completed at 2400 on April 18, 2008. 4. The current date/time 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, Guidance for Limiting and Administrative Conditions for Operations, revision
0. 4. Procedure 324, Thermal Dilution Pumps, revision 69. NRC JPM ADMIN SRO1 Page 1 of 14

,I I 7 AppendixC Job Performance Measure Form ES-C-1 WORKS I--I E ET 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.

Time Critical Task: No. Validation Time: 22 minutes NRC JPM ADMIN SROI Page 2 of 14

. I AppendixC Job Performance Measure WORKSHEET Form ES-C-1 Performance I n f o rmat io n Denote critical steps with a check mark J Performance Step:

1 Procedure Step: Provides repeat back of initiating cue. JPM Start Time: Standard:

Comment: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. Provide the completed Turnover Sheet. ~ ~._. SAT/UNSAT Note: The following steps may be performed in any order.

J Performance Step:

2 - Procedure Step:

Reviews the 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: NRC JPM ADMlN SRO1 Page 3 of 14

. AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 3 Procedure Step:

Reviews the Turnover Checklist.

Standard:

Reviews the Turnover Checklist and notes the following:

0 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at greater than 80% rated load until repairs are completed.

Procedure OP-OC-I 08-1 04-1001 , 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from when EGD 1 was declared inoperable - not 24 lhours 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, 2008. Comment: ~~ ~~ ~- -~ ~~~~ - ~- - - NRC JPM ADMIN SROl Page 4 of 14

.. . , AppendixC Job Performarice Measure Form ES-C-1 WORKSHEET Perf or mance lnf or mat ion J Performance Step: 4 Procedure Step: Reviews the Turnover Checklist.

Standard: Reviews the Turnover Checklist and notes the following:

IAW Procedure 324, if all dilution pumps are tripped (which is the case of a loss of power to the dilution plant) and cannot be immediatc?ly restarted, reduce power as necessary to maintain main condenser outlet temperature c 97 "F to minimize the impact on the environment.

A 2-hour report to the [IEP via the NJDEP Environmental Hotline (1 -877-927-6337) shall be made. A written report shall be generated IAW the NJPDES part IV if bridge temperature exceeds 97 "F. Comment: - - -_ -- __ - - Terminating Cue: The Candidate has reviewed the turnover checklist and noted the discrepancies and any associated actions. JPM Stop Time: NRC JPM ADMIN SROl Page 5 of 14

., . I AppendixC Job Performance Measure WORKSHEET Form ES-C-1 Validation of Completion JPM Number: .~ NRC - - JPM ~ ADMIN ~~ SRO1 ~ Examinee's Name: - -~ - _-_ Date Performed:

~~ __ Facility Evaluator:

__ Number of Attempts:

Time to Complete:

Question:

Result: Satisfactory/Unsatisfactory

~ Examiner's Signature and Date: ~. - - ~- NRC JPM ADMlN SRO1 Page 6 of 14 I*

  • 8 AppendixC Job Performarice Measure Form ES-C-1 WORKSHEET Sirnulato!

Setup 1. None. NRC JPM ADMIN SROl Page 7 of 14

.* I .' '.. Appendix C Job Performance Measure Form ES-C-1 W 0 R KS H E ET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power. 2. You are the oncoming Unit Supervisor after being off for the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. 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) and note any discrepancies and/or any required actions.

NRC JPM ADMIN SRO1 Page 8 of 14

i L 0P-0c-100-1002 Revision 5 DCC FILE # 2'0 70 01 01 03 MAIN CONTROL ROOM TURNOVER CHECKLIST (OPERATING MODE)

Xenon(Checkone) 7 Rising xi 1 -- -1 I - -I 1 Stack RAGEMS SampleandEff&ent Flow - Functional Test, 621 3 024 - __- _______ __ ---- -_______________

__ Reactor Hi/Lo Level Bistable Test and Calibration, 619.3 113 I I Surveillance(s) in progress ,-- - I-- - _- I Fire Hose Station, Hose House and Fire Hydrant Inspection, 645 6 003, I followinga - fire drill earlier in the shift Activities in progress __ - I Safety System ___-___-___

Status rGai;if&&n or comooncnts that are in a dczraded mode ofooeration ocrmittcd bi the Technical Soecifications. For each system, comoare the i. 1 length of time it i\ degraded with the Technicai Specification Acbon Statenlent. Specify the ficcpency ol redundant sy\tern verification or tevting and tIlctlate/tinle of the last test -_ - - __ __-____ _~_ - ______ _________ - APRM 1 is in BYPASS due to failure of the APRM Surveillance Test - Front Panel Check (620.4.002) All other EDG 7 tagged out of service at - 2%O-On4/18/08-7:day-LCO

-_ EDG 2 testing-every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> __ _ APRMs operable- . __ --- -~ __ - - C om p ensa t olllyC om m en t s ~__ ___ - __ ______-_ __-_____________

__- - - __ ______ Li5t my cornpenutorj actions in effect as a result of Procedure CC-AA-I 12 (1 emp Mod), Procculure WC-AA-IO1 (On-Line Maintenance).

out of 1- ice pl:iiit equlpinent or components, or as directid hy the MI or OS. - _- __ - - - - EDG 2 and associated

__ _ systemSare - protected IAW Procedure 341 due to EDG 1 inoperable (annunciators T4b, T5b)

Recording - _ Offgas Radiation

---p__ Monitor - -- levekevery-hour due io AOG trp Noadverse trends . noted p__ - -- - -- - p__- ___________ Turnover Comments

______ EDG 1 declared inoperable at 2000 on 4/18/08, and tagged out 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 p- com-plete a satisfactory surveiance by2300-on 4/19/08 -- The Dilution Plant tripped at 090Oonb/l9/08 Alternate power cannot be tied-in Electrical Maintenance suspects a short and are continuing to investigate Intake temperature is 50 "F No actions have occurred yet except to investigate (Annunciators - 12XR2-4, 12XR2-6, 12XR3-4, 12XR35, and 12XR3-6) AOG tripped 1600 4/18/08 and remains out of service All required actions completed (Annunciatok 10F3b, 10XF3d, 1 OXF4d) -- ._ Page 9 of 14 0P-0c-100-1002 Revision 5 DCC FILE # 20.70.01.01.03 Going Shift Coming Shift * - __ 1 _ -

  • Signature acknowledges all qualifications to stand watch are current and any changes in medical status have been reported IAW OP-AA-105-101 NRC JPM ADMlN SRO1 Page 10 of 14

. 1. MAIN CONTROL ROOM TIJ IINOVER CNECKI,ISrc (CONTINUED) 0P-0c-100-1002 Revision 5 DCC FILE # 20.70.31.01 03 BYP CHAN 1 in nojmal_ TORUS/DWVENT

&PURGE isol VLVS HIRAD I Yes I + NO .L- Main Generator Digital Protective Relay System (DPRS A and B) operating with no abnormal 1 x 1 Yes indications - - - - - - - l-- NRC JPM ADMlN SRO1 Page 11 of 14 0P-0c-100-1002 Revision 5 DCC FILE il20.70.01.01.03

__ __ _. - - __ - . - ___. ___ __ __ . - . . - _- - . - __ __ ___ - __ - ___ - General Turnover Checks :ore-Maneuvering Daily Instruction Sheet, Attachment 1001.22-3 is current and reflects-plant operating con@tions.

--- - --~ Control room panel walkdown performed neaiend of shift - ~ ~ -~ Control room-panelwalkdown performed with oncoming shift. - ~ Performedlight test on alarm winJows. ___ ~ - - - -___ - AX -- ~ ^_-__ - _~_----___I__--_I---I_--_

Reviewed reasons for annunciated alarms with all operators NRC JPM ADMIN SROI Page 12 of 14

. 0. ., 0P-0c-100~~1002 Revision 5 DCC FILE ii 20 70.01.01.03 Shift 0000 - 1200 A 1% 3000 SAT gpm. Declare ESW Pump 52A inoperable and apply TS due to low flow. SAT NRC JPM ADMIN SR03 Page 4 of 10 AppendixC Job Performance Measure Form ES-C-1 WORKSHEET

  • . ACCEPTANCE CRITERIA Step SAT/UNSAT 7.2.2 SAT Required Action if UNSAT/Reason 7.2.3 UNSAT CRITICAL Containment Spray Pump 51 B vibration 4A is above the action range. Declare Containment Spray Pump 51 B inoperable and apply TS. ~ ~~~~~~ - - - ~ - _- ~~~ 7.2.4 UNSAT Valve V-21-17 strokes outside the accept range but CRITICAL less than the limiting value. Retest immediately or declare inoperable and apply TS. ~~ 7.3 7.4 SAT SAT None ~~ NRC JPM ADMIN SR03 Page 5 of 10

' *' ' AppendixC Job Performarce Measure Form ES-C-1 WORKS 1-1 E ET Validation of Completion JPM Number:

NRC JPM ADMIN SR03 _ Examinee's Name: _ Exam in e r' s N am e : Date Performed:

~_ ___ _ ~- _ - Facility Evaluator:

_. ~_ __ _ ~ -_ - Numberof Attempts:

~ _ -_ - __ ~. __ Time to Complete:

Question:

Response : Result: Satisfactory/Unsatisfactory Examiner's Signature and Date: NRC JPM ADMIN SR03 Page 6 of 10

'

Setup 1. None. 2. Provide pages 43 through E4-4 ONLY of 607.4.004.

3. Make the following steps unsat on the test: a. Step 7.1.4:

Lineout 31 00 and insert 3000. Initial and date. 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 ACiCEPT 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

. 1, Appendix C Job Performance Measure Form ES-C-1 WORKS'HEET STUDENT HANDOUT Initial Conditions:

1. The plant is at rated power.
2. Surveillance test, 607.4.004, Containment Spray and Emergency Service Water System 1 Pump Operability and Comprehensive/Preservice/Post-Maintenance Inservice Test, has ju!;t 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 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 NRC JPM ADMIN SR03 Page 8 of 10

. ' AppendixC Job Performance Measure WORKSHEET Form ES-C-1 STUDENT. HANDOUT ACCEPTANCE CR ITER I A Step SATIUNSAT Requived Action if UNSAT/Reason NRC JPM ADMIN SR03 Page 9 of 10 Appendix C . 2, c Job Performance Measure WORKSHEET Form ES-C-1 STUDENT HANDOUT ACC E PTANC: E CR ITER I A Step SAT/UNSAT Required Act ion if U NSAT/Reason 7.2.3 73 SAT None None 7.4 SAT - - - - - ~- - -- NRC JPM ADMlN SR03 Page 10 of 10 c Appendix C Job Performarice Measure Form ES-C-1 WORKS H E ET Facility:

_. Oyster Creek Task No.: Task Title: Initiate __ ~ - Dose Control ~~~ Extension ~ ~~ Forms . -~ . - Job Performance Measure No.: NRC JPM ADMIN SR04 (SRO) K/A

Reference:

Generic ___ 2.3.1 (SRO 3.0) Exam in e r: ~ ~ ~~~~ ~-~ Examinee:

Facility Evaluator:

Date: . ~ . Method of Testing: X Simulated Performance

-~ ~- .Actual Performance

~ __ ~ Plant Classroom - __ X Simulator

~_ ~ 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. - ~- ~- ~~ NRC JPM ADMIN SR04 Page 1 of 10 I Appendix C - -- -- - -1 I --Name- -1 & Current year 1 -- TED E mrem - - - --_ -- - -: 1- - -- 11 1-1 1-1 11 1 1950 1 Fully qualified EO - - I - 350 1750 ~ Fully qualified EO 1 Fully qualified EO; Declared pregnant on 1/1/08 - - -- - - Bill Block .- - Dave Draper 333-33-3333

~ I ~ - Job Performance Measure Form ES-C-1 W 0 R KS H E ET Initial Conditions:

1. The plant was shutdown for an extended outage to replace valves in Reactor Recirculation Loop A. 2. No Reactor Recirculation Pumps are running.
3. The following job is scheduled for next shift: a. Grease the suction valve lirriitorque in Recirculation Loops B and C. b. Manually cycle the valve once (0 - t C, C - 0) after lubrication.
c. Perform RBCCW valve lineups on Reactor Recirculation Pumps and Motors B and C. d. The job will be performed by 2 Equipment Operators; each performing the work on 1 Reactor Recirculation Pumps/Motors.
e. The dose rate in the work area is 325 mrem/hr.
f. Greasing each valve will take 10 minutes. g. Manually cycling the valve (0 -+ C, C -+ 0) will take 10 minutes. h. The RBCCW valve lineup for each pump/motor will take 10 minutes. i. Independent verifications on the valve lineup will be performed later. 4. The available Equipment Operators next shift are listed below.

No other qualified individuals with lower current year routine TEDE will be available to perform this work. EO candidate in the OJT 1 Phase NRC JPM ADMIN SR04 Page 2 of 10 I*. I Appendix C Job Performance Measure Form ES-C-1 WORKSHEET - -~ __ _________~___

~__.~ ___________

Task Standard: Dave Draper and Greg Galler are selected to perform the job. A Dose Control Level Extension Form is initiated for each individual. Required Materials: Calculator. General

References:

1. Procedure RP-AA-203, Exposure Control and Authorization, revision
3. Initiating Cue: Select the 2 Equipment Operators to perform the job. Initiate Section 1 of Attachment 1, Dose Control Level Extension Form, to Procedure RP-AA-203, Exposure Control and Authorization, for the individuals selected to perform the job, if required.

The selected individual(s) will sign the form if the form is required, after initiation. Time Critical Task: No. Validation Time: 22 minutes NRC JPM ADMIN SR04 Page 3 of 10

.< Appendix C Job Performance Measure Form ES-C-1 WORKSIHEET Performance Information Denote critical steps with a check mark J' Standard:

Comment: Performance Step:

1 Procedure Step: Provides repeat back of initiating cue. JPM Start Time: Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

S AT/U N SAT Note: The step below is not proceduralized but is necessary to determine the dose to be received while performing the job. J Performance Step: 2

~ Procedure Step: Determines dose received to each worker.

Standard: Determines dose received to each worker:

10 minutes to grease the suction valve Iimitorque 10 minutes to cycle the suction valve 10 minutes to perform valve lineup o Total time per pump: 30 minutes o Total exposure for each worker:

0.5 hr x 325 mrem/hr

= 162.5 mrem Comment: SAT/UNSAT NRC JPM ADMIN SR04 Page 4 of 10

  • . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Performance Information J Performance Step: 3 - Procedure Step: Determines who is eligible to perform the job. Standard:

Determines who is eligible to perform the job. Determines that Carol Casper cannot perform the job since the dose received is greater than allowed for a declared pregnant worker (500 mR) Determines that Frank Fick cannot perform the job since he is not qualified.

Determines that of the 3 workers left, that Dave Draper and Greg Galler have the lowest current yearly accumulated dose and should be selected.

Comment: J Performance Step: 4 - -~ Procedure Step: Determines total dose to the workers Standard: Dave Draper: 1750 162.5 = 1912.5 mrem o Because his total does is less than the administrative limit of 2000 mrem, no dose extension is required Greg Galler: 1875 + 162.5 = 2037.5 mrem o Because his total does is greater than the administrative limit of 2000 mrem, a Dose Control Level Extension Form is required Comment: SATIUNSAT NRC JPM ADMlN SR04 Page 5 of 10 pi. Appendix C Job Performance Measure Form ES-C-1 W ORKS'HEET Performance Information J Performance Step: 4 Procedure Step: Initiates Section 1 of the Dose Control Level Extension Form for Greg Galler. Standard: Initiates Section 1 of the Dose Control Level Extension Form for Greg Galler: 0 Comment: __ - SAT/U NSAT Name: Greg Galler (critical step)

SSN: 555-55-5555 (critical step)

Answers NO to the question:

Are other qualified individuals with a lower current year routine TEDE available to perform this work? (not critical step)

States why an exten.sion above 2000 mrem routine TEDE for the year is neces:;ary for this individual:

To perform limitorque greasing, valve cycling, and valve lineups (or similar). (not critical) Requests a dose extension to 2500 mrem (1 875 + 162.5 = 2037.5 mrem.) (critical step)

Signs the form as the Requestor and dates not critical)

Terminating Cue: Dave Draper and Greg Galler are selected to perform the job. A Dose Control Level Extension Form is initiated for Greg Galler. JPM Stop Time: NRC JPM ADMlN SR04 Page 6of 10

.a? . Appendix C Job Performance Measure WORKSHEET Form ES-C-1 Validation of Completion NRC JPM ADMlN ~~ ~~~ SR04 JPM Number: - __ Examinee's Name: ~ ~ ~-~~ ~. Examiner's Name: Date Performed:

~~- - Number of Attempts: - -- Time to Complete:

_~ Question:

Response:

Result: SatisfactoryAJnsatisfactory Examiner's Signature and Date: ~ ~ ~-~ NRC JPM ADMIN SR04 Page 7 of 10 e t . Appendix C Job Performarice Measure Form ES-C-1 WORKSHEET

1. None. NRC JPM ADMIN SR04 Page 8 of 10
  • ,
  • Appendix C ll 1-1 1-1 1 ll Bill Block Carol Casper 1 222-22-2222 1950 300 __ - _- ~__ ~~ - --- - _ .- - . __ -- - -_ Job Performance Measure Form ES-C-1 WORKSHEET Dave Draper 1 333-33-3333 444 4444 STUDENT tiANDOUT 1750 1575 - Initial Conditions:
1. The plant was shutdown for an extended outage to replace valves in Reactor Recirculation Loop A. 2. No Reactor Recirculation Pumps are running.
3. The following job is scheduled for vext shift: a. Grease the suction valve limrtorque in Recirculation Loops B and C. b. Manually cycle the valve once (0 -- C, C - 0) after lubrication. c. Perform RBCCW valve lineups on Reactor Recirculation Pumps and Motors B and C. d. The job will be performed by 2 Equipment Operators; each performing the work on 1 Reactor Recirculation Pumps/Motors. e. The dose rate in the work area is 325 mrem/hr.
f. Greasing each valve will take 10 minutes. g. Manually cycling the valve (0 -+ C, C h. The RBCCW valve lineup for each pump/motor will take 10 rnin Utes. i. Independent verifications on [he valve lineup will be performed later. 0) will take 10 minutes. 4. The available Equipment Operators next shift are listed below.

No other qualified individuals with lower current year routine TEDE will be available to perform this work Name 1 SSN 1 Current year I- I j TEDEns EO Status I Fully qualified EO Fully qualified EO; Declared -1 1 Fully qualified EO EO candidate in the OJT Phase Fully qualified EO - ____- - ~ -- 4 pregnant on 1/1/08 I 1 ~ ~ -_ I - -_ < - _ -- NRC JPM ADMlN SR04 Page 9 of 10 c-. . Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Cue: Select the 2 Equipment Operators to perform the job. Initiate Section 1 of Attachment 1, Dose Control Level Extension Form, to Procedure RP-AA-203, Exposure Control and Authorization, for the individuals selected to perform the jots, if required.

The selected individual(s) will sign the form if the form is required after initiation.

NRC JPM ADMIN SR04 Page 10 of 10 c- ' ' AppendixC Job Performanlce Measure Form ES-C-1 WORKSHEET Facility: - Oyster Creek Task NO.: 2OOO5O2401-

-. __ - __ Determine Emergency Classification and Protective Action Task Title: - Recommendations

_. - -- __~- - Job Performance Measure No.: NRC JPM ADMIN SR05 (SRO) WA

Reference:

~~ Generic 2.4.29 (SRO 4.0) Examinee:

E! xam in e r : - Method of Testing: Simulated Performance Actual Performance X Classroom 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 automatic scram occurred 45 minutes ago. The following conditions currently exist: All but 8 control rods indicate full-in APRMs indicate downscale Reactor Engineering has determined that the reactor will remain shutdown under all conditions without boron RPV water level is

-60" with Core Spray injecting Drywell pressure is 28 psig Drywell temperature is 270 "F Main Stack RAGEMS indicates 4.1 pCi/cc HRN Drywell hydrogen indicates 3.1 o/o CHRRMS #l indicates 1320 R/hr CHRRMS #2 is downscale due to a loss of power Dose assessment shows the highest dose at or beyond the site boundary is 115mRem NRC JPM ADMIN SR05 Page 1 of 9 1 ' AppendixC Job Performance Measure Form ES-C-1 WORKSHEET Task Standard: The emergency has been classified and the PARS have been determined.

Required Materials:

None. General

References:

1. EP-AA-1010, Radiological Emergericy 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 IAW EP-AA-1010 (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 ADMlN SR05 Page 2 of 9

' AppendixC 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:

Comment: Provides repeat back of iniiiating cue. Evaluator acknowledges the repeat back. Handout first page of STUDENT HANDOUT. ~ J Performance Step:

2 ~- ~~~~ Procedure Step: Classifies ihe emergency as a General Emergency (FG1). Standard: Classifies the emergency as a General Emergency (FGI). This classification is made within 15 minutes from the JPM Start Time. Reasons: Loss of Fuel Clad barrier (RPV water level c -20"); Loss of Reactor Coolant barrier (RPV water level Loss of Primary Containment barrier (CHRRMS than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after shutdown).

0"); and Potential 121 0 R/hr less Note: Record time that the first page of the STUDENT HANOUT is received from each Candidate.

Comment: - ~ ~ SAT/U NSAT NRC JPM ADMIN SR05 Page 3 of 9 L Appendix C ,. h Job Performarwce Measure Form ES-C-1 WORKSHEET Performance Information

~ J Performance Step: 3 JPM Start Time: __ Note: Once the first page of the STUDENT HANDOUT is collected from all Candidates, provide the second page, read the Additional Conditions, the Cue. and record new start time for this section. Determine the Protective Action Recommendations (PARs)

IAW EP-AA-111 and EP-AA-11

'I -F-10. Provides repeat back of initiating cue. Evaluator acmowledges the repeat back Cue: Procedure Step: Determines the Protective Action Recommendations (PARS), Evacuate 2-mile radius and 5-mile downwind; shelter areas not evacuated (since there are no travel impediments). These areas 5-miles downwind include the SSW, SW, and WSW Recommend KI for the General Public within the EPZ Advise the EPZ to monitor EAS messages Standard: Determines the Protective Action Recommendations (PARs): Evacuate 2-mile radius and 5-mile downwind; shelter areas not evacuated (since there are no travel impediments).

These areas 5-miles downwincr include the SSW, SW, and WSW Recommend KI for the General Public within the EPZ Advise the EPZ to monitor EAS messages The PARs are determined within 15 minutes from the General Emergency classification.

Note: Comment: Record time that the second page of the STUDENT HANOUT is received from each Candidate.

~ ~- ~- ~ __ SATUNSAT NRC JPM ADMIN SR05 Page 4 of 9 Appendix C Job Performarice Measure Form ES-C-1 WORKSHEET Performance Information Terminating Cue: The emergency has been classified and the PARS have been determined. Record stop time on each Candidates' second page. NRC JPM ADMIN SR05 Page 5 of 9 Appendix C ,- - Job Performance Measure WORKSHEET Form ES-C-1 ~~ Va I id at ion of Co m p I e t io n NRC JPM ADMIN SR05 - __ --~ -_ -_ JPM Number: Examinee's Name:

-_- _.._ -- - - Examiner's Name: __ Date Performed: - - - _ Facility Evaluator:

-- Number of Attempts:

-- _- Time to Complete:

-- _~ -__ - - Question: - _- _ Result: Sat isfactory/U nsatisfactory Examiner's Signature and Date: NRC JPM ADMIN SR05 Page 6 of 9 Appendix C GI- Job Performarice Measure Form ES-C-1 WORKSHEET Simulator Setup 1. None. NRC JPM ADMIN SR05 Page 7 of 9

, 9.

  • Appendix C Job Performance 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: All but 8 control rods indicate full-in APRMs indicate downscale Reactor Engineering has determined that the reactor will remain shutdown under all conditions without boron RPV water level is -60" with Core Spray injecting Drywell pressure is 28 psig Drywell temperature is 270 "F Main Stack RAGEMS indicates 4.1 pCi/cc HRN Drywell hydrogen indicates 3.1 o/o CHRRMS #1 indicates 1320 R/hr CHRRMS #2 is downscale due to a loss of power Dose assessment shows the highest dose at or beyond the site boundary is 115mRem Task Cue: Classify the emergency event IAW EP-AA-1010 (include the EAL designation) and state the reason for this classification. Emergency Classification: Emergency Action Level designation:

Reason: - Name: Time: ..______I___ (NRC Only) When complete, hand in this paqe. NRC JPM ADMIN SR05 Page 8 of 9 d . 0. - Appendix C Job Performance Measure Form ES-C-1 WORKS 1-1 E ET STUDENT hANDOUT Initial Conditions: The plant was at rated power when an automatic scram occurred 45 minutes ago. The following conditions currently exist:

All but 8 control rods indicate full-in APRMs indicate downscale Reactor Engineering has determined that the reactor will remain shutdown under all conditions without boron RPV water level is -60' with Core Spray injecting Drywell pressure is 28 psig Drywell temperature is 270 OF Main Stack RAGEMS indicates 4.1 pCi/cc HRN Drywell hydrogen indicates 3.1 Oh CHRRMS #1 indicates 1320 R/hr CHRRMS #2 is downscale due to a loss of power Dose assessment shows the highest dose at or beyond the site boundary is 11 5 mRem Additional Initial Conditions: Environmental conditions show that the wind is from 50" at 20 mph There are no travel impediments Task Cue: e Actibn Recommendations (PARS) Protective Action Recommendations:

Time: ~ __-.______

Name: (NRC Only) NRC JPM ADMIN SR05 Page 9 of 9

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