ML063060342

October 2006 Exam - Draft Section a Operating Exam (Folder 2)

ML063060342
Person / Time
Site:	Oyster Creek
Issue date:	09/05/2006
From:	AmerGen Energy Co
To:	D'Antonio J Operations Branch I
Sykes, Marvin D.
References
Download: ML063060342 (67)

Text

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

Facility: Ovster Creek Task No: 2000101404 Task

Title:

Perform a Manual Reactor Heat Balance Job Performance Measure No: NRC Admin R01 WA

Reference:

Examinee: NRC Examiner:

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

-J performance measure will be satisfied.

Initial Conditions:

I . The Reactor is at 100% power with all systems normally aligned.

2. No transients are in progress.

3. Reactor water level, power, and pressure are stable.

4. Feed pump discharge pressure is 1300 psig for all three loops.

5. The PPC is unavailable.

Task Standard: A manual reactor heat balance has been completed IAW Procedure 1001.6.

Required Materials: Calculator General

References:

Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range, Rev. 26 Initiating Cue: Perform a manual reactor heat balance IAW with procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range.

NRC Admin R 0 1 Page 1 of 11

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Time Critical Task: No C

Validation Time: 18 minutes Simulator Setup: IC-65.

NRC Admin R 0 1 Page 2 of 11

Appendix C Form ES-C-1

- Performance Information Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

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

Comment:

Performance Step: 2 Standard: Obtains a copy of the reference procedure and reviewhtilize the correct section (Procedure 1001.6, Section 5).

Comment:

Performance Step: 3 Standard: Verifies Prerequisites and reviews Precautions and Limitations.

Comment:

NRC Admin R 0 1 Page 3 of 11

Appendix C Form ES-C-1

-- Performance Information Performance Step: 4 (step 5.1 -1)

Standard: Calculates feedwater flow per Method 1 by performing the following:

1. Requests EO to report total feedwater Ap in inches of water from venturi transmitter FT-422-1 in the Feedwater Pump Room and records.

CUE: As the EO,report reading on FT-422-1 as 489 inches of water Ap.

2. Records feedwater temperature from 5F/6F Recorder (ID01Ol), rounded to nearest whole degree.

3. OBTAIN the specific volume (v) of the Feedwater at 1100 psia and the temperature above from Attachment 1001.6-3 and records.

Comment:

Performance Step: 5 (step 5.2.1)

Standard: Records reactor pressure to the nearest whole pound. (Narrow range recorder Panel 5F/6F)

Comment:

NRC Admin R 0 1 Page 4 of 11

Atmendix C Form ES-C-1 Performance Information

'*L/

Performance Step: 6 (step 5.2.2)

Standard: Records Feedwater temperature to the nearest whole degree. (Recorder panel 5F/6F)

Comment:

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

Performance Step: 7 (step 5.2.3)

Standard: Records recirculation flow to the nearest thousand gpm. (Recorder panel 3F)

Comment:

Performance Step: 8 (step 5.2.4)

Standard: Calculates the reactor absolute pressure by adding the value of step 5 (step 5.2.1) + 14.7 pounds pressure and records.

Comment:

NRC Admin R 0 1 Page 5 of 11

Appendix C Form ES-C-1 Performance Information ii Performance Step: 9 (step 5.2.5)

Standard: Records Main Steam enthalpy from Attachment 1001-6-5,at saturated conditions using calculated absolute pressure.

Comment:

Performance Step: 10 (step 5.2.6)

Standard: Records the Feedwater enthalpy from Attachment 1001.6-6 for compressed water at 1100 psia using Feedwater temperature.

Comment:

Performance Step: 11 (step 5.2.7)

Standard: Calculates the difference of the Main Steam and Feedwater enthalpies and records.

Comment:

NRC Admin R 0 1 Page 6 of 11

Appendix C Form ES-C-1 Performance Information i_/

Performance Step: 12 (step 5.2.8)

Standard: Records Total Flow Venturi method FLO (tot) from line (D) of the Feedwater flow calculation worksheet (Attachment 1001.6-1).

Comment:

Performance Step: 13 (step 5.2.9)

Standard: Calculates the product of the Feedwater flow and the enthalpy difference to obtain MBTU/hr and record.

-L/-,.

Comment:

Performance Step: 14 (step 5.2.1 0)

Standard: Converts MBTU/hr to Megawatts. (MBTU/hr x 0.293) and record.

Comment:

NRC Admin R 0 1 Page 7 of 11

Appendix C Form ES-C-1 Performance Information

\4 Performance Step: 15 (step 5.2.1 1)

Standard: Records RWCU flow to the nearest gpm (recorder panel 3F) on line (K)of Attachment 1001.6-2.

Comment:

Performance Step: 16 (step 5.2.12)

Standard: Calculates 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 Comment:

4 Performance Step: 17 (step 5.13)

Standard: Add the Fixed Losses from line (L) to the Megawatts from Line (J) and record the Calculated Core Thermal Power (CTP) on line (N). Acceptable values are 1900 - 1960 MWth (1930 MWth 2 1.5%).

Comment :

NRC Admin R 0 1 Page 8 of 11

Appendix C Form ES-C-1 Performance Information Performance Step: 18 (steps 5.2.1 4/5.2.15)

Standard: Marks these steps as N/A since the PPC is not available.

Comment:

Performance Step: 19 (steps 5.3/5.4)

Standard: 1. Verifies that the RWCU system differential temperature is e 80 deg F (step 5.3)

CUE: Inform the Candidate that another Operator will perform step 5.3.

2. Provides completed calculation to the SRO. (step 5.4)

Comment:

Terminating Cue: A manual reactor heat balance has been completed IAW Procedure 1007.6.

JPM Stop Time:

NRC Admin R 0 1 Page 9 of 1 1

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Admin R 0 1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

• =

Response

Result: SatisfactoryAJnsatisfactory Examiners signature and date:

NRC Admin R01 Page 10 of 11

Appendix C Form ES-C-1 u

STUDENT HANDOUT Initial Conditions:

1. The Reactor is at 100% power with all systems normally aligned.

2. No transients are in progress.

3. Reactor water level, power, and pressure are stable.

4. Feed pump discharge pressure is 1300 psig for all three loops.

5. The PPC is unavailable.

Task Cue:

Perform a manual reactor heat balance IAW with procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range.

NRC Admin R 0 1 Page 11 of 11

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

.-j Facility: Ovster Creek Task No: 2150101005 Task

Title:

Perform Core Dailv Checks (APRM Drawer Count)

Job Performance Measure No: NRC Admin R02 WA

Reference:

G2.1.2 (RO 3.O/SRO 4.0) G2.1.31 (R04.2/SRO 3.0)

Examinee: NRC Examiner:

Facility Eva1uator : 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.

Initial Conditions:

1. The plant is at full power.

Task Standard: The APRM Drawer count documentation is complete and the correct discrepancy has been identified.

Required Materials:

1. Copy of Attachment 202.1 -1, with the following LPRMs marked as BYPASSED in Section 1: 12-17D and 20-25D (inputs to APRM 7),28-33C (APRM l ) , and 12-17A (APRM 3).

2. Copy of Attachment 403-2, with the following LPRMs marked as BYPASSED:

12-17D and 20-25D (inputs to APRM 7),28-33C (APRM l ) , and 12-17A (APRM 3).

General References

1. Procedure 202.1, Power Operation, Rev. 98

2. Procedure 403, LPRM-APRM System Operations, Rev. 11 Initiating Cue: Verify LPRM inputs to APRM 7 IAW Procedure 202.1, Power Operation, Attachment 202.1-4, Section 2.

NRC Admin R 0 2 Page 1 of 8

Appendix C Form ES-C-1 Performance Information

~- ~ ~~

Performance Step: 4 (step 5.3.3.8.1 of procedure 403)

Standard: Obtains US permission.

CUE: Report US permission to continue.

Comment:

Performance Step: 5 (step 5.3.3.8.2)

Standard: Confirms APRM bypassing is allowed, and then places joystick for APRM 7 on Panel 4F to the CH 7 position. (Panel 4F)

- Performance Step: 6 (step 5.3.3.8.3)

Standard: Rotates APRM 7 drawer INPUT switch clockwise to the COUNT position. (Panel 5 R)

Note: The indication will read 60% (6 LPRM inputs).

Comment :

NRC Admin R 0 2 Page 4 of 8

Appendix C Form ES-C-1 Performance Information L--

4 Performance Step: 7 (step 5.3.3.8.3.a)

Standard: Continues to rotate the same INPUT switch to position 8, position 7, etc.

(Panel 5R)

MarksLPRM 12-17D and 20-25B as Bypassed on Attachment 202.1-1.

Marks the number of UNBYPASSED LPRMs as 6 on Attachment 202.1 -1.

Note: LPRMs 12-17 0 and 20-258 will indicate 0 when selected (bypassed).

Comment:

4 Performance Step: 8 (step 5.3.3.8.3.b)

.-- , Standard: Continues to rotate the same INPUT switch to the AVERAGE position.

NOTE: The APRM will again show 100°/o power on the meter.

Comment:

Performance Step: 9 (step 5.3.3.8.3.c)

Standard: Unbypasses APRM 7 by placing the APRM joystick from CH 7 to the neutral position (Panel 4F).

CUE: Procedure step 5.3.3.8.4 says to repeat the above manipulations for other APRMs, as required. No other APRM counts are required to be performed.

CUE: Procedure step 5.3.3.8.5 says to verify ALL APRM INPUT switches in AVERAGE and is not required.

LA>

NRC Admin R 0 2 Page 5 of 8

Appendix C Form ES-C-1

--.--, Performance Information Comment:

J Performance Step: 10 Standard: Initials completion on Attachment 202.1-1 and recognizes the following discrepancy: (initial not required for critical task)LPRM 20-25D had been shown as BYPASSED and is NOT BYPASSED.LPRM 20-25B had NOT been shown as BYPASSED and is BYPASSED.

Notifies the SRO of the discrepancy (not required for critical task).

Cue: As the SRO, acknowledge the report.

-J Comment:

Terminating Cue: The APRM Drawer count documentation is complete and the correct discrepancy has been identified.

JPM Stop Time:

NRC Adrnin R 0 2 Page 6 of 8

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Admin R 0 2 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

~ ~ ~

Result: SatisfactorykJnsatisfactory Examiners signature and date:

NRC Admin R 0 2 Page 7 of 8

Power Operation 99 ATTACHMENT 202.1-1 DAILY APRM STATUS CHECK NOTE: MARK FAILED OR INOP LPRMS WITH AN "XI. Complete work sheet per 202.1-4 instructions.

Section 1 : Perform nightly 2.^

403-3 Verified correct (initial) 403-4 Verified correct 9 (initial)

%l (28-49

--e-El-I

'Li Power Operation 99 ATTACHMENT 202.1-1 DAILY APRM STATUS CHECK NOTE: MARK FAILED OR INOP LPRMS WITH AN "X'. Complete work sheet per 202.1-4 instructions Section 1: Perform nightly 403-3 Verified correct (initial) 403-4 Verified correct (initial)

\ /

A (4) 20-09 28-09 El-I

AmerGen- OYSTER CREEK GENERATING Number nn cxelan company STATION PROCEDURE 202.1

-v Title Revision No.

Power Operation 99

1. From procedure 403, obtain the following information and document on attachment 202.1-1 the following:

a. Inoperable or bypassed LPRMs that are inputs to the APRM system. From 403-2 [ ]

b. All LPRMs in any inoperable or bypassed APRM Channel. From 403-2 [ I

c. Verify lights and markings on 4F panel match 202.1-1 [ I

d. Verify FCTR Card status and active LEDs are green and curve select display is 0 [ ]

e. Verify 403-3 LPRM/APRM STATUS LOG SHEET is up to date and initial. [ I

f. Verify 403-4 NON-INPUT LPRM STATUS LOG SHEET is up to date and initial [ ]

2. On the first Sunday of each month verify inputs to APRM drawers as follows.

a. Perform drawer in ut count per 403 and verify number of inputs matches and g

correct inputs are ypassed. [ I

.W b. Mark bypassed LPRM inputs to APRMs on section 2 of 202.1-1 [ I

c. Mark the number of Un-bypassed inputs on section 2 of 202.1-1 I.E. 8,7,6,or 5 [ ]

3. Perform a Screen Print of the PPC Core State Parameters Display. Verify thermal limits are acceptable and datehime of last case is reasonable. [ I

4. Determine the required APRM 100% Setpoint in accordance with Attachment 202.1-3. [ I

5. Adjust the APRMs according to the following equation: [ I APRM = Core Thermal Power from Heat Balance

• 100 Setting 00 percent setpoint

6. Perform a Screen Print of the PPC Reactor Heat Balance Display [ I Verify the following RWCU parameters are displayed:

RWCU Inlet Temp = 520 Deg. F (constant)

RWCU Outlet Temp = 440 De . F constant)

RWCU Flow = GPM 93F kecorder)

Record RWCU Flow as indicated on 3F Recorder, and verify this value is not more than 10 GPM higher than the PPC RWCU Flow Input.

7. Attach a Surveillance Review Form, Attachment 116-1,to the Reactor Heat Balance Display, the Core State Parameters Display, Attachment 202.1-1 and Attachment 202.1-3. [ I E4-1

AmerGm OYSTER CREEK GENERATING STATION Number A n [v'hCompany

. PROCEDURE 202.1

<L>- Title Usage Level Revision No.

Power Operation I 99 Prior Revision98incorporated the This revision 99 incorporates the following Temporary Changes: following Temporary Changes:

N/A TC-07/17/06-01 List of Paqes 1.Oto 41.O E l - I to El-2 E2-1 E3-1 E4-1 E5-1 to E5-5 E6-1 to E 6 4 E-7-1 1.o

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The plant is at full power.

Task Cue:

Verify LPRM inputs to APRM 7 IAW Procedure 202.1, Power Operation, Attachment 202.1-4, Section 2.

NRC Admin R 0 2 Page 8 of 8

AmerGen OYSTER CREEK GENERATING Number A n fxebn Company STATION PROCEDURE 202.1

'd' Title Revision No.

Power Operation 99 Section 2: Perform on the first Sunday of each month.

s Place an X in the box next to the LPRM's that are Bypassed 0 Place the number of un-bypassed inputs in last row. Perform drawer count per 403. Verify number of inputs correct and bypassed LPRM inputs are correct. (initial)

E1-2

\

Appendix C Form ES-C-1

~~

Performance Information i .-,- '

Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

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

Comment:

J Performance Step: 2 Standard: Reviews the clearance request against the reference materials. The clearance request isolation points are deficient for personnel protection due to the following:

1. The listed power supply for the breaker for SDC Pump C is incorrect: USS 1A2 is listed; the correct power supply is USS 162.

2. OP-MA-109-101, step 5.3.1.5, says that dual valve protection should be provided when isolating from an energy source of > 200" F or pressures >

500 psig.

a. SDC motor-operated Isolation valves V-17-19 (on the SDC pump suction side) and V-17-54 (on the SDC pump discharge side) must be CLOSED and have their breakers DE-ENERGIZED (Note: a motor-operated valve on the SDC pump discharge side, V-17-207, could be CLOSED and de-energized in place of V-17-54; there is no alternate isolation valve on the SDC suction side).

NOTE: The following items are not required: type of tag, clearance sequence, identification of venvdrain valves, or how a component is de-energized ( a breaker is opened/locked open/racked-0ut) .

Comment:

-L/.

NRC Admin R03 Page 3 of 7

Appendix C Form ES-C-1 Terminating Cue: The clearance has been found to be unacceptable for personnel protection (see reasons above).

JPM Stop Time:

. I li NRC Admin R 0 3 Page 4 of 7

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Admin R 0 3 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

~~~~

Result: SatisfactoryAJnsatisfactory Examiners signature and date:

NRC Admin R03 Page 5 of 7

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The plant is hot at 295" F,and is cooling down with Isolation Condensers.

2. Shutdown Cooling Pumps A and B have motor shorts and cannot be used.

3. Shutdown Cooling Pump C was placed into service and found to have high vibrations and was subsequently secured. Engineering has determined that Shutdown Cooling Pump C needs an internal inspection.

4. No Shutdown Cooling System isolations are in effect.

Task Cue:

Attached is the clearance request (from Maintenance) for Shutdown Cooling Pump C.

Confirm the isolation points meet the requirements for personnel protection under the given conditions.

NRC Admin R 0 3 Page 6 of 7

Appendix C Form ES-C-1 STUDENT HANDOUT Clearance Request Work to be performed: Perform an internal inspection of Shutdown Cooling Pump C Clearance Isolation Points:

Electrically isolate Shutdown Cooling Pump C Place Shutdown Coolina /

0 Pumr, C control switch in PTL 0 DE-ENERGIZE Shutdown Cooling Pump C breaker on 480V US@ 1 62 DE-ENERGIZE Shutdown Cooling Pump C motor heaters (if there are any) 4 0 Hydraulically isolate Shutdown Cooling Pump C Place Shutdown Cooling Pump C suction valve V-17-3 switch in CLOSE Place Shutdown Cooling Pump C discharge valve V-17-57 switch in CLOSE(

0 DE-ENERGIZE1Shutdown Cooling Pump C suction valve V-17-3 breaker on MCC-DCl ./

DE-ENERGIZE1Shutdown Cooling Pump C discharge valve V-17-57 breaker on MCC-DC1/

~-\~+) r?

Isolate RBCCW to Shu down Cooling Pump C

.J c/@id v-n-sY v-t 03 o CLOSE V-5-207 and V-5-208 dr c I.re eb When the pump has been isolated, then drain the isolated portion of Shutdown Cooling Pump C OPEN the appropriate Shutdown Cooling Pump C vents and drains2 NOTES:

1. de-energize means to remove electrical power by the appropriate means (opening the breaker, or opening the breaker and locking open, or racking-out of the breaker).

2. identification of vents and drains is not required.

3. all valves are considered operable, such that an open valve will allow full flow (no blockage), and a closed valve allows no flow (no leakage).

4. the sequencing of steps is not required.

NRC Admin R03 Page 7 of 7

Appendix C Form ES-C-1 Performance Information J Performance Step: 3 (Procedure EP-OC-1010) (Timed Critical Step #1)

Standard: Classifies the emergency as a General Emergency 0 MGl: Prolonged Loss of ALL Offsite AC Power AND Prolonged Loss of ALL Onsite AC Power 0 The emergency classification is made 5 15 minutes from the start time.

Comment:

Critical Task #1 Stop Time:

Critical Task #2 Start Time:

u Performance Step: 4 (Attachment 1 of EP-OC-114-100)

(Timed Critical Step #2)

Standard: Completes the StatdLocal Notification Form (Page 1 ONLY is required). The critical steps are identified below:

Block 3: Classification: General Emergency; Declared at: actual time/date 0 Block 4: EAL Number: MG1; Brief Non-Technical

Description:

Prolonged Loss of ALL Offsite AC Power AND Prolonged Loss of ALL Onsite AC Power (or similar)

Block 5: Non-Routine Rad Release: None in progress Block 6: Meteorology: Wind direction from 90"; Wind Speed 10 mph Comment:

NRC Admin SROl Page 4 of 7

Appendix C Form ES-C-7 Validation of Completion Job Performance Measure No. NRC Admin SRO1 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

.---- - Response:

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Admin SROl Page 4 of 7

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The plant was at full power when an automatic scram occurred 30 minutes ago

2. Off-site power was lost when the scram occurred and both EDGs have failed to start and are being investigated

3. No combustion turbines have been able to supply power to the plant

4. The RPV Flooding - No ATWS EOP has been entered

5. No radiological release is in progress

6. Winds are from the East at 10 mph

7. The Shift Manager is not in the Control Room

8. No Emergency Plan Emergency Classifications have been made Task Cue:

Assuming the duties of the Shift Emergency Director, classify the emergency and complete the required notification forms IAW procedure EP-OC-114-100,State/Local Notifications.

L-NRC Admin SROl Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Ovster Creek Task No: 341010241 1 Task

Title:

Determine Shift Operatinq Compliment Job Performance Measure No: NRC Admin SR02 WA

Reference:

G2.1.4 (SRO 3.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

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:

1. The plant is at 100% power.

2. The following list of Operations shift personnel has just come to relieve the off-going crew:

Name Qualifications Hours Worked in last 6 Days Jim Abbott SM 48 NRC Admin S R 0 2 Page 1 of 6

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Task Standard: The shift coverage is determined to be adequate, with the exception that

'U' Karl Ralph needs a completed Overtime Guideline Deviation Authorization form prior to exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> worked.

Required Materials: None General

References:

1. Tech Specs, Section 6

2. OP-OC-100, Oyster Creek Conduct of Operations, Rev. 5

3. OP-OC-100-1001, Shift Coverage Log, Rev. 5

4. LS-AA-119, Overtime Controls Initiating Cue: Determine if the above Operations Shift Personnel meet the minimum duty shift coverage, as required by Technical Specifications, to stand and complete the watch.

Time Critical Task: No Validation Time: 10 minutes Simulator Setup: N/A NRC Admin SR02 Page 2 of 6

Appendix C Form ES-C-1 Performance Information u'

Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

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

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (Tech Specs, Section 6.2.2).

Comment:

Standard: Determines that the shift coverage is adequate, with the exception that Karl Ralph needs a completed Overtime Guideline Deviation Authorization form completed prior to exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> worked. (the exact form name is not required)

The candidate may decide to call-in another similarly qualified NLO in place of Karl Ralph who had fewer hours (564 hours0.00653 days <br />0.157 hours <br />9.325397e-4 weeks <br />2.14602e-4 months <br />) (this would be acceptable).

Comment:

NRC Admin SR02 Page 3 of 6

Appendix C Form ES-C-1 L./' Terminating Cue:

JPM Stop Time:

NRC Admin SR02 Page 4 of 6

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Admin SR02 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

LJ,' Response:

Result: SatisfactoryAJnsatisfactory Examiner's signature and date:

NRC Admin S R 0 2 Page 5 of 6

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The plant is at 100% power.

2. The following list of Operations personnel has just come to relieve the off-going crew:

Name Qualifications Hours Worked in last 6 Days Jim Abbott SM 48 Dave Brown US, IA 48 Bill Charles US, STA 40 Nick Deport RO 52 Allen Francis RO 56 Delores Klapper NLO, FBL 48

, I Todd Peterman NLO, FB 60

=.-----

Karl Ralph NLO, FB 68 Larry Tingley none (new to the NLO job) 52 Task Cue:

Determine if the above Operations Shift Personnel meet the minimum duty shift coverage, as required by Technical Specifications, to stand and complete the watch.

NRC Admin SR02 Page 6 of 6

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Facility: Oyster Creek Task No:

Task

Title:

Review Plant StartuD Checkoff Job Performance Measure No: NRC Admin SR02 WA

Reference:

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testinq:

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

in the initial conditions, which steps to simulate or discuss, and provide es: w h Z 5 - y 5 i p l e t e the tasK&ccessfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. The plant is shutdown with all control rods fully inserted

2. RPV coolant temperature is 120" F

3. The Reactor Mode switch is in REFUEL

4. Reactor start-up preparations are being performed IAW procedure 201 , Plant Startup

5. Attachment 201-4, Primary Containment Integrity and Drywell Closure Checkoff, has been completed by the off-going Crew Task Standard: The Checkoff has been reviewed and the discrepancies have been noted.

Required Materials: A completed Attachment 201-4 General

References:

Procedure 201, Plant Startup, Rev. 39 Initiating Cue: Review the completed Attachment 201-4, and make any comments to the Shift Manager.

Time Critical Task: No NRC Admin SR02 Page 1 of 6

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Validation Time:

Simulator Setup: N/A P

NRC Admin SR02 Page 2 of 6

Appendix C Form ES-C-1 Performance Step: 1 JPM Start Time:

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

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (201, Attachment 201-4)

J Performance Step: 3 (page 2)

Standard: While reviewing the Checkoff, reports the following deficiency:

0 Reactor Water Sample Valve V-24-30 is Not Operable and open. IAW the procedure, the valve should be secured in the closed position and their position indicators illuminated. (V-24-30 is an automatic containment isolation valve)

Comment:

NRC Admin SR02 Page 3 of 6

Appendix C Form ES-C-1 4 Performance Step: 4 (step 6.0, page 3)

Standard: While reviewing the Checkoff, reports the following deficiency:

0 There is an unauthorized Temporary Procedure Change. (Therefore, this step is not considered complete.)

Comment:

Terminating Cue: The Checkoff has been reviewed and the discrepancies have been NRC Admin SR02 Page 4 of 6

Appendix C Form ES-C-1

- I . .-

Validation of Completion Job Performance Measure No. NRC Admin SR02 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Result: SatisfactoryAJnsatisfactory Examiners signature and date:

NRC Admin SR02 Page 5 of 6

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The plant is shutdown with all control rods fully inserted

2. RPV coolant temperature is 120" F

3. The Reactor Mode switch is in REFUEL

4. Reactor start-up preparations are being performed IAW procedure 201, Plant Startup

5. Attachment 201-4, Primary Containment Integrity and Drywell Closure Checkoff, has been completed by the off-going Crew.

Task Cue:

Review the completed Attachment 201-4, and make any comments to the Shift Manager.

NRC Admin SR02 Page 6 of 6

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

'll' Facility: Oyster Creek Task No: 2260201402 Task

Title:

Evaluate AcceDtance Criteria Followina Surveillance Performance Job Performance Measure No: NRC Admin SR03 KIA

Reference:

G2.2.12 (SRO 3.4)

Examinee: NRC Examiner:

FaciIity Eva1uator : 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

\L-'

performance measure will be satisfied.

Initial Conditions:

1. The plant is at 100% power

2. Procedure 607.4.014, Containment Spray and ESW System 1 Pump Operability, IST, and Containment Spray Pumps Trip, has just been field completed (normal surveillance) and needs SRO review.

Task Standard: Containment Spray Pump 51A is declared inoperable (step 6.4.15) and valve V-21-18 (step 6.4.10) should either be declared inoperable or retested immediately.

Required Materials: Completed procedure 607.4.014 Genera1

References:

1. 607.4.014, Containment Spray and ESW System 1 Pump Operability, IST, and Containment Spray Pumps Trip Initiating Cue: Perform a review of Section 7.0, Acceptance Criteria, of procedure 607.4.014, Containment Spray and ESW System 1 Pump Operability, IST, and Containment Spray Pumps Trip NRC Admin SR03 Page 1 of 6

Appendix C Job Performance Measure Form ES-C-1 WORKSHEET Time Critical Task: No ii Validation Time: 30 minutes Simulator Setup: N/A NRC Admin SR03 Page 2 of 6

Appendix C Form ES-C-1 Performance Information LJ Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

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

Comment:

Performance Step: 2 Standard: Obtain a copy of the reference procedure and reviewhtilize the correct section (607.4.014, Section 7.0).

Comment:

Ll J Performance Step: 3 (step 7.1 . l )

Standard: Verifies that Containment Spray Pump 51A was below the acceptable valve for discharge pressure (minimum was > 60 psig; recorded in step 6.14.5 was 59 psig). Declares Containment Spray Pump 51A inoperable and applies TS 3.4.C (not required to discuss the actual K O ) .

Comment:

NRC Admin S R 0 3 Page 3 of 6

Appendix C Form ES-C-1 d

Performance Information Performance Step: 4 (step 7.1.6)

Standard: Verifies that valve V-21-18 recorded closing time (45.2 seconds) was longer than allowed by the acceptable range (32.2 - 43.5 seconds) but less than the Limiting Value (47.3 seconds) [see step 6.4.101. As required by 7.1.9.2, the valve may either be declared inoperable or retested immediately. If declared inoperable, then applies TS 3.4.C (not required to discuss the actual LCO).

Comment:

Performance Step: 6 Standard: All other components verified to meet the acceptance criteria.

Comment:

Terminating Cue:

JPM Stop Time:

NRC Admin SR03 Page 4 of 6

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Admin SR03 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

- ~~

Response

Result: SatisfactoryAJnsatisfactory Examiner's signature and date:

NRC Admin SR03 Page 5 of 6

Appendix C Form ES-C-1 STUDENT HANDOUT initial Conditions:

1. The plant is at 100% power

2. Procedure 607.4.014, Containment Spray and ESW System 1 Pump Operability, IST, and Containment Spray Pumps Trip, has just been field completed (normal surveillance) and needs SRO review.

Task Cue:

Perform a review of Section 7.0, Acceptance Criteria, of procedure 607.4.014, Containment Spray and ESW System 1 Pump Operability, IST, and Containment Spray Pumps Trip.

NRC Admin SR03 Page 6 of 6

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

Facility: Oyster Creek Task No: 3430302001 Task

Title:

Determine Radioloaical Access Requirements Job Performance Measure No: NRC Admin SR04 WA

Reference:

G2.3.1 (SRO 3.0)

Examinee: NRC Examiner:

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

.U, 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 90% power. The plant is to shutdown next week to enter a refuel outage.

2. Operations needs three more individuals to assign to the Leak Rate Team for the entire outage (scheduled to last three weeks).

3. Radiation Protection has provided historical dose accumulations for Leak rate Team members:

Week 1: 175 mrem Week 2: 110 mrem Week 3: 75 mrern

4. There are three extra Operators who will be assigned to you during the outage, as listed below:

Dave Carey: year-to-date exposure: 1825 mrem Peter Simpson: year-to date exposure: 1410 mrem 0 Julie Davis (declared pregnant worker): year-to-date exposure: 380 mrem (340 mrem has been received since she declared her pregnancy IAW RP-AA-203, Exposure Control and Authorization)

NRC Admin S R 0 4 Page 1 of 5

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

'.- Task Standard: The Candidate correctly states why/why not each RO cankannot participate as a Leak Rate Team member for the entire outage.

Required Materials: None General

References:

1. RP-AA-203, Exposure Control and Authorization, Rev. 2 Initiating Cue: Determine if each listed individual can be assigned to the Leak Rate Team for the entire 3-week outage.

Time Critical Task: No Validation Time: 18 minutes Simulator Setup: N/A NRC Admin SR04 Page 2 of 5

Appendix C Form ES-C-1 Performance Information U

Denote critical steps with a check mark

~~

Performance Step: 1 JPM Start Time:

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

Comment:

Standard: Makes the following determinations:

1. The total dose expected for the 3-week period is (175+110+75) 360 mrem (not required for critical task).

2. If Dave Carvey received this dose, his annual dose would be 2185 mrem.

This is above the administrative dose limit of 2000 mrem. This administrative limit can be raised to let Dave Carvey perform the task, but this documentation must be performed prior to Dave Carvey exceeding 2000 mrem (critical task)

3. Peter Simpson can, without any documentation, work on the Leak Rate Team for the entire period (critical task) since his total dose would remain below the same administrative dose limit (1410+360=1770~2000).

4. Julie Davis cannot join the Leak Rate Team for the entire time under any circumstance (critical task) since her total dose would be (340+360) 700 mrem. Her NRC exposure limit is only 500 mrem. This NRC limit cannot be exceeded.

Comment:

Terminating Cue:

JPM Stop Time:

• i NRC Admin SR04 Page 3 of 5

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Admin SR04 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Admin SR04 Page 4 of 5

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The plant is at 90% power. The plant is to shutdown next week to enter a refuel outage.

2. Operations needs three more individuals to assign to the Leak Rate Team for the entire outage (scheduled to last three weeks).

3. Radiation Protection has provided historical dose accumulations for Leak Rate Team members:

Week 1: 175 mrem W e e k 2 110 rnrem Week 3: 75 mrem

4. There are three extra Operators who will be assigned to you during the outage, as listed below:

Dave Carey: year-to-date exposure: 1825 mrem Peter Simpson: year-to date exposure: 1410 mrem Julie Davis (declared pregnant worker): year-to-date exposure: 380 mrem (340 mrem has been received since she declared her pregnancy IAW RP-AA-203, Exposure Control and Authorization)

Task Cue:

Determine if each listed individual can be assigned to the Leak Rate Team for the entire 3-week outage.

NRC Admin SR04 Page 5 of 5

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

Facility: Ovster Creek Task No: 341 010241 1 Task

Title:

Review/ADprove Manual Reactor Heat Balance Job Performance Measure No: NRC Admin SR05 WA

Reference:

G2.1.7 (SRO 4.4)

Examinee: NRC Examiner:

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.

Initial Conditions:

1. The Reactor is at 100% power with all systems normally aligned, except that the PPC is not available.

2. No transients are in progress.

3. Reactor water level, power, and pressure are stable.

4. Feed pump discharge pressure is 1300 psig for all three loops.

5. The Reactor Operator has just completed performing a manual reactor heat balance IAW procedure 1001.6, Core heat Balance and Feedwater Flow Calculation - Power Range. Feedwater flow was determined using Method 1.

Task Standard: Procedure 1001.6 has been reviewed and found not to be acceptable for approval as written.

Required Materials:

1. A completed procedure 1001.6, Core heat Balance and Feedwater Flow Calculation - Power Range

2. Calculator L*

NRC Admin SR05 Page 1 of 5

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

References:

Procedure 1001.6, Core heat Balance and Feedwater Flow Calculation - Power Range, Rev. 26 Initiating Cue: Perform a review/approval of the completed procedure.

Time Critical Task: No Validation Time: 10 minutes Simulator Setup: N/A NRC Admin SR05 Page 2 of 5

Appendix C Form ES-C-1 Performance Information

• e Denote critical steps with a check mark Performance Step: 1 JPM Start Time:

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

Comment:

J Performance Step: 2 Standard: Determines that step 5.2.13 (Step N in the table, Attachment 1001.6-2) is mis-calculated. The fixed losses (Step L) were subtracted from Step J instead of being added to Step J.

.\-.

NOTE: It is not required to correct the calculation.

Comment:

Terminating Cue: Procedure 1001.6 has been reviewed and found not to be acceptable for approval as written.

JPM Stop Time:

NRC Admin SR05 Page 3 of 5

Appendix C Form ES-C-1 Validation of Completion Job Performance Measure No. NRC Admin SR05 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

~ ~

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

NRC Admin SR05 Page 4 of 5

Appendix C Form ES-C-1 STUDENT HANDOUT Initial Conditions:

1. The Reactor is at 100% power with all systems normally aligned, except that the PPC is not available.

2. No transients are in progress.

3. Reactor water level, power, and pressure are stable.

4. Feed pump discharge pressure is 1300 psig for all three loops.

5. The Reactor Operator has just completed performing a manual reactor heat balance IAW procedure 1001.6, Core heat Balance and Feedwater Flow Calculation - Power Range. Feedwater flow was determined using Method 1.

Task Cue:

Perform a review/approval of the completed procedure.

NRC Admin SR05 Page 5 of 5