Text

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: IR 05000410/2008303; ML082520298; ML082740366; ML082960011; ML083110428; ML083110457; ML083110465; ML083580209; ML083580222; ML083650054; ML083650061;
References
	TAC U01778
	Download: ML083110428 (75)
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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

/ YhJLF N/A - Exam Security I Gene61 Subervisdr Date General Supervisor Date OperationsTraining (Designee) 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 Self verification shall be demonstrated.

3. During Training JPM:

0 Self verification shall be demonstrated.

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

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 back (GAP-OPS-Ol/Operations Manual) providing correction if necessary.

RECORD START TIME

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

NRC 2008 ADMlN JPM COO1 - 3 .- October 2008

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

Reactor Operators 1 and 2 SRO #I - Eligible SRO #2 - Not Eligible - would exceed 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

4. FOR SROs - Completes Overtime Completes Columns 1 and 2 of Part 1 of Pass/Fail Deviation Request Form GAP-FFD-02 Attachment 1, per attached key SatlUnsat C'ompletes Columns 3 and 4 of Part 1 of GAP-FFD-02 Attachment 1, per attached key SaVUnsat Clompletes Part 2.A of GAP-FFD-02 Attachment 1, 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 10119 10120 10121 10122 10123 10124 10125 10126 10127 1830-0642 1830-0642 1830-0730 1830-0542 1830-0642 1830-0706 (includes 12 (includes 12 (includes 60 (includes 12 (includes 12 (includes 36 OFF minutes of minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time) turnover time)

RO #2 I

10/19 10120 1012 1 10122 10123 10124 10125 10126 10127 I I I I I I I (includes 12 (Includes 0 (includes 12 ' (includes 24 (includes 12 (includes 12 OFF OFF minutes of minutes of minutes of minutes of minutes of minutes of turnover time) turnover time) turnover time) turnover time) turnover time) turnover time)

RO #3 10119 10120 1012 1 10122 10123 10124 10125 10126 10127 I I I 1830-0642 1830-0630 1830-0648 1830-0642 1830-0642 1830-0742 (includes 12 (includes 0 (includes 18 (includes 12 (includes 12 (includes 12 OFF 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 October 2008

ATTACHMENT B SROS 10119 10120 10121 10122 10123 10124 10125 10126 10127 1830-0642 1830-0642 1830-0735 1830-0642 1830-0720 (includes (includes (includes (includes (includes 12 minutes 12 minutes OFF 65 minutes OFF 12 minutes 50 minutes OFF OFF of turnover of turnover of turnover of turnover of turnover time) time) time) time) time) 10119 10120 1012 1 10122 10123 10124 10125 10126 10127 1830-0642 1830-0630 1830-0648 1830-0642 0630-1830 0500-1200 (includes (includes 0 (includes finc!g&s 0 12 minutes minutes of 18 minutes OFF minutes of OFF of turnover turnover of turnover turnover time) time) time) time)

NRC 2008 ADMIN JPM COO1 October 2008

ATTACHMENT C - RO Answer Sheet Eligible to work without an If No, what work hour limit(

Overtime Deviation Request? would be exceeded IAW Gf (Yes/No) FFD-02?

RO #I RO #2 RO #3 NRC 2008 ADMIN JPM COO1 October 2008

ATTACHMENT D - SRO Answer Sheet Eligible to work without an If No, what work hour limit1 Overtime Deviation Request? would be exceeded IAW GI (Yes/No) FFD-02?

I RO #I RO #2 RO #3 SRO #I SRO #2 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 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. From the provided list of personnel working hours, determine who is eligible to work a complete 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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:NTC - - KO Answer Sheet Eligible to work without an If No, what work hour limit(s)

Overtime Deviation Request? would be exceeded IAW CAP-FFD-02?

KO #1 KO #2 K O #3 NIIC' 2008 A D M I N JPM COO2 October 2008

ATTACHMENT D -. SkO Answer Sheet i- .. . . . __ .. __ .

Eligible to work without an If No, what work hour limit(s)

Overtime Deviation Request would be exceeded IAW GAP-

- (YesiNo) FFII-02 ?- _ I - . --

I K O #l 110 #2 I .

RO #3

'/I'. .

SKO #2 N l i C 2008 AI)MlN JI'M C O O 2 Octobcr 2008

CONTROL OF WORKING HOURS GAP-FFD-0%

Revision 01700 Page 1 of 1 Attachment 1, OVERTIME DEVIATION REQUEST I OVERTIME DEVIATION REQUEST i PART 1 TYPEOF OVERTIME DEVIATION 1 More than 16 consecutive hours 3 More than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period 5 Less than 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break between work penods 7 More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months penod 4 More than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months tin a 7 day period 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 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months , 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.

f I:

1 P *bJ

Nine Mile Point Nuclear Station Station Administrative Procedure GAP-FFD-02 CONTROL OF WORKING HOURS Revision 01700 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 01700 Page 2 of 10

SUMMARY

OF ALTERATIONS Revision Change Summary of Revision or Change 017 00 Reworded Section 5.3.A Section 7: Added guidance for retention of monthly overtime reports.

CONTROL OF WORKING HOURS --,i 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 INTRODUCTION ........................................................................................................................... 4 1.1 Purpose ........................................................................................................................ 4 1.2 Scope/Applicability: ....................................................................................................... 4

2.0 REFERENCES

.............................................................................................................................. 4 2.1 Developmental References .......................................................................................... 4 2.2 Performance References .............................................................................................. 4 3.0 DEFINITIONS ............................................................................................................................... 4 4.0 RESPONSIBILITIES ..................................................................................................................... 5 5.0 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 6.0 BASES .......................................................................................................................................... 9 7.0 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. Unit 2 Technical Specifications, Section 5.2.2, Unit Staff C. 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 0 hours 0 weeks 0 months on the first day and ending at 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months 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. Managers/Directors C. General Supervisors/Supervisors D. Individuals who work in excess of the limitations stated in Section 5.1 of this procedure 5.0 PROCESS 5.1 Work Hour Limits 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 01700 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for any individual tour of duty i s 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 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight

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

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

d. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift schedule, who, as a result of transition in and out of daylight savings time, will exceed the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 NCTS 503524- 10, NM PC will review all departments methods of overtime control and tracking.

[NO021 DER C-95-3190 Provide definition for 7-day period.

[NO031 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.

[NO041 DER NM-2001-1737 Apparent reliance on the excessive u s e of overtime deviations to complete RF016.

7.0 RECORDS Completed Attachment l s , 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 :.\ i ~ - ' GAP-FFD-02 1 i Revision 01700 Page 1 of 1 Attachment 1, OVERTIME DEVIATION REQUEST OVERTIME DEVIATION REQUEST 1

PART 1 TYPEOF OVERTIME DEVIATION TYPEOF TIMEPERIOD OF DEVIATION OVERTIME Name of Personnel (List Names Individually) DEV.(1-5) FROM (DATERIME) To (DATE~IME)

PART 2 -

A. Reason for Deviation I .I

6. Method to monitor employee physicallmental fitness I-I

---I Supervisor (Print/Signature)* IDate (PrinffSignature) (Date __

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

Upon signing, the Supervisor has verified :I) that no one will work greater than 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months , 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 Self checking shall be demonstrated.

3. During Training JPM:

0 Self checking shall be demonstrated.

0 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:

.. 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.

e 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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.

e

. 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 e 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 10CFR50.72 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 logic is not reportable under 50.72 references 50.72 (b)(3)(iv)(B)(2). (b)(3)(iv)(B)(2) because the actuation is not due to a valid signal.

LER is not a verbal reporting 0 LER if; required under 50.73 Sat/Unsat/NA requirement. (b)(2)(:iv). Identification of this requirement is not required.

Locate and identify applicability of Identifies leak rate above 10 gpm PasslFail 50.72(a)( 1)(i). Declaration of an requires EAL 2.1 .I UNUSUAL Emergency Class. 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.

Locate and identify applicability of Refer 1.0 Tech Spec 3.4.5.C. and SaUUnsat 50.72(b)(2)(i). Non-emergency determines that with specification not four hour report. Initiation of a being met, the required action to plant shutdown required by Tech comply with Tech Spec is to be cold Specs. (If not already reported shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The plant with the 50.72(a)(l)(i). shutdown being performed is required by Tech Specs.

0 Identify reportability per 50.72(b)( PasslFail 2)(i) within four hours, if not already reported.

Locate and identify applicability of 0 Identify reportability per PasslFail 50.72(b)(2)( iv)(B) Non- 50.72(b)(2)(iv)(B) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , if emergency four hour report. not already reported.

Actuation of RPS when the reactor is critical.

Locate and identify applicability of Identify reportability per PasslFail 50.72(b)(3)(iv)(A)( iv)(B)(2) Non- 50.72@)(3)(iv)(A)(iv)(B)(2).

emergency eight hour report. within El hours, if not already Actuation reported.

End of JPM TERMINATING CUE: Determine notification requirements.

RECORD STOP TIME 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months despite leakage reduction attempts.

Actions to comply with Tech Specs as n result of the leakage are initiated and N2-OP-101C, 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

Attac himent 1 JPM Scorecard KEY Identify the applicable verbal reportability requirements, the reason that I they apply and the associated time limitations for reporting under that category Reportability Time Limi,t Reason (Event) Category Reauirement Applies 50.72 (b)(3)(iv)(A) also NOT Containment Purge Isolation references 50.72 REPOR 'ABLE during maintenance activity. Also, (b)(3)(iv)(B)(2). General only affects one system.

containment isolation signals.

50.72(a)(l)(i) and (a)(3). Within 15 rriinutes Declaration of UE 2.1 . I Declaration of an of declaration, Emergency Class immediately after notifying state and local agenciies and not later than one hour after the time of declaration 50.72(b)(2)(i). Initiation of a Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , if Initiation of a plant shutdown plant shutdown required by not previously required by Tech Specs 3.4.5.C Tech Specs reported. Unidentified leakage is above 5 gpm for >4 hours.

50.72(b)(2)(iv)(B). Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , if Automatic reactor trip when the Actuation of RPS when the not previously reactor is critical.

reactor is critical. reported.

50.72( b)(3)(iv)(A)(iv)(B)(2). Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , if MSlV Isolation not previously reported.

NMP2 NRC SRO ADMlN JPM COO2 6 October 2008

Attact-I ment 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 Time Limit Reason (Event) Category Reauirement 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 01 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) I f 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 t o 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. Ifnot 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 t o 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. I f 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 t o 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 51200 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 t o 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) f f F A c t u a t i o n 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 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 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 9-17-08 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. Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by a o.

2. During Evaluated JPM:

0 Self-verification shall be demonstrated.

3. During Training JPM:

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 2.3.11, 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 Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME PART A

1. .Obtain a copy of the reference u ODCM obtained. Section D.3.3.2 and Sat/Unsat procedure and reviewhtilize the Bases B 3.3.2 are referenced.

correct section.

2. .Reference CONDITION B 0 Determines that the inoperable OFG Sat/Unsat Radiation Monitors must be restored to OPERABLE status within 30 days.

0 Refers to Table 3.3.2-1 Sat/ Unsat 0 Determines that CONDITION C is Sat/Unsat applicable NMP2 2008 Retake NRC SRO ADMlN JPM EC Rev 9-17-08 3 October 2008

3. .Reference CONDITION C o Action C . l - place channels in trip Sat/ Unsat condition EXAMINER NOTE: If Candidate Determines that tripping both implements REQUIRED ACTION channels of OFG*RE13A and B C . l , OFG will isolate. would isolate OFG.

In order to continue the JPM (part B), OR inform the candidate that instead of Action C.1, the other Actions were implemented for sampling. Then o Action C.2.1 Pass/Fail provide the applicant with the Part B Determines that OFG grab samples Initial Condition information sheet. must be taken within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

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

Part B EVALUATOR: When the candidate Cue: Asked the candidate to determines the ODCM sample determine when the first and second requirements, provide the samples are due based upon a 06:OO candidate with the attached PART time for the OFG*RI3A/B B Initial Conditions and Initiating inoperabilities.

Cues Information Sheet.

NMP2 2008 Retake NRC SRO ADMIN JPM EC Rev 9-17-08 4 October 2008

I Performance steps ] Standard Grade I Comments

1. .Obtain a copy of the applicable o Reviews ODCM Section 3.0, Sat/Unsat reference documents and review/ Applicability.

utilize the correct sections. o Reviews Tech Spec Section 1.3, Sat/Unsat Completion Times.

2. .Determines that Example 1.3-1 First sample is due by 18:OO today PasslFail I I applies to the first 12 Hours

3. *Determines that Example 1.3-6 o Second sample is due by 06:OO Pass/Fail 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months + a 25% extension of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months = 15 applies to the next AND once tomorrow, with an allowable hours per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. extension of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months (as late as 09:OO)

End of JPM TERMINAT!NG 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 D 3.3 INSTRUMENTATION D 3.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DLCO 3.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table D 3.3.2-1 shall be FUNCTIONAL with:

a. The minimum FUNCTIONAL channel(s) in service.

b. 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.

c. The a l d t r i setpoints of RadwasteReactor Building Vent Effluent NobIpe 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.

APPLICABILITY According to Table D 3.3.2-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gaseous effluent A.l Suspend the release of Immediately monitoring instrumentation radiloactive gaseous effluents channel a l a d t r i p setpoint monitored by the affected less conservative than channel.

required.

OK A.2 Declare the channel Immediately nonjhnctional.

Immediately A.3 Change the setpoint so it is

__.____.- acceptably conservative.

(continued)

Unit 2 Revision 30 13.3-7 September 2007

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more channels B. 1 Enter the Condition referenced Immediately nonfunctional. in Table D 3.3.2-1 for the channel.

AND B.2 Restore nonfunctional 30 days channel(s) to FUNCTIONAL status.

C. As required by Required C.1 Place the nonfunctional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B. 1 and referenced channel in the tripped in Table D 3.3.2-1. ccmdition.

C.2.1 Take grab samples. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter C.2.2 Analyze samples for gross 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from timie activity. of sampling completion (continued)

Unit 2 Revision 30 I 3.3-8 September 2007

Radioactive Gaseous Effluent Monitoring Instrumentation D 3.3.2 ACTIONS (continued)

- 1 CONDITION REQUIRED ACTION COMPLETION rIME D. As required by Required Estimate the flow rate for the 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action B. 1 and referenced nonfunctional channel(s).

in Table D 3.3.2-1.

3nce per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

hereafter E. As required by Required E. 1 Continuously collect samples 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Action B. 1 and referenced using auxiliary sampling in Table D 3.3.2-1. equipment as required in Table D 3.2.1-1.

F. As required by Required F. 1.1 Take grab samples. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action B. 1 and referenced in Table D 3.3.2-1. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND F. 1.2 Analyze samples for gross 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from time activity with a radioactivity of sampling limit of detection of at least completion 1 x lo4 pCi/ml.

AND F.2.1 Restore the nonfunctional 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channel(s) to FUNCTIONAL status.

OR F.2.2 Through a CR, determine: 14 days (1) The cause(s) of the nonfunctional.

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

(continued)

Unit 2 Revision 30 I 3.3-9 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 FREQUENCY DSR 3.3.2.7 Perform CHANNEL CALIBRATION. The initial 24 months CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology k? IST) or using standards that have been obtained om suppliers that participate in measurement assurance activities with NIST, or usin actual samples of gaseous effluents that have een analyzed on a system that has been calibrated with NIST traceable sources. These standards shall permit calibrating the system over. its intended ran e of energy and measurement. For subsequent HANNEL8 CALIBRATIONysources that have been related to the initial calibration may be used.

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. 18 months DSR 3.3.2.9 Perform CHANNEL CALIBRATION. The initial 18 months 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 samples of gaseous effluents that have een analyzed 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.

~~

DSR 3.3.2.10 Perform CHANNEL CALIBRATION. 24 months Unit 2 Revision 30 13.3-12 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) 2 C DSR 3.3.2.1 Activity Monitor DSR 3.3.2.4

- Providing DSR 3.3.2.1 Alarm and Automatic Termination of Release

b. System Flow- (a) 1 D DSR 3.3.2.1 Rate Measuring DSR 3.3.2.5 Device DSR 3.3.2.10 (a) 2 D DSR 3.3.2.1

c. Sample Flow- DSR 3.3.2.5 Rate Measuring DSR 3.3.2.10 Device

2. RadwasteReactor Building Vent Effluent System

a. Noble Gas (b) 1 F DSR 3.3.2.1 Activity Monitor DSR 3.3.2.3 (c) DSR 3.3.2.6 DSR 3.3.2.9

b. Iodine Sampler (b) 1 E DSR 3.3.2.2

c. Particulate (b) 1 E DSR 3.3.2.2 Sampler

d. Flow-Rate (b) 1 D DSR 3.3.2. I Monitor DSR 3.3.2.5 DSR 3.3.2.8

e. Sample Flow- (b) 1 D DSR 3.3.2.1 Rate Monitor 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.

Unit 2 Revision 30 13.3-13 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. Noble Gas DSR 3.3.2.1 Activity Monitor DSR 3.3.2.3 (c) DSR 3.3.2.6 DSR 3.3.2.9

b. Iodine Sampler DSR 3.3.2.2 C. Particulate DSR 3.3.2.2 Sampler

d. Flow-Rate DSR 3.3.2.1 Monitor DSR 3.3.2.5 DSR 3.3.2.8

e. Sample Flow- DSR 3.3.2.1 Rate Monitor DSR 3.3.2.5 DSR 3.3.2.8

~~

(b) At all times (c) Includes high range noble gas monitoring capability.

Unit 2 Revision 30 13.3-14 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,asSystem 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 10CFRl 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.

Unit 2 Revision 30 I B 3.3-2 September 2007

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE

Title:

Radiological Requirements Related to Operator Inspection Revision: NRC 2008 Of High Radiation Areas 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: Date:

NMP2 2008 ADMIN JPM RC 1 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. Critical steps are identified as PasslFail. All steps are sequenced critical unless denoted by a "*".

2. During Evaluated JPM:

Self-verification shall be demonstrated.

3. During Training JPM:

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 PasslFail AREA SCORECARD #2: Area dose rates PasslFail up to 790 mrem/hour.

- Determine protective clothing:

SCORECARD #3: Although no PC PasslFail 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: SaVUnsat SCORECARD #4: Determine TLD and ED required to enter the area.

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

NMP2 2008 ADMIN JPM RC 4 October 2008

I Performance Steps I Standard Grade Comments (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 highest contamination levels.

Record Sheet for the area which require inspection.

NOTE: X-R key is for LOCKED PROMPT: If determines X-R key, inform HIGH RAD AREAS and is the performer that RP is not authorized controlled solely by RP. X-R keys to issue X-R keys to operators.

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 SCORECARD #7: Determine H2D-13 SaffUnsat RP would not issue an X-R key if requested so not radiation protection. key is needed (indicated on survey critical.

map) and it is obtained from radiation protection.

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 0Additional 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 #: SATIUNSAT Designate required dosimetry to enter the area:

TLD and ED (Electronic Dosimeter)

~.

Evaluate delta exposure (check one) and explain: 0 Acceptable Total is 1690+10+15+5+300 = 2020 mrem Additional approval(s) required Explanation:

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

0 Personnel accessing HRA should have minimum authorized delta exposure of 300 mrem. Exceptions shall be approved by RP per GAP-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 SATIUNSAT 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' Map No.

NMP Outer TIP Room - For Training Only 2!9A Survey No. 2RB-25430 Quarterly Radiation/Contamination Survey H2D-13 Key 7 -

= Rope/Area

- Boundary 2. @ =Smear Location 3, 2 = General Area Unless Noted 4'

- Y P Contact

# Y P 30cm

8. =Area Rad Monitor 9. v#I VAMP Number y = Readings in mRem/hr. p = Readings in mRad/hr.

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 Dose Rate Alarm 500 mRemlHr Backoff Dose 40 mRem Elapsed Time Alarm 780 minutes 1433

~ ~~ ~~ ~~~~

~ ~~

Task: 1 High Radiation Area BAR CODE Clearances

~~ ~ ~ ~~~~~~

Task: 2 High Radiation Area BAR CODE Cond.Demin Activities

~~ ~ ~~

Task: 3 High Radiation Area BAR CODE Other Ops Activities

~~~~~ ~ ~~

~~~~~

Task: 4 High Radiation Area BAR CODE T raining Activities

~ ~~~

Task: 5 High Radiation Area BAR CODE Turbine Building Rounds Task: 6 High Radiation Area BAR CODE Reactor Building Rounds

~~~~~ ~

Task: 7 High Radiation Area BAR CODE Surveillance 's/PMs

~

Protective Clothing Requirements (common to all tasks): Standing RWP PCs TLD, Electronic Dosimeter 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 < I to 120mRem/hr Contamination Levels: ~ 4 0 -045,00Odpm/l OOcm / (Airborne Levels: ~ 0 . 3DAC Specific areas as per RP briefing and / or survey maps.

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

Dose Alarm 50 mRem Dose Rate Alarm 500 mRemlHr Backoff Dose

~ ~~~ ~~-

40 mRem

~- ~ ~

Elapsed Time Alarm

~~ ~~ ~

780 minutes

-~

1433 PC Requirements based on areas entered If entry to a Contaminated Area is required on this RWP, Contact Radiation Protection for Protective Clothing Requirements.

Instructions (common to all tasks):

1) Notify RP prior to venting/draining evolutions or other system breach.

2) No entry above arms reach unless specifically approved by RP.

ALARA Review Number:

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

CONSTELLATION ENERGY GROUP OPERATOR JOB PERFORMANCE MEASURE

Title:

Emergency Classification With PARS Rev: NRC2008 Task Number: N/A Approvals: .

G e n w Supervisd

?/d,)/@

Date 1

- NA EXAMINATION SECURITY General Supervisor Date Operations yraining (Designee) Clperations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer: (SRO)

TrainedEvaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant >: Simulator or other location Expected Completion Time: 20 min Time Critical Task: YES 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 w: critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature: Date:

NMP2 2008 SRO ADMIN JPM EP October 2008

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

Any appropriate location with proper references.

Simulator Set-up (if required):

None Directions to the Instructor/Evaluator:

Candidate is to be provided with blank SM/ED Emergency Plan packet (obtained from control room or simulator) that would be used by SM/ED during actual emergency plan implementation.

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 equipment 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 Training 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 if

" 9, 0 .

2. During Evaluated JPM:

0 Self checking shall be demonstrated.

3. During Training JPM:

0 Self checking shall be demonstrated.

0 Peer checking shall be demonstrated.

References:

1. EPIP-EPP-08, Offsite Dose Assessment And Protective Action Recommendations

2. EPIP-EPP-20, Emergency Notifications

3. EAL Matrix Tools and Equipment:

1. EAL Matrix

2. SMlED Emergency Plan Packet Task Standard:

Given a set of plant conditions, classify the emergency (within 15 min.), and complete the Part 1 Notification Fact sheet including PARS (within 15 min.)

NMP2 NRC SRO ADMIN JPM EP October 2008

Initial Conditions:

1. The plant is under accident conditions.

2. A Site Area Emergency has been declared based on plant conditions.

3. An Exclusion Area Evacuation has been directed and is in progress.

4. The Chemistry Technician has just reported the following new release data:

0 Dose assessment for ground level release rate is 154 Curies per second (CVsecond) 0 Dose assessment for elevated level release rate is 842 Ci/second 0 Wind speed is 12 mph 0 Wind direction is from (65) 0 Pascal Stability Class is D Initiating Cues:

(Operators name), evaluate the new data and take the required actions as the Emergency Director.

Performance Steps Standard Grade -

Evaluator Note: Inform the Candidate that this is a Time-Critical task

1. Provide repeat back of initiating cue. Proper communications used for repeat back Sat/Unsat Evaluator Acknowledge repeat back (GAP-OPS-OIlOperations Manual) providing correction if necessary.

RECORD TASK 1 CRITICAL START TIME

2. Obtain a copy of the reference procedure The candidate may reference any/all of the Sat/Unsat and reviewlutilize the correct section of the follow ing :

procedure. EAL Matrix obtained. Section 5.0 EPIP-EPP-08 Att. 1

3. Using given plant data and EPIPO-EPP-08 General Emergency is declared, within 15 PasslFail Attachment 1 Table 1.Iand Table 1.2, minutes of recorded start time for Task 1.

determine that a General Emergency exists based upon calculated total release From EPP-08 Attachment (ground release + elevated release).

154/357 = (.431) + 842/1388 = (.607) =

1.038 (General Emergency Exists if above 1.O)

RECORD TASK 1 CRITICAL STOP/ TASK 2 CRITICAL START TIME

4. Review meteorological data and EPIP- PARs made and indicated on Part I PasslFail EPP-08 and/or EPIP-EPP-20 to determine Notifitcation Fact Sheet Block 6.B to evacuate PARs. and implement the KI Plan for ERPAs 1, 2, 3,6,11, 26, and 27. Advise the remaining Cue: If asked, all evacuation routes are ERPAs listen to Emergency Alert System, available for use. within 15 minutes of recorded start time for Task 2.

RECORD TASK 2 CRITICAL STOP TIME NMP2 NRC SRO ADMIN JPM EP October 2008

Terminating Cue: The event is classified as a General Emergency and PARS are made.

RECORD STOP TIME NMP2 NRC SRO ADMIN JPM EP October 2008

Initial Conditions:

1. The plant is under accident conditions.

2. A Site Area Emergency has been declared based on plant conditions.

3. An Exclusion Area Evacuation has been directed and is in progress.

4. The Chemistry Technician has just reported the following new release data:

0 Dose assessment for ground level release rate is 154 Curies per second (Cikecond) 0 Dose assessment for elevated level release rate is 842 Cikecond Wind speed is 12 mph 0 Wind direction is from (65) 0 Pascal Stability Class is D Initiating Cues:

(Operators name), evaluate the new data and take the required actions as the Emergency Director.

NMP2 2008 SRO ADMIN JPM EP October 2008

ATTACHMENT 1: SMlED CHECKLIST Name: Date: Unit IIH NOTES: 1. All steps should be performed.

2. Use NlA or NlR if appropriate,

3. A log documenting activities should be maintained. Completed NIA UE Alert SAE GE N/A

1. ........................................................................ 0 0 0

2. Classify the emergency per EPIP-EPP-01 or EPIP-EPP-02 (within 15 minutes of indicationsavailable in control room)................................................................................................. 0 0 0 do I

3. Using Attachment 1, Figure 1 flowchart determine the appropriate evacuation and accountability .. 0 d0

4. Announce to Control Room staff you are now assuming SMlED position and duties, and you are now declaring (state emergency classification level), and provide reason for classificationldeclarationlupgrade....................................................... 0 0 0 NOTE: IF: the announcement for a ground attack has been made as required by EPIP-EPP-10, THEN: DO NOT make further announcements until safety is assured, coordinate as necessary with security.

5. Direct the appropriate announcement to be made using Attachment 2 of this procedure.................0 0 0 d n NOTE: If reclassifying and ERO has not been notified, repeat step 7 .

6. inform unaffected unit SM of forthcoming CAN notification f,ax and request Communications Aide call CAN in accordancewith faxed attachment (only need to call out the ERO one time) ......... 0 0 or higher

7. Completethe following in accordance with EPIP-EPP-20:

a. Part 1 Notification Fact Sheet (provide to Comm Aide) Include information from other /

unit as applicable .................................................................................................................... 0 0 0 d E: Assure the safety of the ERO before making CAN Notifications.Consider directing ERO responseto Alternate Emergency Duty Location.

b. CAN Notification Form

1) Fax completed form to unaffected unit Control Room, verify received (UI-2996, U2-1207) ......................................................................................................... 0 or higher

c. NRC Notification Worksheets (provide to Comm Aide) .......................................................... 0 0 0 0 0 NOTE: For events affecting both units, direct other Unit SM to complete NRC notification worksheet and notify the NRC

8. Verify appropriate Site Emergency Procedures implementation per Attachment 8 .......................... 0 0 0

9. Implementemergency exposure controls in accordance witti EPIP-EPP-15 (Including issuing KI as required) ............................................................................... 0 0 0 0 0

10. Implement Protective Actions as needed per EPIP-EPP-08,Attachment 1....................................................... CONTINUOUS Page 5 EPIP-EPP-18 Rev 16

ATTACHMEN4 (Cont)

Page 2 of 4 Comdeted.

UE Alert SAE GE NIA

11. Verifv completion of notificationsin accordance with EPIP-EPP-20:

State and County via RECS (within 15 minutes of declaration)..................................................

ERO via CAN (verify through unaffected unit SM) ...................................................................... 0 or higher

[7 I NRC via ENS .............................................................................................................................. 13 NOTES: 1. PARSmust be communicatedto NYS and Oswego County within 15 minutes of declaration of General Emergency.

2. The step below (Step 12) only applies to the Unit 2 SM.

(Cl) 12. If an emergency is declared that involves any type or size Loss of Coolant Accident (LOCA) at Unit 2, the Unit 2 SM shall advise the Unit 1 SM to initiate the Unit 1 Control Room EmergencyVentilation system ................................................................... CONTINUOUS

13. If notified by Security that the accountability report printout has been initiated, instruct CSO to make announcement per Attachment 3............................................. cl 0

14. If notified of a failure of the security computer provide a list of control room personnel to PersonnelAccountability Coordinator (~2662) .........................................

15. Determinewhat assistance, if any is required from JAFNPP or other Organizations (refer to EPIP-EPP-32, as necessary) ....................................................................................... CONTINUOUS

16. Provide status announcementsto station personnel as necessary using Attachment 5 .................................. CONTINUOUS

17. Review and approve news releases from Public Affairs and Corporate Communication(PACC)............................................................................................. I3

18. Keep informed through the Dose Assessment Advisor of actual release rates as compared to General Emergency release rates................................................................... 0 0

19. Complete Figure 2 and fax to ext. 2111. Providehpdate the status of the plant emergency to the TSC Manager using information provided on Figure 2. ........................................................... 17

20. Ensure turnover of NRC notifications to TSC ENS Communicator when notified that TSC is activated.......................................................................................................................... 0 17 NOTES: 1. If a classification is made in the control room, notifications should be made from the control room until all are completed for that classification.

2. Completion of Notification Fact Sheet Part 1 ilnd CAN Notifications remain in the control room, until assumed by the EOF Communications Coordinator.

21. Complete Figure 2 and fax to EOF at 593-5920. When called by the EDlRM, turn over the status of the plant emergency using information provide on Figure2 ................................................ 17 0 Page 6 EPIP-EPP-18 Rev 16

ATTACHMEN= (Cont)

Page 3 of 4 Completed NY

22. When notified that the EOF is activated, ensure turn-over of Statelcounty Notifications to EOF Communications Coordinator................................................................................................................. 0 0

23. When notified that the EDlRM has assumed the duties of the Emergency Director at the EOF, make the following announcement:

0 Place GAltronics in Merge (if not done so already) 0 Sound StationAlarm for 10 Seconds 0 Announce:

AAttention, this is a drillI an actual event (circle one) As of hrs, overall authority for control of the emergency has been transferredto the Emergency DirectorlRecovery Manager, (name) in the EOF. This is a drill I an actual event (circle one). I 0 RepeatAlarm and Announcement (1 time). ................................................................................................ 0 0

24. Following activation of the OSC, direct shift personnel and other available operations personnel not assigned control room or DCT functions to report to the OSC for assignment in accordance with EPIP-EPP-22 ............................................................................................................................................. 0 0

25. Continue to monitor plant status and provide recommendationsto EDlRM when changes in plant conditions require upgradesto the Emergency Classification (includetime indicationswere available)............CONTINUOUS

26. Communicate as needed in-plant correctivelmitigative actioiis to the TSC Manager and EDlRM and request this assistance be supplied from the OSC ............................................................................................ CONTINUOUS (C4) 27. WHEN informedlaware of changes in classificationlplant status changes andlor emergency termination THEN coordinate with the EDlRM regarding EmergencyAnnouncements content and ensure announcements are timely and made in accordancewith Attachments 2-7 of this procedure ......................... CONTINUOUS

28. Evaluate termination or re-classification of the emergency or make recommendationsas necessaryto the EDlRM in accordance with EPIP-EPP-25............................................................................... CONTINUOUS

29. Ensure Termination Announcement is made when the event is terminated, or as directed by the EDlRM in accordance with Attachment 7 ......................................................................................................... 17 0 (C2) 30. Collect and retain for the Emergency PreparednessDepartmentall paperwork generated as a result the event for possible inclusion in the PermanentPlant File.............................................................................. 17 0 Page 7 EPIP-EPP-18 Rev 16

ATTACHMENT 'I: FIGURE 1 EVACUATIO~IACCOUNTABiLlTYFLOWCHART classification of the Implement

~ --

NO No I

I I

I 1 N O - C

-4)

-+

i I ImpkmentEPiP-1

~

EPP-056,

! Area Proleaad L EwGuabQL -1 i implement 1

iI - EPIP-EPP-OLD - 4 f Accountability A 1

Page 8 EPIP-EPP-18 Rev 16

ATTACHMENT 2: EMERGENCY ANNOUNCEMENT DATE:

TIME:

INSTRUCTIONS: (check boxes to select appropriate announcement,consider crossing out rows not used)

1. PLACE GAITRONICS IN MERGE.

2. SOUND THE APPROPRIATE ALARM:

Station alarm for 10 seconds.

Evacuation Alarm for 10 seconds. (When an^ evacuation is being ordered)

3. ANNOUNCE ONLY THOSE ITEMS CHECKED: (Provide short description of the reason for classification, not the whole EAL) 0 a. 'Mention. Attention all personnel. This is 0 a drill an actual emergency Nine Mile Point 0 Unit I is experiencing:

Unit 2 is experiencing:

I, I!

"An Unusual Event due to "AnAlert emergency condition due to 11 I,

"A Site Area Emergency due to 0 "A General Emergency due to I,

b. If this is the first announcement for an Alert or hiaher. then alwavs add

- - Response Oraanization personnel are to report to their Emergency

'Yll Emewencv I - - Response facilities and card In."

c3 4. FOR A CREDIBLE INSIDER SECURITY THREAT, ADD (Only do step 4 once) 0 a. Secure all non-essential activities in vital areas, the two person line of sight vital area access rules are now in effel3.

5. FOR A LOCAL AREA EVACUATION, ADD 0 a. ' I n evacuation of:

is being ordered due to:

All personnel are to leave the (Unit 1/21 (area)staying clear of and report to

6. FOR ACCOUNTABILITY WITHOUT EVACUATION, ADD (only use with 4 above if evacuation unsafe and only do step 6 once.)

a. 'Iccountabilityis being performedin the Protected Area. All personnel shall report to an onsite assembly area, cxd in ar remain in the area until furthernotice."

7. FOR A PROTECTED AREA EVACUATION, ADD (Only do step 7 once) 0 a. "All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building.

and remain at this location until furthernotice".

-CONTINUED NEXT PAGE---

Page 10 EPIP-EPP-18 Rev 16

ATTACHMENT2 (Cont)

EMERGENCYANNOUNCEMENT

j. FOR AN EXCLUSION AREA EVACUATION. ADD (Only do step 8 once) 3 a. 'All personnel not assigned emergency response dul'ies shall evacuate the Nine Mile Point Exclusion Area immediately and report to:" (select appropriate)

1. "Offsite Assembly Area located on Howard Road in Volney, Maps may be obtained from security as you exit.'

OR 0 2. (provide other location as appropriate)

OR

3. "Home" 7 b. IF NECESSARY ADD:

(If radioactive release is in progress, then obtain plume direction from Chem Tech and check appropriate box below) 0 Personnel are to leave the area heading west towards Oswego then turn south.

Personnel are to leave the area heading south as soon as possible.

n (Detail other directions as appropriate)

3. IF APPROPRIATE, ADD: (Only do step 9 once)

D a. "Personnelin protective clothing should" (select appropriate):

17 1. "leave the area removing PCs as indicated at the step off pad."

2. "leave the area immediately and obtain Radiation Protection assistance at the access control point.

10. IF APPROPRIATE, ADD:

17 a. "There is no eating, drinking, or smoking within the protected area until further notice. "

0 b. (Only done if "IOa"has been done) Eating, drinking, smoking are now permitted within the Protected Area.

11. ALWAYS ADD:

0 "I repeat this is a drill. "

17 "I repeat this is an actual emergency. "

12. Repeat the alarm and entire announcement so that all specified steps of the specific announcement are made 2 (lwo) times.

13. Leave GAltronics in merge mode for the duration of the event.

14. Upon completion return this attachment to the EP Dept.

Page I 1 EPIP-EPP-18 Rev 16

Cl State Emergency I3 Oswego County 0 JA Fitzpatrick 0 Unaffected NMP Notification #

Communications Center Warning Point Power Plant Unit (SE(

Step Step Changed 1.

J 2.

3.

J 4.

5.

6.

J

7. UNIT EAL# Brief event description and other significant information: ( if necessary. Do not repeat EAL description)

I 8.

2 UNIT I

EAL#

Reactor Status:

I

-Unit 1: w p e r a t i n g 6. Shutdown (date) at (time - 24 hr clock) -

Unit 2: k Operating @Shutdown A. Elevated wind speed 1L

9. at 200 ft A. Elevated wind direction (from) at 200 ft.

IO.

11.

12.

Stabilitv Class: A Reported by: (Communicator name)

B C

- at Tel. No. (315)

ASK: Does Oswego County or New York State need further clarification on any information?

. (provide as appropriate) THEN: This is the end of the message, standby for verification roll call.

Check those involved 0 State Emergency 0 Oswego County 0 JA Fitzpatrick I3 Unaffected IVMP Unit in verification roll call CommunicationsCenter Warning Point Power Plant (time - 24 hr clock)

L&

THEN STATE: Nine Mile Point out at time:

Approved by: (SM/ED or ED/RM):

Print name: Signature:

Page 11 EP I P-EPP-20 Rev 21

AlTACHMENT 1A INSTRUCTIONS COMPLETING THE NOTIFICATION FACT SHEET PART 1 - Sheet 2 of 5 NOTE: 1. Complete all applicable sections.

2. For all updates (all notifications except the initial), check the box or boxes that have changed from the last notification.

BLOCK # INSTRUCTIONS

1. Communications Aide completes this row using date and time that number was dialed (A then *).

2. Indicate actual emergency or exercise (drill) by circling as appropriate.

3. indicate by circling as appropriate the:

A-D Classification Level, or E. If event is terminated, or F. Other

4. Indicate the date and time (24 hr clock / military time) the event w a s classified.

5. Indicate the status of any releases of radioactive materials by circling as appropriate, request Chemistry Technician srovide release information then indicate:

NOTE: This section applies to a release of radioactive materials that took place DUE to t h e classified event. IF a radioactive material release is taking place and it is unknown if it is related to the event, THEN a s s u m e the releEse is the result of the event A. No Release: Circle this selection if there is no release related to t h e declared event.

B. Release below federally aDDrOVed oDeratina limits (ODCM) Circle this selection if a release is in progress due to the event AND the release rate h a s been determined (by any means available) to NOT exceed ODCM [CI] Indicate using check box if to water or to atmosphere.

C. Release above federallv amroved operatinu limits (ODCMLCircle this selection if a release is in progress due to the event AND the release rate has been determined (by any means available) to exceed ODCM. [Cl] Indicate using check box if tci water or to atmosphere.

D. Unmonitored release recwirino evaluation: Circle this selection if evidence exists of a release from a pathway from which a release cannot be readily determined (examples: Emergency Condenser vents, steam or air passing blowocrt panels, Rx Bldg pressurized)

6. Indicate Protective Action Recommendations by circling as appropriate:

A. No need for protective actions B. Evacuate (indicate appropriate ERPAs as recommended by Dose assessment Advisor/ODAM) and implement the KI Plai

-for the following ERPAs and Shelter all remaining ERPAs. Circle the appropriate ERPAs

7. Write the EAL # that the event w a s classified as, in the box provided for Item #7. If a site event, place the number nearest the Unit making the call. If each unit is declaring a n emergency indicate the appropriate EAL next to the specific unit nuriber. Under

- Additional Information - see Notes below for examplesldirections for information that should be provided:

NOTES:

0 Do not repeat the EAL description here.

Provide other conditions if present that could have a n effect on future classifications / event or termination prognosis Put other EALs that amplify the present plant status, do riot write in all applicable EALs, only those that may impact present conditions. Other units status may be indicated here.

If the EAL requires no additional explanation, the Additional Information section should b e left blank.

8. Provide reactor status at both units. If unit is shutdown (per EOP definition), provide date and time of shutdown.

Each unit status should be provided regardless of a n emergency h a s been declared at the opposite unit or not.

NOTES: 1. Meteorological Data to be recorded on the IPart I Notification Fact Sheet is the 15 minute average data in accordance with EPIP-EPP-08.

2. IF meteorological data is not available for the initial notification, then indicate LTR in that data field.

9. Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record.

10. Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record.

11. Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record. (Use elevated Stability class)

12. Communice:rons Aide completes this row listing name and t h e ccrnmercial telephone they use.

THEN: Sign the Part 1 Notification Fact Sheet.

AND: Provide to Communications Aide.

For termination of Lxsual Events only, 4

1. Complete Part I Notification Fact S h e e t (Attachment IA) ,through Line 4. Indicate date/time of termination on line 4 and:

a. Sign where appropriate

b. Provide to the Communications Aide Page 12 EPI P-EPP-20 n-..- 4

ATTACHMENT 1: INITIAL DOSE ASSESSMENT AND PROTECTIVE ACTIONS Has e GENERAL

- h . r D P C L I P .---

I the following ERPAs Measure the dose Advise t h f SM that rate at plume conditions for a (Pan 1 NFS Seleclion 6 C) centerline as close I General Emergency have

, None, proceed to next box been met boundary as N0 1

I I

f??i 12 miles around and 5 miles downwind (except for sheltered ERPAs from Y

monrtor plant.

previous step) radiologicaland AND meteorological Implement the KI plan conditions AND Advise the remainder of the EPZ t o go indoors and listen to EAS (Pari 1 NFS Selection 6 8 )

r.;1 Reevaluate PARS Perform refined dose assessment (1) Use this formula ifrelease has both a ground and elevated component:

Ground Release Rate ( C k ) Elevated Release Rate ( C k )

+ IF 2 1, A General Emergency Exists I Table 1.1 Ground Release Rate (CVs)

Table 1.1Elevated Release Rate (CVs)

I I (2) When to suspect an unmonitored release

- (U1) Emergency Condenser tube rupture

- TB overpressure due to significant steam leak

- Steam or coolant release outside Primary Containment and Rx Bldg is positive Page 8 E PI P-EPP-08 Rev 19

ATTACHMENT 1: INITIAL DOSE ASSESSMENT AND PROTECTIVE ACTIONS TABLE 1.1 GENERAL EMERGENCY RELEASE RATES 1 3,

- -r (rnilh) A I BIC I ElFlG Windspeed (milh)

I I A l Stability Class BIC I D I 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 10-13 7692 2083 1388 14-17 10753 1075 500 164 14-17 11494 2857 1818 22'73 i i i i I I I I 18-21

_ _ II 13514 I 1389 I 667 1 213 18-21 14286 3704 2273 2 7 7 8

>21 16393 I

1667 I

833 I

256 >21 i 17241 i 4348 i 2632 i 3 2 g 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 EPIP-EPP-08 Rev 19

v t e Letter Sequence Other
TAC:U01778, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML083110428, ML083110457, ML083110465, ML083580222
MONTHYEAR2008-09-23 [Table View]

ML083110428

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