ML083110428

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Final - Section a Operating Exam (Folder 3)
ML083110428
Person / Time
Site: Nine Mile Point 
Issue date: 09/22/2008
From:
Constellation Energy Group
To: D'Antonio J
Operations Branch I
Hansell S
Shared Package
ML082520049 List:
References
TAC U01778
Download: ML083110428 (75)
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Text

Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Determine Personnel Overtime Availability IAW GAP-FFD-02 Revision: NRC 2008 Task Number: N/A Approvals.

Af

/ Y h J L F Gene61 Subervisdr Date OperationsTraining (Designee)

N/A - Exam Security I

General Supervisor Date Operations (Designee)

N/A - Exam Security

/

Configuration Control Date Performer:

(RO/SRO)

TrainedEvaluator:

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time: 30 minutes Time Critical Task:

No Alternate Path Task: No Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature:

Date:

NRC 2008 ADMIN JPM COO1 October 2008

Recommended Start Location: Classroom Simulator Set-up: None Directions to the Instructor/Evaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function a:: the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cuesasnecessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability tlo perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as Pass/Fail.
2. During Evaluated JPM:

0

3. During Training JPM:

0 0

Self verification shall be demonstrated.

Self verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. GAP-FFD-02 Tools and Equipment:
1. Calculator NRC 2008 ADMIN JPM COO1 October 2008

Task Standard:

Determine Personnel Availability for Overtime IAW GAP-FFD-02.

Initial Conditions:

1. The plant is shutdown.
2. In order to support critical path work required for startup, personnel overtime will be required for the night shift on October 26 from 1830-0630.
3. All the overtime hours will be spent performing (ROs) or supervising (SROs) field activities.

initiating Cues:

1.
2.
3.

From the provided list of personnel working hours, determine who is eligible to work a complete 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of overtime beginning at 1830 on October 26 without requiring an Overtime Deviation Request IAW GAP-F FD-02.

If an Overtime Deviation Request would be required for individual(s), state the work hour limit(s) which would be exceeded IAW GAP-FFD-02.

SROs ONLY - Complete Parts 1 and 2.A of an Overtime Deviation Request Form for all individuals who would need a deviation approved to cover the shift.

EXAMINER NOTE:

FOR ROs - Provide Attachments A & C.

FOR SROs - Provide Attachments A, B & D, and Blank Overtime Deviation Request Form.

Performance Steps Standard Grade

1.

Provide repeat back of initiating cue.

Piroper communications used for repeat Sat/Unsat Evaluator Acknowledge repeat back providing correction if necessary.

back (GAP-OPS-Ol/Operations Manual)

RECORD START TIME

2.

Obtain a copy of the reference procedure GAP-FFD-02 obtained and reviewhtilize the correct section of the procedure.

Sat/Unsat NRC 2008 ADMlN JPM COO1

- 3.-

October 2008

3. FOR ROs - Reviews work hours for Reactor Operators 1 thru 3 ROs - Determines the followinq:

PasdFail R. 0 #I - Eligible RO #2 - Not Eligible -would exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 day period RO #3 - Not Eligible -would exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period FOR SROs - Reviews work hours for Reactor Operators 1 thru 3 and Senior Reactor Operators 1 and 2 SROs - Determines the above limitations d u s the followinq:

SRO #I - Eligible SRO #2 - Not Eligible - would exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period

4.

Deviation Request Form FOR SROs - Completes Overtime Completes Columns 1 and 2 of Part 1 of GAP-FFD-02 Attachment 1, per attached key C'ompletes Columns 3 and 4 of Part 1 of GAP-FFD-02 Attachment 1, per attached key SaVUnsat Pass/Fail SatlUnsat Clompletes Part 2.A of GAP-FFD-02, per attached key TERMINATING CUE: JPM Attachment D and GAP-FFD-02 Attachment 1 completed RECORD STOP TIME NRC 2008 ADMIN JPM COO1

- 4.-

October 2008

ATTACHMENT A - ROS 1011 9 10120 10121 10122 10123 10124 1830-0642 1830-0642 1830-0730 1830-0542 1830-0642 (includes 12 (includes 12 (includes 60 (includes 12 (includes 12 minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time) 10125 10126 10127 1830-0706 OFF (includes 36 minutes of turnover time)

RO #2 10/19 10120 1 012 1 1 0122 I

I I

I 10123 10124 1 0125 10126 10127 I

I I

I OFF OFF (includes 12 (Includes 0 (includes 12 ' (includes 24 (includes 12 (includes 12 minutes of minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time) turnover time)

NRC 2008 ADMIN JPM COO1 RO #3 1011 9 10120 1 012 1 10122 I

I I

10123 10124 1 0125 1 0126 1 0127 October 2008 1830-0642 (includes 12 minutes of turnover time) 1830-0630 1830-0648 1830-0642 1830-0642 1830-0742 OFF (includes 0 (includes 18 (includes 12 (includes 12 (includes 12 minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time)

ATTACHMENT B - SROS 1012 1 OFF 1011 9 1830-0642 (includes 12 minutes of turnover time) 1 0122 10123 1830-0735 (includes 65 minutes OFF of turnover time) 10120 1830-0642 (includes 12 minutes of turn over time) 10122 1830-0642 1 0123 10124 0630-1 830 10124 (includes 12 minutes of turn over time) 1830-0642 1 0125 (includes 50 minutes of turnover time) 1830-0720 10126 OFF 10127 OFF 1011 9 1830-0642 (includes 12 minutes of turnover time) 10120 1830-0630 (includes 0 minutes of turnover time) 1 012 1 1830-0648 (includes 18 minutes of turnover time) 10125 OFF 10126 0500-1 200 finc!g&s 0 minutes of turnover time) 1 0127 OFF NRC 2008 ADMIN JPM COO1 October 2008

ATTACHMENT C - RO Answer Sheet RO #I RO #2 RO #3 Eligible to work without an Overtime Deviation Request?

(Yes/No)

If No, what work hour limit(

would be exceeded IAW Gf FFD-02?

NRC 2008 ADMIN JPM COO1 October 2008

ATTACHMENT D - SRO Answer Sheet I

RO #I RO #2 RO #3 SRO #I SRO #2 Eligible to work without an Overtime Deviation Request?

(Yes/No)

If No, what work hour limit1 would be exceeded IAW GI FFD-02?

NRC 2008 ADMlN JPM COO1 October 2008

Initial Conditions:

1. The plant is shutdown.
2. In order to support critical path work required for startup, personnel overtime
3. All the overtime hours will be spent performing (ROs) or supervising (SROs) will be required for the night shift on October 26 from 1830-0630.

field activities.

Initiating Cues:

1. From the provided list of personnel working hours, determine who is eligible to work a complete 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of overtime beginning at 1830 on October 26 without requiring an Overtime Deviation Request IAW GAP-FFD-02.
2. If an Overtime Deviation Request would be required for individual(s), state the work hour limit(s) which would be exceeded IAW GAP-FFD-02.
3. SROs ONLY - Complete Parts 1 and 2.A of an Overtime Deviation Request Form for all individuals who would need a deviation approved to cover the shift.

NRC 2008 ADMIN JPM COO1

- $1 -

October 2008

"ts

<'A x. t,'

'f A'1'I'A~'HNIE:NT C -- KO Answer Sheet Eligible to work without an Overtime Deviation Request?

KO #1 KO #2 KO #3 NIIC' 2008 ADMIN JPM COO2 If No, what work hour limit(s) would be exceeded IAW CAP-FFD-02?

October 2008

i-ATTACHMENT D -. SkO Answer Sheet I

KO #l 110 #2 I

RO #3 SKO #2 Eligible to work without an Overtime Deviation Request (Y esiNo)

.I/';

If No, what work hour limit(s) would be exceeded IAW GAP-FFII-02 ? -_I___

N l i C 2008 AI)MlN JI'M COO2 Octobcr 2008

CONTROL OF WORKING HOURS GAP-FFD-0%

Revision 01 700, OVERTIME DEVIATION REQUEST Page 1 of 1 I

OVERTIME DEVIATION REQUEST i

PART 1 - TYPE OF OVERTIME DEVIATION 1 More than 16 consecutive hours 7 More than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penod 3 More than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period 4 More than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> tin a 7 day period 5 Less than 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> break between work penods Name of Personnel (List Names Individually)

~.

7 "

s-A. Reason for Deviation

8. Method to monitor employee physicallmental fitness r

-1 kna_ger (Prinffsignature)

IDate 1

Note: Ensure deviation is approved by the Plant General Manager before scheduling overtime.

'Upon signing, the Supervisor has verified :I) that no cine will work greater than 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />, exclusive of turnover time, in a 7-day period. AND 2) that personnel will be periodically monitored to assess their fitness for duty, and to take action as appropriate, to ensure worker fatigue does not jeopardize nuclear or personnel safety.

PART 3 - Additional Actions I --____-

.I

[Plant General Manager Approval

]Date Approved Overtime Deviation request forms to be retained in the Plant General Manager's Ofice in accordance Wlth NIP-RMG-01.

1 P

f I:

  • bJ

Nine Mile Point Nuclear Station Stat ion Administrative Proced ure GAP-FFD-02 CONTROL OF WORKING HOURS Revision 01 700 50.59 Review Tech Spec.

INFORMATION USE Applicable To:

[x1 Nine Mile Point Nuclear Station, Units 1 and 2 Sponsor: Director-Licensing (NMP)

Approval Authority: Pliant General Manager

CONTROL OF WORKiNG HOURS GAP-FFD.42 Revision 01 700 Page 2 of 10

SUMMARY

OF ALTERATIONS Revision Change Summary of Revision or Change 01 7 00 Reworded Section 5.3.A Section 7: Added guidance for retention of monthly overtime reports.

--, i CONTROL OF WORKING HOURS GAP -FFD?Q%,

Revision 01700 Page 3 of 10 TABLEOFCONTENTS SECTION TITLE PAGE

CONTROL OF'WORKING HOURS

+

GAP.FFD.Qs.

Revision 01700 Page 3 of 10 I TABLE OF CONTENTS SECTION TITLE PAGE 1. 0 2.0 3.0 4.0 5.0 6.0

7.0 INTRODUCTION

4 1. 1 Purpose........................................................................................................................

4 1.2 Scope/Applicability:.......................................................................................................

4 REFERENCES.............................................................................................................................. 4 2.1 Developmental References..........................................................................................

4 2.2 Performance References..............................................................................................

4 DEFINITIONS...............................................................................................................................

4 RESPONSIBILITIES.....................................................................................................................

5 PROCESS..................................................................................................................................... 5 5.1 Work Hour Limits..........................................................................................................

5 5.2 Exceeding Work Hour Limits........................................................................................

6 5.3 Review of Overtime Worked I Independent Review.....................................................

9 BASES..........................................................................................................................................

9 RECORDS....................................................................................................................................

9. OVERTIME DEVIATION REQUEST...............................................................................

10

CQNTROL OF WORKING HOURS GAP-FFD,-,OZ I Revision 01700 1.O INTRODUCTION 1.1 Purpose A.

To establish administrative controls necessary for the implementation of technical specification requirements on individual working hours.

B.

To ensure Station Personnel are physically/mentally fit for duty to perform job duties during extended working hour periods.

I

.2 ScopelApplicability:

A.

The work hour limits specified in Section 5.1.6 of this procedure apply to all station and non-station personnel working at NMP.

B.

The documentation requirements of Section 5.2.E apply only to personnel who perform or directly supervise those who perform safety-related functions, specially:

Licensed senior reactor operators, reactor operators, and non-licensed operators.

Chemistry, Radiation Protectiim, and Reactor Analyst Technicians.

e Key Maintenance personnel as defined in Section 3.6.

Personnel who perform inspections, examinations, or tests on safety-related Structures, Systems or Components. [NO031

2.0 REFERENCES

2.1 Developmental References A.

Unit 1 Technical Specifications, Section 6.2.2, Unit Staff B.

C.

Unit 2 Technical Specifications, Section 5.2.2, Unit Staff Unit 2 USAR, Section 1.I

.O, Position on NUREG-0737 - I.A.1.3, Shift Manning 2.2 Performance References None 3.0 DEFINITIONS A.

7 Day Period A seven calendar day rolling period beginning at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on the first day and ending at 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on the seventh day. [ NO021

CONTROL: QF.WORKING HOURS

r.

GAP-FFD-02 3

Revision 01700 Page 5 of 10 3.0 (Continued)

B.

Key Maintenance Personnel Those personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of safety-related structures, systems, and components, and those personnel who are performing or immediately supervising the performance of such activities (reference GL 83-14).

4.0 RESPONSIBILITIES The following individuals and organizations are assigned responsibilities within this procedure:

A.

Plant General Manager

8.

Manager s/Directors C.

General Supervisors/Supervisors D.

5.0 PROCESS 5.1 Work Hour Limits Individuals who work in excess of the limitations stated in Section 5.1 of this procedure NOTE Work hour limits are established to ensure that individuals performing activities that directly impact personnel safety and the safe and reliable operation of the plant are not overly fatigued such that their mental alertness and decision-making ability might be impaired.

A.

ManagerdDirectors shall ensure adequate shift coverage is maintained without routine heavy use of overtime. The objective shall be to have operati ng personnel work a normal 8-12 hour day, nominal 40-hour week while the facility is operating.

B.

However, when circumstances dictate working beyond scheduled working hours, the following limitations apply:

CONTROL OF WORKING HOURS GAP-FFD-02 Revision 01 700 5.1 (Continued)

NOTE For criteria in Section 5.1.B.1 below, turnover time should NOT be included. Turnover time of greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for any individual tour of duty is not exempted from individual overtime hours.

The below periods are consecutive rolling periods and are not based on calendar work weeks.

1.

Individuals identified in Section 1.2 should not be permitted to work more than:

a.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight

b.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period

c.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period

d.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period

2.

Work in excess of these limits shall NOT be routinely authorized.

C.

There should be a break in an individual's work schedule of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following a work period for which work goes beyond the limitations in Step 5.1.B.

D.

The requirements and limits specified in Steps 5.1.B and 5.1.C apply to all hours worked if any portion of an individual's total work time is spent performing or supervising field activities.

E.

Individuals working a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift schedule, who, as a result of transition in and out of daylight savings time, will exceed the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period guideline, are authorized to deviate from the guideliine for the one hour transition period. No Overtime Deviation Request is required to be completed for this deviation.

5.2 Exceeding Work Hour Limits A.

It is recognized that deviations from the "Work Hour Limits" may occasionally occur. The use of overtime should be limited to circumstances where essential work must be done on an accelerated schedule and, except during extended shutdown periods, should be considered on an individual basis and not for the entire staff on a shift.

CONTiROL OF WORKING HOURS 5.2 (Continued)

B.

Circumstances that may warrant deviating from the guidelines of Section 5.1 include, but are not limited to:

0 To respond to a Limiting Condition for Operation (LCO).

e To complete a work activity where it is safer to complete than to secure.

e To complete work affecting critical path during a shutdown.

e To complete work on a problem immediately affecting nuclear or industrial safety.

e Absenteeism, e

Weather-related extension of work periods.

C.

All paid overtime should be approved by authorized supervision before the overtime is worked.

D.

The following are the requirements applicable to personnel who do NOT perform or directly supervise those who perform safety-related functions. Refer to Section 5.2.E for additional guidance.

1.

Personnel shall track their work hours and notify their supervisors if they expect to reach the limits of Section 5.1.

2.

Prior to exceeding any of the work hour limits in Section 5.1, personnel shall obtain verbal approval from their Supervisor, General Supervisor, Director, or Manager. Approval shall be given only if the following conditions are met:

0 The work activity is necessary to support safe and reliable operation of the plant.

AND e

Other personnel cannot reasonably be m ade available to perform the work activity.

3.

Personnel shall generate a Condition Report if work hour limits were exceeded without obtaining prior approval.

4.

Supervisors shall:

a.

Ensure personnel are fit for duty at all times.

b.

Make more frequent direct observations of personnel exceeding work hour limits.

CONTROLOF WORKING HOURS GAP-FFD-OB Revision 01700 Page 9 of 10 5.2 (Continued)

4.

Completed Attachment 1s shall be forwarded to the Administrative Assistant to the Plant General Manager.

5.3 Review of Overtime Worked I Independent Review A.

The Director of Human Resources (HR) shall ensure that overtime is reviewed on a monthly basis. The scope of monthly review shall include personnel identified in Section 1.2.8 of this procedure to assure excessive hours have not been worked. It will be documented in a monthly report and supplied to the Plant General Manager.

8.

If the review determines that excessive hours of overtime have been assigned then a Condition Report shall be initiated.

6.0 BASES

[NO011

[NO021

[NO031

[NO041 NCTS 503524-10, NM PC will review all departments methods of overtime control and tracking.

DER C-95-3190 Provide definition for 7-day period.

DER C-91-Q-0464 Ensure overtime controls are applicable to personnel who perform safety-related functions (including contractors) as expressed in NRC Information Notice 91-36.

DER NM-2001-1737 Apparent reliance on the excessive use of overtime deviations to complete RF016.

7.0 RECORDS Completed Attachment ls, Overtime Deviation Request, shall be retained by the Administrative Assistant to the Plant General Manager for one year and then may be discarded.

Completed monthly independent Over time Report shall be maintained by the Hum an Resources Department for one year and then may be discarded.

LAST PAGE

CQNTROL OF WORKING HOURS Name of Personnel (List Names Individually)

\\.: i

~ - '

GAP-FFD-02 1 i Revision 01700 TIME PERIOD OF DEVIATION TYPE OF OVERTIME DEV. (1-5) FROM (DATERIME) To (DATE~IME)

Page 1 of 1, OVERTIME DEVIATION REQUEST 1

OVERTIME DEVIATION REQUEST PART 1 - TYPE OF OVERTIME DEVIATION PART 2 -

A. Reason for Deviation I

.I

6. Method to monitor employee physicallmental fitness I

I-

---I Supervisor (Print/Signature)*

IDate Note. Ensure deviation is approved by the Plant General Manager before scheduling overtime.

(PrinffSignature)

(Date

  • Upon signing, the Supervisor has verified :I) that no one will work greater than 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />, exclusive of turnover time, in a 7-day period. AND 2) that personnel will be periodically monitored to assess their fitness for duty, and to take action as appropriate, to ensure worker fatigue does not jeopardize nuclear or personnel safety.

PART 3 - Additional Actions Plant General ManaQer Approval

[Date Approved Overtime Deviation request forms to be retained in the Plant General Manager's Office in accordance with NIP-RMG-01,

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE

Title:

Assess Reportability Requirements Revision: NRC 2008 Task Number: NA Approvals:

NA EXAMINATION SECURITY General Supervisor Date Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer:

- (SRO)

Trainer/Evaluator:

Evaluation Method:

X Perform Simulate Evaluation Location:

Plant X

Simulator or other location Expected Completion Time: 25 min Time Critical Task:

NO Alternate Path Task: NO Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Date:

NMP2 NRC SRO ADMlN JPM COO2 1

October 2008

Recommended Start Location: (Completion time based on the start location)

Simulator or other designated area Simulator Set-up:

N/A Directions to the Instructor/Evaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equiprnent will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Tralnlng JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a ".".
2. During Evaluated JPM:

0

3. During Training JPM:

0 0

Self checking shall be demonstrated.

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. CNG-NL-1.01-1004
2. 10CFR50.72
3. NUREG 1022 Rev 2, Section 3.2.6
4. EAL Matrix Tools and Equipment:
1. None Task Standard:

Determine notification requirements.

NMP2 NRC SRO ADMIN JPM C0102 2

October 2008

Initial Conditions:

e.

e..

e...

The plant is operating at 100% power.

Containment purge is in progress Maintenance is using an approved work order to perform a maintenance activity on containment purge isolation logic Work order identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short.

While the work order is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs. No other systems are affected.

After conditions are stabilized, Drywell Floalr Drain leakage rate rises to 10 gpm.

Drywell pressure stabilizes below the scram setpoint but the leakage has remained at 10 gpm for the past 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> despite leakage reduction attempts.

Actions to comply with Tech Specs as a result of the leakage are initiated and N2-OP-IOlC, Plant Shutdown is being implemented.

Reactor power is now at 50%.

Drywell Floor Drain leak rate is at Igpm anld Tech Spec LCO is exited.

After conditions are stabilized, a spurious h4SIV isolation occurs and the reactor automatically scrams All rods fully insert SRVs and RClC are controlling reactor prelssure Feedwater is controlling RPV level which is being maintained 160 to 200 inches.

Plant conditions are stabilized and a normal cool down occurs.

Initiating cue:

(Operators name), identify ALL the applicable verbal notification requirements, the reason that they apply and the associated time limitations for reporting under that category.

1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME 2

.Obtain a copy of the any of the 0

Reference materials obtained.

reference documents related to regulatory notifications. These are likely to include the following:

NIP-IRG-01 0

1 OCFR50.72 and 73 0

NUREG1022 0 EAL Matrix Note: Invalid isolation during maintenance is illustrated in NUREG 1022, Rev 2, section 3.2.6 System Actuation on page 52, example 7.

NMP2 NRC SRO ADMIN JPM COO2 3

October 2008

50.72 (b)(3)(iv)(A); also references 50.72 (b)(3)(iv)(B)(2).

LER is not a verbal reporting 0

requirement.

Locate and identify applicability of 50.72(a)( 1 )(i). Declaration of an Emergency Class.

Locate and identify applicability of 50.72(b)(2)(i). Non-emergency four hour report. Initiation of a plant shutdown required by Tech Specs. (If not already reported with the 50.72(a)(l)(i).

0 Locate and identify applicability of 0

50.72(b)(2)( iv)( B) Non-emergency four hour report.

Actuation of RPS when the reactor is critical.

Locate and identify applicability of 50.72( b)(3)(iv)(A)( iv)( B)(2) Non-emergency eight hour report.

Actuation logic is not reportable under 50.72 (b)(3)(iv)(B)(2) because the actuation is not due to a valid signal.

LER if; required under 50.73 (b)(2)(:iv). Identification of this requirement is not required.

Identifies leak rate above 10 gpm requires EAL 2.1.I UNUSUAL EVENT must be declared.

Identify reportability per 50.72(a)( 1 )(i) and (a)(3), within 15 minutes of declaration, immediately after notifying State and local agencies and not later than one hour after the time of: declaration.

Refer 1.0 Tech Spec 3.4.5.C. and determines that with specification not being met, the required action to comply with Tech Spec is to be cold shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The plant shutdown being performed is required by Tech Specs.

Identify reportability per 50.72(b)(

2)(i) within four hours, if not already reported.

Identify reportability per 50.72(b)(2)(iv)(B) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if not already reported.

Identify reportability per 50.72@)(3)(iv)(A)(iv)(B)(2).

within El hours, if not already reported.

End of JPM TERMINATING CUE: Determine notification requirements.

RECORD STOP TIME Sat/Unsat/NA PasslFail SaUUnsat PasslFail PasslFail PasslFail NMP2 NRC SRO ADMIN JPM COO2 4

October 2008

Applicant Cue Sheet Initial Conditions:

The plant is operating at 100% power.

Containment purge is in progress Maintenance is using an approved work order to perform a maintenance activity on containment purge isolation logic Work order identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short.

While the work order is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs. No other systems are affected.

After conditions are stabilized, Drywell Floor Drain leakage rate rises to 10 gpm.

Drywell pressure stabilizes below the scram setpoint but the leakage has remained at I O gpm for the past 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> despite leakage reduction attempts.

Actions to comply with Tech Specs as n result of the leakage are initiated and N2-OP-101 C, Plant Shutdown is being implemented.

Reactor power is now at 50%.

Drywell Floor Drain leak rate is at Igprri and Tech Spec LCO is exited.

After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams All rods fully insert SRVs and RClC are controlling reactor pressure Feedwater is controlling RPV level which is being maintained 160 to 200 inches.

Plant conditions are stabilized and a normal cool down occurs.

Initiating cue:

(Operators name), identify ALL the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category.

NMP2 NRC SRO ADMIN JPM COO2 5

October 2008

At t a c hi men t 1 JPM Scorecard KEY Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category I

Re porta bil i ty Reau irement 50.72 (b)(3)(iv)(A) also references 50.72 (b)(3)(iv)( B)(2). General containment isolation signals.

50.72(a)(l)(i) and (a)(3).

Declaration of an Emergency Class 50.72(b)(2)(i). Initiation of a plant shutdown required by Tech Specs 50.72( b)(2)( iv)( B).

Actuation of RPS when the reactor is critical.

50.72( b)(3)(iv)(A)( iv)(B)(2).

Time Limi,t NOT REPOR 'ABLE Within 15 rriinutes of declaration, immediately after notifying state and local agenciies and not later than one hour after the time of declaration Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if not previously reported.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if not previously reported.

Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, if not previously reported.

Reason (Event) Category Applies Containment Purge Isolation during maintenance activity. Also, only affects one system.

Declaration of UE 2.1. I Initiation of a plant shutdown required by Tech Specs 3.4.5.C Unidentified leakage is above 5 gpm for >4 hours.

Automatic reactor trip when the reactor is critical.

MSlV Isolation NMP2 NRC SRO ADMlN JPM COO2 6

October 2008

At t a c t-I men t 2 JPM Scorecard For Applicant Use Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability Rea u i rement Time Limit Reason (Event) Category ADDlies NMP2 NRC SRO ADMIN JPM COO2 7

October 2008

I U LCK ~ u.

/ L immeuiaie notiiicaiion requirernenrs lor operating nuclear power reactors.

rage I 0 1 2 j

50.72 Immediate notification requirements for operating nucl power reactors.

(a) General requirements.' (1) Each nuclear power reactor licensee licensed under §Ej 50.21(b) or 50.22 holdi operating license under this part or a combined license iunder part 52 of this chapter after the Commission in:

finding under Ej 52.103(g), shall notify the NRC Operations Center via the Emergency Notification System of:

(i) The declaration of any of the Emergency Classes specified in the licensee's approved Emergency Plan; 3r (ii) Those non-emergency events specified in paragraph (b) of this section that occurred within three years of discovery.

(2) If the Emergency Notification System is inoperative, the licensee shall make the required notifications via telephone service, other dedicated telephone system, or any other method which will ensure that a report is r as practical to the NRC Operations Center.3 (3) The licensee shall notify the NRC immediately after notification of the appropriate State or local agencies i than one hour after the time the licensee declares one of the Emergency Classes.

(4) The licensee shall activate the Emergency Response Data System (ERDS) as soon as possible but not lat hour after declaring an Emergency Class of alert, site area emergency, or general emergency. The ERDS may activated by the licensee during emergency drills or exercises if the licensee's computer system has the capat transmit the exercise data.

(5) When making a report under paragraph (a)(l) of this section, the licensee shall identify:

(i) The Emergency Class declared; or (ii) Paragraph (b)(l), ' ' One-hour reports," paragraph (b)(2), ' ' Four-hour reports," or paragraph (b)(3), ' ' f reports," as the paragraph of this section requiring notification of the non-emergency event.

(b) Non-emergency events--( 1) One-hour reports. I f not reported as a declaration of an Emergency Class unc (a) of this section, the licensee shall notify the NRC as soon as practical and in all cases within one hour of thc of any deviation from the plant's Technical Specifications authorized pursuant to Sec. 50.54(x) of this part.

(2) Four-hour reports. If not reported under paragraphs (a) or (b)(l) of this section, the licensee shall notify 1 soon as practical and in all cases, within four hours of the occurrence of any of the following:

(i) The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.

(ii)-(iii) [Reserved]

(iv)(A) Any event that results or should have resulted in emergency core cooling system (ECCS) discharge int coolant system as a result of a valid signal except when the actuation results from and is part of a pre-planne during testing or reactor operation.

(B) Any event or condition that results in actuation of thle reactor protection system (RPS) when the reactor i!:

except when the actuation results from and is part of a pre-planned sequence during testing or reactor opera1 (v)-(x) [Reserved]

(xi) Any event or situation, related to the health and safety of the public or onsite personnel, or protection of environment, for which a news release is planned or notification to other government agencies has been or w Such an event may include an onsite fatality or inadvertent release of radioactively contaminated materials.

http://www.nrc.gov/r~ading-rm/doc-col1ections/cfr/pa1~050/pa~050-0072.htm1 9/2 5/2OO8

(3) Eight-hour reports. If not reported under paragraphs (a), (b)(l) or (b)(2) of this section, the licensee shal NRC as soon as practical and in all cases within eight hours of the occurrence of any of the following:

(i) [Reserved]

(ii) Any event or condition that results in:

(A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded; (B) The nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.

(iii) [Reserved]

(iv)(A) Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(:r)(i section, except when the actuation results from and is part of a pre-planned sequence during testing or reach (B) The systems to which the requirements of paragraph (b)(3)(iv)(A) of this section apply are (1) Reactor protection system (RPS) including: Reactor scram and reactor trip.

(2) General containment isolation signals affecting containment isolation valves in more than one system or n steam isolation valves (MSIVs).

(3) Emergency core cooling systems (ECCS) for pressurized water reactors (PWRs) including: High-head, inte head, and low-head injection systems and the low pressure injection function of residual (decay) heat removc (4) ECCS for boiling water reactors (BWRs) including: High-pressure and low-pressure core spray systems; hi coolant injection system; low pressure injection functiorn of the residual heat removal system.

(5) BWR reactor core isolation cooling system; isolation condenser system; and feedwater coolant injection s)

(6) PWR auxiliary or emergency feedwater system.

(7) Containment heat removal and depressurization systems, including containment spray and fan cooler syst (8) Emergency ac electrical power systems, including: E3mergency diesel generators (EDGs); hydroelectric fac lieu of EDGs at the Oconee Station; and BWR dedicated Division 3 EDGs.

(v) Any event or condition that at the time of discovery could have prevented the fulfillment of the safety fun(

structures or systems that are needed to:

(A) Shut down the reactor and maintain it in a safe shutdown condition; (B) Remove residual heat; (C) Control the release of radioactive material; or (0) Mitigate the consequences of an accident.

(vi) Events covered in paragraph (b)(3)(v) of this sectio'n may include one or more procedural errors, equipm and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies. However, indi, component failures need not be reported pursuant to paragraph (b)(3)(v) of this section if redundant equipmc same system was operable and available to perform the required safety function.

(vii)-(xi) [Reserved]

912 512 00 8

(xii) Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for (xiii) Any event that results in a major loss of emergency assessment capability, offsite response capability, o communications capability (e.g., significant portion of control room indication, Emergency Notification System notification system).

(c) Followup notification. With respect to the telephone notifications made under paragraphs (a) and (b) of th addition to making the required initial notification, each licensee, shall during the course of the event:

(1) Immediately report (i) any further degradation in the level of safety of the plant or other worsening plant including those that require the declaration of any of the Emergency Classes, if such a declaration has not bee made, or (ii) any change from one Emergency Class to,another, or (iii) a termination of the Emergency Class.

(2) Immediately report (i) the results of ensuing evaluations or assessments of plant conditions, (ii) the effeci response or protective measures taken, and (iii) information related to plant behavior that is not understood.

(3) Maintain an open, continuous communication channel with the NRC Operations Center upon request by th

[48 FR 39046, Aug. 29, 1983; 48 FR 40882, Sept. 12, 1.983; 55 FR 29194, July 18, 1990, as amended at 55 I 10, 1991; 56 FR 23473, May 21, 1991; 56 FR 40184, AIJ~. 13, 1991; 57 FR 41381, Sept. 10, 1992; 58 FR 67 1993; 59 FR 14087, Mar. 25, 1994; 65 FR 63786, Oct. 25, 2000; 72 FR 49502, Aug. 28, 20071

1. Other requirements for immediate notification of the NRC by licensed operating nuclear power rectors are c elsewhere in this chapter, in particular Secs. 20.1906, 20.2202, 50.36, 72.216, and 73.71.
2. These Emergency Classes are addressed in Appendix E of this part.
3. Commercial telephone number of the NRC Operations Center is (301) 816-5100.
4. Requirements for ERDS are addressed in Appendix E,Section VI.
5. Actuation of the RPS when the reactor is critical is reportable under paragraph (b)(2)(iv)(B) of this section.

http://www.nrc.gov/reading-rm/doc-collections/cfr/partO5 O/part050-0072.html 912 51200 8

multiple svstems.

(6) Manual Actuation efEfFComponent in Response to Actual Plant Condition At a PWR, maintenance personnel inadvertently pulled an instrument line out of a compression fitting connection at a pressure transmitter. The resultant reactor coolant system (RCS) leak was estimated at between 70 and 80 g.p.m. Charging flow increased due to automatic control system action. The operations staff recognized the symptoms of an RCS leak and entered the appropriate off-normal procedure. The procedure directed the operations staff to start a second charging plump and flow was manually increased to raise pressurizer level. Based on the response of the pressurizer level, the operations staff determined that a reactor scram and safety injection were not necessary. Maintenance personnel still at the transmitter closed the instrument block and root valves terminating the event.

The staff considers the manual start of the charging pump (which also serves as an ECCS pump, but with a different valve lineup) in response to dropping pressurizer level to be an intentional manual actuation e f a f f f f F i n response to equipment failure or human error and reportable because it constitutes deliberate manual actuation of a single componentdaft

ffF, in response to plant conditions, to mitigate the consequences of an event.+

3 A

s discussed previouslv in this section, actuations that need not be reported are those that are initiated for reasons other than to mitigate the consequences of an event (e.g., at the discretion of the licensee as part of a planned procedure or evolution).

(7) ffFActuation Durina Maintenance Activitv At a BWR, a maintenance activity was under way involving placement of a jumper to avoid-unintended actuations. The maintenance staff recognized that there was a high potential for a loss of contact with the jumper and consequent fff.actuation. This potential was explicitly stated in the maintenance work request and on a risk evaluation sheet. The operating staff was briefed on the potential Eif-actuations prior to start of work. During the event, a loss of continuity did occur and the ffFactuations occurred, involving isolation, standby gas treatment start, closing of some valves in the primary containment isolation system (recirculation pump seal mini-purge valve, nitrogen supply to drywell valve, and containment atmospheric monitoring valve)-.

The event is not reportable under 5 50.72(b)(2)(iv) or (bM3Miv) because the actuations were not valid. It is reportable under 5 50.73(a)(2)('iv) because the actuations were not listed as land were not) definitely expected to occur.

3.2.7 Event or Condition That Could Have Prevented Fulfillment of a Safety Function

§ 50*73(a)(2)(v)

"Any event or condition that &at the "Any event or condition that ateffecould have prevented the fulfillment of the safety function of structures or systems that are NUREG-1022, Rev. 2 52

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE

Title:

Offsite Dose Calculation Manual (ODCM) Asslessment Revision: NRC 2008 for Inoperable Equipment Task Number:

Approvaly7 NA EXAMINATION SECURITY Date General Supervisor Date Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer:

(SRO)

Trainer/Evaluator:

Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time: 15 minutes Time Critical Task: NO Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail Alternate Path Task: NO NOTE: A JPM overall rating of fail shall be given if a ~ !

critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature:

Date:

NMP2 2008 Retake NRC SRO ADMIN JPM EC Rev 9-1 7-08 1

October 2008

Recommended Start Location: (Completion time based on the start location)

Simulator or other designated location Simulator Set-up:

N/A Directions to the InstructorlEvaluator To be performed as an administrative JPM with two parts (Part A and Part 6)

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SSS, CSO, and Auxiliary Operators.

Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional /

concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

Therefore, either another individual or I will act as the additional / concurrent verifier.

Notes to Instructor / Evaluator:

1.
2.

During Evaluated JPM:

3.

During Training JPM:

Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by a o.

0 Self-verification shall be demonstrated.

Self-verification shall be demonstrated.

No other verification shall be demonstrated.

References :

1. N2-OP-42, Offgas System.
2. ODCM D.3.3.2, Radioactive Gaseous Effluent Monitoring Instrumentation.
3. K/A 2.3.1 1, Ability to control radiation releases (3.2).

Tools and Equipment:

1. None Task Standard:

Determines that periodic OFG effluent grab samples and analyses are required per the ODCM and the time limits for the first and second grab samples.

NMP2 2008 Retake NRC SRO ADMlN JPM EC Rev 9-17-08 2

October 2008

Initial Conditions:

1. Reactor power is 45% with power ascension in progress.
2. Both OFG*RE13A and OFG*RE13B were previously OPERABLE and in-service
3. Both OFG*13A and OFG*13B indications have just failed downscale.
4. Sample flow is available.
5. Troubleshooting has not yet commenced.
6. Ask the operator for any questions.
1. Provide repeat back of initiating cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary Proper communications used for repeat RECORD START TIME PART A
1..Obtain a copy of the reference u

procedure and reviewhtilize the correct section.

2..Reference CONDITION B 0

0 0

ODCM obtained. Section D.3.3.2 and Bases B 3.3.2 are referenced.

Determines that the inoperable OFG Radiation Monitors must be restored to OPERABLE status within 30 days.

Refers to Table 3.3.2-1 Determines that CONDITION C is applicable Sat/Unsat -

Sat/Unsat Sat/Unsat Sat/ Unsat Sat/Unsat NMP2 2008 Retake NRC SRO ADMlN JPM EC Rev 9-1 7-08 3

October 2008

3..Reference CONDITION C EXAMINER NOTE: If Candidate implements REQUIRED ACTION C.l, OFG will isolate.

In order to continue the JPM (part B),

inform the candidate that instead of Action C.1, the other Actions were implemented for sampling. Then provide the applicant with the Part B Initial Condition information sheet.

o Action C.l - place channels in trip condition Determines that tripping both channels of OFG*RE13A and B would isolate OFG.

OR o Action C.2.1 Determines that OFG grab samples must be taken within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

0 Actinn c.2.2 Determines that the samples must be analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sample completion.

Part B EVALUATOR: When the candidate determines the ODCM sample requirements, provide the candidate with the attached PART B Initial Conditions and Initiating Cues Information Sheet.

Cue: Asked the candidate to determine when the first and second samples are due based upon a 06:OO time for the OFG*RI3A/B inoperabilities.

NMP2 2008 Retake NRC SRO ADMIN JPM EC Rev 9-1 7-08 Sat/ Unsat Pass/Fail PasslFail 4

October 2008

I Performance steps

] Standard

1.
2.
3.

Grade I Comments

.Obtain a copy of the applicable reference documents and review/

utilize the correct sections.

Pass/Fail

.Determines that Example 1.3-1 applies to the first 12 Hours 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> + a 25% extension of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> = 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />

  • Determines that Example 1.3-6 applies to the next AND once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

o Reviews ODCM Section 3.0, Applicability.

o Reviews Tech Spec Section 1.3, Completion Times.

First sample is due by 18:OO today o Second sample is due by 06:OO tomorrow, with an allowable extension of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as late as 09:OO)

Sat/Unsat Sat/Unsat PasslFail I I

End of JPM TERM IN AT! N G CUE :

Determines that periodic OFG effluent grab samples and analyses are required per the ODCM and the time limits for the first and second grab samples.

RECORD STOP TIME NMP2 2008 Retake NRC SRO ADMIN JPM EC Rev 9-17-08 5

October 2008

PART A Initial Conditions:

1. Reactor power is 45% with power ascension in progress.
2. Both OFG*RE13A and OFG*RE13B indications have failed downscale.
3. Sample flow is available.
4. Troubleshooting has not yet commenced.
5. Ask the operator for any questions.

Initiating cue:

(Operators name), Determine required actions.

NMP2 2008 Retake NRC SRO ADMIN JPM EC Rev 9-17-08 7

October 2008

PART B Initial Conditions and lnitiatinq Cue Information Sheet Initial Conditions:

1. OFG*REI 3 N B were declared non-functional at 06:OO today
2. Ask the operator for any questions.

Initiating cue:

(Operators name), determine the latest time that the first sample is due. Then based upon this time, determine the latest time the next sample can be taken.

NMP2 2008 Retake NRC SRO ADMIN JPM EC Rev 9-17-08 9

October 2008

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 CONDITION D 3.3 INSTRUMENTATION D 3.3.2 DLCO 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation The radioactive gaseous effluent monitoring instrumentation channels shown in Table D 3.3.2-1 shall be FUNCTIONAL with:

REQUIRED ACTION

a.
b.

The minimum FUNCTIONAL channel(s) in service.

The a l d t r i p set oints of Offgas Noble Gas Activity Monitor set to ensure that the f) imit of Technical Specification LCO 3.7.4 is not exceeded.

Effluent Nob Ip e Gas Activity Monitor and Main Stack Effluent Noble Gas Activity Monitor set to ensure that the limits of DLCO 3.2.1 are not exceeded.

c.

The a l d t r i setpoints of RadwasteReactor Building Vent A.

Gaseous effluent monitoring instrumentation channel aladtrip setpoint less conservative than required.

APPLICABILITY According to Table D 3.3.2-1.

A.l Suspend the release of radiloactive gaseous effluents monitored by the affected channel.

OK A.2 Declare the channel nonjhnctional.

ACTIONS A.3 Change the setpoint so it is acceptably conservative.

COMPLETION TIME Immediately Immediately Immediately (continued) 13.3-7 Unit 2 Revision 30 September 2007

ACTIONS (continued)

CONDITION B.

One or more channels nonfunctional.

C. As required by Required Action B. 1 and referenced in Table D 3.3.2-1.

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 REQUIRED ACTION B. 1 Enter the Condition referenced in Table D 3.3.2-1 for the channel.

AND B.2 Restore nonfunctional channel(s) to FUNCTIONAL status.

C.1 Place the nonfunctional channel in the tripped ccmdi tion.

C.2.1 Take grab samples.

C.2.2 Analyze samples for gross activity.

I 3.3-8 COMPLETION TIME Immediately 30 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from timie of sampling completion (continued)

Unit 2 Revision 30 September 2007

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 E. As required by Required Action B. 1 and referenced in Table D 3.3.2-1.

ACTIONS (continued) -1 E. 1 Continuously collect samples using auxiliary sampling equipment as required in Table D 3.2.1-1.

REQUIRED ACTION Estimate the flow rate for the nonfunctional channel(s).

CONDITION D. As required by Required Action B. 1 and referenced in Table D 3.3.2-1.

F. As required by Required Action B. 1 and referenced in Table D 3.3.2-1.

F. 1.1 Take grab samples.

AND F. 1.2 Analyze samples for gross activity with a radioactivity limit of detection of at least 1 x lo4 pCi/ml.

AND F.2.1 Restore the nonfunctional channel(s) to FUNCTIONAL status.

OR F.2.2 Through a CR, determine:

(1) The cause(s) of the nonfunctional.

(2) The actions to be taken and the schedule for restoring the system to FUNCTIONAL status.

COMPLETION rIME 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 3nce per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

hereafter 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 12 hours AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of sampling completion 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 14 days (continued)

I 3.3-9 Unit 2 Revision 30 September 2007

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE DSR 3.3.2.7 Perform CHANNEL CALIBRATION. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology IST) or using standards that have been obtained k? om suppliers that participate in measurement assurance activities with NIST, or usin actual on a system that has been calibrated with NIST traceable sources. These standards shall permit calibrating the system over. its intended ran e of CALIBRATIONy sources that have been related to the initial calibration may be used.

samples of gaseous effluents that have % een analyzed energy and measurement. For subsequent 8 HANNEL The CHANNEL CALIBR4TION shall also demonstrate that automatic: isolation of this pathway occurs when the instrument channels indicate measured levels above the Trip Setpoint.

DSR 3.3.2.8 Perform CHANNEL CALIBRATION.

DSR 3.3.2.9 Perform CHANNEL CALIBRATION. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology IST) or using standards that have been obtained E"

rom suppliers that participate in measurement assurance activities with NIST, or usin actual on a system that has been calibrated with NIST traceable sources. These standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.

samples of gaseous effluents that have % een analyzed

~~

DSR 3.3.2.10 Perform CHANNEL CALIBRATION.

FREQUENCY 24 months 18 months 18 months 24 months 13.3-12 Unit 2 Revision 30 September 2( I07

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 1 of 2)

Radioactive Gaseous Effluent lvionitoring Instrumentation REQUIRED CONDITIONS APPLICABILITY OR CHANNELS REFERENCED OTHER SPECIFIED PER.

FROM REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUMENT ACTION B. 1 REQUIREMENTS

1.

Offgas System

a.

Noble Gas (a)

Activity Monitor

- Providing Alarm and Automatic Termination of Release

b.

System Flow-(a)

Rate Measuring Device (a)

c.

Sample Flow-Rate Measuring Device 2

1 2

C D

D DSR 3.3.2.1 DSR 3.3.2.4 DSR 3.3.2.1 DSR 3.3.2.1 DSR 3.3.2.5 DSR 3.3.2.10 DSR 3.3.2.1 DSR 3.3.2.5 DSR 3.3.2.10

2.

RadwasteReactor Building Vent Effluent System

a.

Noble Gas (b) 1 F

DSR 3.3.2.1 DSR 3.3.2.3 Activity Monitor (c)

DSR 3.3.2.6 DSR 3.3.2.9

b.

Iodine Sampler (b) 1 E

DSR 3.3.2.2

c.

Particulate Sampler

d.

Flow-Rate Monitor 1

E DSR 3.3.2.2 (b)

(b) 1

e.

Sample Flow-(b)

Rate Monitor 1

D DSR 3.3.2. I DSR 3.3.2.5 DSR 3.3.2.8 D

DSR 3.3.2.1 DSR 3.3.2.5 DSR 3.3.2.8 (continued)

(a)

During offgas system operation.

(b) At all times.

(c)

Includes high range noble gas monitoring capability.

13.3-13 Unit 2 Revision 30 September 2007

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 Table D 3.3.2-1 (page 2 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation REQUIRED CONDITIONS APPLICABILITY OR CHANNELS REFERENCED OTHER SPECIFIED PER FROM REQUIRED SURVEILLANCE INSTRUMENT CONDITIONS INSTRUiMENT ACTION B. 1 REQUIREMENTS

3.

Main Stack Effluent

a.
b.

C.

d.
e.

Noble Gas Activity Monitor (c)

Iodine Sampler Particulate Sampler Flow-Rate Monitor Sample Flow-Rate Monitor DSR 3.3.2.1 DSR 3.3.2.3 DSR 3.3.2.6 DSR 3.3.2.9 DSR 3.3.2.2 DSR 3.3.2.2 DSR 3.3.2.1 DSR 3.3.2.5 DSR 3.3.2.8 DSR 3.3.2.1 DSR 3.3.2.5 DSR 3.3.2.8

~~

(b)

At all times (c)

Includes high range noble gas monitoring capability.

13.3-14 Unit 2 Revision 30 September 2007

Radioactive Gaseous Effluent Monitoring Instrumentation B 3.3.2 B 3.3 INSTRUMENTATION B 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The a l d t r i p setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Part I1 to ensure that the alarmhip will occur before exceeding the limits of 10 CFR 20. Although the Offgas System Noble Gas Activity Monitor is listed in Table D 3.3.2-1, "Radioactive Gaseous Effluent Monitoring Instrumentation", these monitors are actually located upstream of the Main Stack noble gas activity monitor and are not effluent monitors. They were included in Table D 3.3.2-1 in accordance with NUREG-0473. As such, Offg,as System Noble Gas Activity Monitor alarm and trip setpoints are not based on 10CFR20. The offgas system noble gas monitor alert setpoint is set at 1.5 times nominal full power background to assure compliance with ITS SR 3.7.4.1 which requires offgas sampling be performed within four hours of a 50% increase in offgas monitoring readings, and to support MSLRM trip removal. The offgas system noble gas monitor trip setpoint is based on the 1 OCFRl 00 limits for The limiting design basis gaseous waste system accident which is the offgas system rupture. The irange of the noble gas channels of the main stack and radwasteheactor building vent effluent monitors is sufficiently large to envelope both normal and accident levels of noble gas activity. The capabilities of these instruments are consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,"

December 1980 and NUREG-0737, "Clarification of the TMI Action Plan Requirements,"

November 1980. This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mi Ktures in the offgas system. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of GDC 60,63, and 64 of Appendix A to 10 CFR 50.

I B 3.3-2 Unit 2 Revision 30 September 2007

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE

Title:

Radiological Requirements Related to Operator Inspection Of High Radiation Areas Revision: NRC 2008 Task Number: N/A Approvals:

NA EXAMINATION SECURITY Date General Supervisor Date Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer:

(RO)

Trainer/Evaluator:

Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED LOCATION Expected Completion Time: 20 minutes Time Critical Tiask: NO Alternate Path Task: NO Start Time:

Stop Time:

Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if an^! critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature:

NMP2 2008 ADMIN JPM RC 1

Date:

October 2008

Recommended Start Location: (Completion time based on the start location)

Simulator or other designated location.

Simulator Set-up:

NIA Directions to the Instructor/Evaluator:

RWP and survey map to be provided with this JPM.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.

Notes to Instructor / Evaluator:

1.
2.

During Evaluated JPM:

3.

During Training JPM:

Critical steps are identified as PasslFail. All steps are sequenced critical unless denoted by a "*".

Self-verification shall be demonstrated.

0 Self-verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. GAP-RPP-01; 3.5.
2. GAP-RPP-02; 3.3.
3. GAP-RPP-08; 3.2.
4. GAP-RPP-07; 3.2.5
5. WA 2.3.12 (3.7) Knowledge of radiological safety principles related to licensed operator duties.

Tools and Equipment:

1. None.

Task Standard: Radiological requirements related to the performance of high radiation area inspection are met prior to and during the performance of the inspection.

NMP2 2008 ADMIN JPM RC 2

October 2008

Initial Conditions:

1. The plant is operating at 100% power.
2. N2-PM-M008, Monthly,Checklist is scheduled for this shift.
3. You will be conducting an inspection of the Outer Tip Room, Reactor Bldg 250.
4. An RWP and survey map are provided.
5. Your exposure is 1690 mrem TEDE at the beginning of the shift. You have inspected 3 areas already and your ED indicated 10 mrem, 15 mrem, and 5 mrem, respectively for the 3 areas already inspected.
6. Ask the operator for any questions.

RECORD START TIME NOTE: A score card is attached to this JPM identifying the items for the performer to identify.

2. *Obtain a copy of the reference N2-PM-MOO8 obtained and referenced.

Sat/Unsat procedure and reviewhtilize the correct section.

GAP-RPP-01; 3.5 referenced as required.

GAP-RPP-02; 3.3 referenced as required GAP-RPP-08; 3.2 referenced as required GAP-RPP-07; 3.2.5 referenced as required NMP2 2008 ADMIN JPM RC 3

October 2008

3..Applicable radiological Reviews RWP/Survey Map:

precautions shall be observed.

Rad Protection shall be

- Determine radiological controls:

contacted for guidance as required.

SCORECARD # I : HIGH RADIATION AREA SCORECARD #2: Area dose rates up to 790 mrem/hour.

- Determine protective clothing:

SCORECARD #3: Although no PC requirements are outlined on the RWP, determines PROTECTIVE CLOTHING IS REQUIRED because the area is a contaminated area and determines that RP must be consulted for guidance.

- Determine entry requirements dosimetry:

SCORECARD #4: Determine TLD and ED required to enter the area.

- Per GAP-RPP-08, Step 3.2.2, determine delta exposure:

SCORECARD #5: Determine required delta exposure of 300 mrem. Additional approvals ARE required prior to performing the inspection.

1690+ IO+ 7 5+5+300 = 2020 mrem (In excess of 2000 mrem requires RP and Dept Manager approval per GAP-RPP-07 3.2.5).

PasslFail PasslFail PasslFail SaVUnsat PasslFail NMP2 2008 ADMIN JPM RC 4

October 2008

I Performance Steps I Standard Grade (Personnel accessing HRA should have minimum authorized delta exposure of 300 mrern. Exceptions shall be approved by RP per GAP-RPP-08 3.2.2).

4..Check the Radiation/

SCORECARD #6: Notes area with PasslFail Contamination survey Map Entry Record Sheet for the area which require inspection.

highest contamination levels.

Comments NOTE: X-R key is for LOCKED HIGH RAD AREAS and is controlled solely by RP. X-R keys are different than keys for HIGH EAD AREAS, wnicn we keep locked. Needs H2D-13 key (indicated on survey map) which can be issued.

c. *Obtain associated key(s) from radiation protection.

SCORECARD #7: Determine H2D-13 SaffUnsat key is needed (indicated on survey map) and it is obtained from radiation protection.

PROMPT: If determines X-R key, inform the performer that RP is not authorized to issue X-R keys to operators.

RP would not issue an X-R key if requested so not critical.

End of JPM TERMINATING CUE: Radiological requirements related to the performance of high radiation area inspection are met prior to and during the performance of the inspection.

RECORD STOP TIME NMP2 2008 ADMIN JPM RC 5

October 2008

Initial Conditions:

1. The plant is operating at 100% power.
2. N2-PM-M008, Monthly Checklist is scheduled for this shift.
3. You will be conducting an inspection of the Outer Tip Room, Reactor Bldg 250.
4. A RWP and survey map are provided.
5. Your exposure is 1690 mrem TEDE at the beginning of the shift. You have inspected 3 areas already and your ED indicated 10 mrem, 15 mrem, and 5 imrem, respectively for the 3 areas already inspected.
6. Ask the operator for any questions.

Initiating cue:

(Operators name), you will be performing N2-PM-M008, Monthly Checklist, for the Outer Tip, Reactor Building 250. An RWP and a survey map are provided. Address the radiological aspects of performing this inspection. Document your findings on the SCORECARD provided NMP2 2008 ADMIN JPM RC 6

October 2008

OK TO PROVIDE TO CANDIDATE Answer the following when performing this task:

Classify the area (check one):

0 Radiation Area U High Radiation Area U Locked High Radiation Area

[I1 Very High Radiation Area SCORECARD #2:

Designate the highest dose rate in the area and the location:

SCORECARD #3:

Designate whether or not protective clothing is required (check one):

0 Yes 0

No

~.

OR Designate required dosimetry to enter the area:

SCORECARD #5:

Evaluate delta exposure (check one) and explain:

17 Acceptable 0

Additional approval(s) required SCORECARD #6:

Designate the highest contamination levels in the room and the location:

SCORECARD #7:

Designate the key to be obtained AND who controls the key.

NMP2 2008 ADMIN JPM RC 7

October 2008

NOTE: THIS IS THE EXAMINER SCORECARD.

DO NOT PROVIDE TO THE CANDIDATE.

Answer the following when performing this task:

J High Radiation Area Cl Locked High Radiation Area C1 Very High Radiation Area cation:

190 mrem/hr, Between Tip Machine D & E Designate whether or not protective clothing is required (check one):

J Yes 0

No The area is a Contaminated Area SCORECARD #:

SATIU NSAT Designate required dosimetry to enter the area:

TLD and ED (Electronic Dosimeter)

~.

Evaluate delta exposure (check one) and explain:

Total is 1690+10+15+5+300 = 2020 mrem 0

Acceptable Additional approval(s) required Explan a tion:

0 0

In excess of 2000 mrem requires RP and Dept Manager approval per GAP-RPP-07 3.2.5.

Personnel accessing HRA should have minimum authorized delta exposure of 300 mrem. Exceptions shall be approved by RP per GA P-RPP-08 3.2.2 SCORECARD #6:

SSI Designate the highest contamination levels in the roorn and the location:

20,000dpm/l00cm2 at Tip Machine C SCORECARD SATIU NSAT Designate the key to be obtained AND who controls the key:

H2D-13 controlled by RP NMP2 2008 ADMIN JPM RC 8

October 2008

Reactor Building 250' Outer TIP Room - For Training Only NMP Survey No. 2RB-25430 Quarterly Radiation/Contamination Survey H2D-13 Key 7 Map No.

2!9A 3, 2 = General Area Unless Noted 4'

2. @ =Smear Location

= Rope/Area Boundary

8.

=Area Rad Monitor

9. v#I VAMP Number y = Readings in mRem/hr. p = Readings in mRad/hr.
  • # - Y P Contact Y P 30cm Remarks: No beta detected SAC4 04/05/08 RM-14 08/01/08 Dose:

2 mRem Reviewed By:

Date:

311 512005 10:00:25AM Page 1 of 1 Radiation Work Permit: 205022 A Shift OPS HRA Standing RWP Survey Data:

Radiation Turbine Building HRAs

<I to 450mRem/hr / Reactor Building HRAs <I to 400mRem/hr

~

~~

~~

~~

~~~

~~

Levels:

Rad Waste Buiding HRAs e1 to 400mRemlhr / Off Gas Building HRAs <I to 120mRemlhr Contamination Levels: <400 - 45,00Odpm/l OOcm / Airborne Levels:

C0.3 DAC Specific areas as per RP briefing and / or survey maps.

Low Risk Activity **********

Dose Alarm 50 mRem Backoff Dose 40 mRem

~

~~

Task: 1 High Radiation Area Clearances

~

~~~~~~

~~

~

Task: 2 High Radiation Area Cond.Demin Activities Task: 3

~

~~

~~

High Radiation Area Other Ops Activities

~~~~~

~

~~~~~

Task: 4 High Radiation Area T rai n i n g Activities Task: 5

~

~~~

High Radiation Area Turbine Building Rounds Task: 6 High Radiation Area Reactor Building Rounds Task: 7

~~~~~

~

High Radiation Area Surveillance 's/PMs

~

Protective Clothing Requirements (common to all tasks):

TLD, Electronic Dosimeter Dose Rate Alarm Elapsed Time Alarm

~

~~

500 mRemlHr 780 minutes 1433

~~

~~~~

BAR CODE BAR CODE BAR CODE

~~

BAR CODE BAR CODE BAR CODE BAR CODE Standing RWP PCs Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP.

311 512005 10:00:25AM Page 1 of 1 Radiation Work Permit: 205022 A Shift OPS HRA Standing RWP Survey Data:

Radiation Turbine Building HRAs

< I to 450mRem/hr / Reactor Building HRAs e1 to 400mRemlhr

~

~

~~~

~

~-

~~~

~~~

Levels:

Rad Waste Buiding HRAs < I to 400mRem/hr / Off Gas Building HRAs 21 16393 1667 833 256

- - r (rnilh)

A I

BIC I ElFlG (milh)

I A

l BIC I

D I

>21 i 17241 i 4348 i 2632 i 3 2

g 10-3 1333 213 119 38 0-3 2041 1124 4-6 3226 286 143 48 4-6 3703 909 769 7-9 5556 536 750 83 7-9 5882 1515 1075 1250 10-13 7692 769 357 117 10-1 3 7692 2083 1388 14-1 7 11494 2857 1818 22'73 14-17 10753 1075 500 1 64 TABLE 1.3 - EPA 400 Protective Action Guidelines (EPA PAGs)

EPIP-EPP-08 Rev 19

ATTACHMENT 1: INITIAL DOSE ASSESSMENT AND PROTECTIVE ACTIONS FIGURE 1.5 - ERPA Map Page 11 EP I P-EPP-08 Rev 19

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