Text

Initial Submittal of the Administrative Jpms for the Examination - Jan/Feb 2003
	ML030780143
Person / Time
Site:	Perry
Issue date:	01/27/2003
From:	Pierson J; FirstEnergy Nuclear Operating Co
To:	; NRC/RGN-III
References
	50-440/03-301 50-440/03-301
	Download: ML030780143 (115)
	v • d • e

INITIAL SUBMITTAL OF THE ADMINISTRATIVE JPMS FOR THE PERRY EXAMINATION - JAN/FEB 2003

Appendix C Job Performance Measure Form ES-C-I Worksheet Perry Evaluate Proposed Work Schedule Against Established Task No:

JPM No:

299-893-03-01 2003 NRC RO A. L.a Overtime Guidelines K/A

Reference:

2.1.2 Method of testing Simulated Performance Classroom NRC Examiner:

N/A Date:

Actual Performance Simulator Plant Task Standard:

Candidate determines that he cannot work the proposed overtime without additional authorization (i.e., an approved Technical Specification Overtime Deviation Request).

Required Materials:

NOP-LP-1002, Rev 0 General

References:

NOP-LP-1002, Rev 0 Time Critical Task:

Validation Time:

NO 10 minutes READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

The plant is operating at 100% power. Operations Section shift manning is being severely affected due to a flu epidemic. All healthy licensed operators are being scheduled to work extra hours in order to cover shift vacancies.

Listed below is your proposed Work Schedule for the next 10 days.

Sun Mon Tue Wed Thu Fri Initiating Cue:

Sat Sun Mon Tue Off Off 12-24 12-24 12-24 12-24 16-24 06-16 Off 08-16 Note: All work hours shown exclude turnover time.

As a licensed operator, determine if you can work the proposed overtime without any additional authorization.

NUREG 1021, Revision 8, Supplement 1 Facility:

Task

Title:

Examinee:

Facility Evaluator:

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Note: Ensure a copy of NOP-LP-1002, Fitness For Duty Program, is available for use by the Candidate.

Performance Step:

The following guidelines are applicable to personnel performing 4.14.3 safety-related functions (e.g., licensed Senior Reactor Operators, Reactor Operators, Health Physicists, Auxiliary Operators, Perry Plant Operators, Perry Plant Attendants and Key Maintenance Personnel).

Overtime Deviation shall be controlled as specified in each plant's licensing documents, and may be supplemented as directed by site management.

1. An individual should not work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time).

2. An individual should not work 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 period, 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, or 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period (all excluding shift turnover time).

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods. (Shift turnover time should not be part of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break period.)

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift or crew.

5. The crew performing fuel loading operations should not normally be expected to work more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months out of each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period when scheduled for consecutive daily duty.

Standard:

Determines that he will exceed Guideline #3 for his proposed Sat /

Sun work schedule (a break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods).

Determines that he cannot work the proposed overtime without additional authorization (a Technical Specification Overtime Deviation Request is requested by his Supervisor and authorized by the Plant Manager or his designees).

Comment:

Terminating Cue:

When the Candidate has determined that he cannot work the proposed overtime without additional authorization, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I

Appendix C Page 3 of 4 Form ES-C-I VERIFICATION OF COMPLETION Job Performance Measure No.

2003 NRC RO A. L.a Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

N/A Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response

Result:

SAT OR UNSAT Examiner's Signature and Date:

NUREG 1021, Revision 8, Supplement I

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The plant is operating at 100% power. Operations Section shift manning is being severely affected due to a flu epidemic. All healthy licensed operators are being scheduled to work extra hours in order to cover shift vacancies. Listed below is your proposed Work Schedule for the next 10 days.

Sun Mon Tue Wed Thu Fri Sat Sun Mon Tue Off Off 12-24 12-24 12-24 12-24 16-24 06-16 Off 08-16 Note: All work hours shown exclude turnover time.

INITIATING CUE:

As a licensed operator, determine if you can work the proposed overtime without any additional authorization.

NUREG 1021, Revision 8, Supplement I

FENOC Procedure Number:

NOP-LP-1 002

Title:

Use Category:

Fitness For Duty Program General Skill Reference Revision:

Change:

Page 00 N/A 31 of 36 4.14 Overtime Guidelines 4.14.1 Plant staffing shall be such that adequate coverage of operating and key maintenance activities are maintained without the routine heavy use of overtime. The objective of the controls over the use of overtime is to assure that, to the extent practicable, personnel are not assigned to work activities while in a fatigued condition that could significantly reduce their mental alertness or their decision making capability and potentially create a Fitness for Duty concern.

4.14.2 The norm is for personnel work a 40-hour week while the plant is operating.

In the event that substantial amounts of overtime are required for unforeseen problems, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, the overtime guidelines shall be followed.

4.14.3 The following guidelines are applicable to personnel performing safety-related functions (e.g., licensed Senior Reactor Operators, Reactor Operators, Health Physicists, Auxiliary Operators, Perry Plant Operators, Perry Plant Attendants and Key Maintenance Personnel). Overtime Deviation shall be controlled as specified in each plant's licensing documents, and may be supplemented as directed by site management.

1.

An individual should not work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time).

2.

An individual should not work 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 period, 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, or 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period (all excluding shift turnover time).

3.

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods.

(Shift turnover time should not be part of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break period.)

4.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift or crew.

5.

The crew performing fuel loading operations should not normally be expected to work more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months out of each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period when scheduled for consecutive daily duty.

FENOC Procedure Number:

NOP-LP-1 002

Title:

Use Category:

Fitness For Duty Program General Skill Reference Revision:

Change:

Page 00 N/A 32 of 36 4.14.4 Deviation from the above guidelines shall normally not be required during times when the plant is operating and adequate shift coverage is available.

Exceptions to this policy may include a Limiting Condition for Operation (LCO), Emergency Plan activation or callout, or other significant need to maintain safe plant operation, to maintain shift compliment, or maintain production capability.

NOTE An electronic database version of the forms may be used as applicable to each site's overtime request program.

4.14.5 Deviations from the overtime guidelines are normally requested by the immediate supervisor and authorized by the Plant Manager or his designees (or by higher levels of management) using the Technical Specification Overtime Deviation Request (PNPP No. 7699) at the Perry Plant or the Overtime Deviation Request at DBNPS, DB-0047. Overtime deviation requests should not be completed significantly in advance of the hours to be worked.

4.14.6 Supervisors requesting overtime deviation must be familiar with the condition of the individual involved to ensure that the additional overtime hours can be safely worked.

4.14.7 The Section Manager responsible for personnel who perform safety-related functions; (e.g., Senior Reactor Operators, Reactor Operators, Auxiliary Operators, Perry Plant Operators, Perry Plant Attendants, Health Physics technicians, and Key Maintenance Personnel), shall maintain a method by which the overtime hours of an individual may be compared to the overtime guidelines.

4.14.8 The Plant Manager or his designees shall review individual overtime on a monthly basis to ensure that excessive hours have not been assigned and that routine deviation from the overtime guidelines is not authorized.

TECHNICAL SPECIFICATION OVERTIME DEVIATION REQUEST DEPTISECTION PNPP No. 7699 Rev. 9/27/00 DEVIATION CODES:

1 - MORE THAN 16 HRS STRAIGHT 3-MORE THAN 24 HRS IN 48 HRS 5-LESS THAN 8 HR BREAK BETWEEN ASSIGNMENTS 2 - MORE THAN 16 HRS IN 24 HRS 4 - MORE THAN 72 HRS IN 7 DAYS (CODES 01 -04 EXCLUDE SHIFT TURNOVER TIME)

NAME SOCIAL SECURITY CODE START END DATE REASON No.

DATE Reason shall include as a minimum: 1) the specific work to be performed, 2) why other individuals cannot not be used and 3) why the work cannot be rescheduled. General statements such as "outage support" and "to meet the schedule" are not acceptable.

I I

Supervisors requesting an overtime deviation are signifying that they are familiar with the condition of the individual involved and that the individual's condition is such that the additional overtime hours can be safely worked.

REQUESTED BY GENERAL MANAGER/DIRECTOR APPROVAL

/

I Signature Date Section Signature Date I

I I

I

Appendix C Job Performance Measure Form ES-C-1 Worksheet Method of testing Simulated Performance Classroom Perry Determine the Effect(s) of Relay I E51A-K51 Removal Task No:

JPM No:

N/A 2003 NRC RO A. L.b NRC Examiner:

N/A Date:

Actual Performance Simulator Plant Task Standard:

Candidate determines that the removal of Relay I E5 IA-K51 will defeat the RCIC automatic suction transfer (i.e., prevent the automatic opening of RCIC Pump Suppression Pool Suction Isolation Valve, I E5 1 -F031, on low CST level or high SP level).

Required Materials:

Electrical Drawings - 208-075 Series General

References:

Electrical Drawings - 208-075 Series Time Critical Task:

Validation Time:

NO 20 minutes READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue:

The plant is operating at 100% power. The Reactor Core Isolation Cooling System (RCIC) is in the normal Standby Readiness lineup.

Agastat Relays has issued an industry-wide notice that has identified a specific batch of relays that were not built to design specifications.

Agastat Relays has recommended that these relays be replaced as soon as practicable. Perry has identified that currently installed Relay I E5 IA-K51 was part of this batch.

The Unit Supervisor directs you to determine the potential effect(s) on the RCIC System if Relay I E5 I A-K51 were to be removed with the plant in its current operating condition.

NUREG 1021, Revision 8, Supplement I Facility:

Task

Title:

K/A

Reference:

2.1.24 Examinee:

Facility Evaluator:

Appendix C Page 2 of 5 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Note: The Candidate will require access to the Plant Electrical (208) Drawings located either in the Simulator, TEC Reference Library, or the Unit 1 Control Room.

Performance Step: 1 Standard:

Using the Plant Electrical (208) Drawings, determine the potential effect(s) on the RCIC System if Relay I E51 A-K51 were removed with the plant in its current operating condition.

Determines that the removal of Relay I E5 I A-K51 will defeat the RCIC automatic suction transfer (i.e., prevent the automatic opening of RCIC Pump Suppression Pool Suction Isolation Valve, I E5 1-F031, on low CST level or high SP level).

NUREG 1021, Revision 8, Supplement I

Appendix C Page 3 of 5 Form ES-C-I PERFORMANCE INFORMATION Comment:

Detailed discussion of Relay I E5tA-K5I removal.

1. B208-075 Sh 02:

Locates Relay I E5 IA-K51 (in far-left column).

Determines relay is shown on Sh 04.

+ Determines relay contact T I-MI is shown on Sh 21 (for valve E51 -F03 I).

2.

B208-075 Sh 04 Line 25:

Identifies Relay I E5 IA-K5 1.

+ Determines relay is normally de-energized.

+ Determines relay would not energize on either a low CST level (K78) or high SP level (K79)

(B208-075 Sh 10 Lines 05 & 17).

Note: Relay K50 is normally de-energized, therefore, relay contact MI-RI is normally closed.

3. B208-075 Sh 21 Line 09:

Identifies Relay IE51A-K51 contact MI-TI.

Determines contact would not close.

Determines RCIC Pump Suppression Pool Suction Isolation Valve, 1 E5 I -F03 1, would not automatically open if either a low CST level or high SP level condition were to occur.

Note: It is not critical for the Candidate to determine the Operability of the RCIC System in accordance with Technical Specifications.

Terminating Cue:

When the Candidate has determined that the RCIC automatic suction transfer has been defeated, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement I

Form ES-C-1 Question Documentation:

Question:

Response

Result:

SAT OR UNSAT Examiner's Signature and Date:

NUREG 1021, Revision 8, Supplement I Appendix C Page 4 of 5 VERIFICATION OF COMPLETION Job Performance Measure No.

2003 NRC RO A. 1.b Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

N/A Number of Attempts:

Time to complete:

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The plant is operating at 100% power. The Reactor Core Isolation Cooling System (RCIC) is in the normal Standby Readiness lineup. Agastat Relays has issued an industry-wide notice that has identified a specific batch of relays that were not built to design specifications. Agastat Relays has recommended that these relays be replaced as soon as practicable. Perry has identified that currently installed Relay I E5 IA-K5 I was part of this batch.

INITIATING CUE:

The Unit Supervisor directs you to determine the potential effect(s) on the RCIC System if Relay I E5 I A-K51 were to be removed with the plant in its current operating condition.

NUREG 1021, Revision 8, Supplement I

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

Perry Perform Independent Verification of Tag Placement Task No:

JPM No:

299-655-03-01 299-574-03-01 2003 NRC RO A.2 2.2.13 NRC Examiner:

Date:

Method of testing Simulated Performance Classroom Task Standard:

Actual Performance Simulator Plant Candidate determines that valve P42-F295B was incorrectly closed and tagged. Notifies the Clearance Authority of the tagging discrepancy.

Required Materials:

NOP-OP-1001, Rev 0 Clearance PYI-P47-0027 (Copy for training only)

General

References:

NOP-OP-1001, Rev 0 Time Critical Task:

Validation Time:

NO 10 minutes READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue:

The plant is operating in MODE 1. The chilled water coils for Controlled Access and Misc. Equipment Areas HVAC System (CA&MEA) Supply Plenum M21-BO0IB has a 2 gpm leak. The chilled water coils are being isolated and tagged per Clearance PY I -P47-0027.

The initial placement of the Control Room tags has been completed.

The Unit Supervisor directs you, as a Reactor Operator, to perform the independent verification of the Control Room tag placement for Clearance PY 1 -P47-0027 in accordance with NOP-OP-1001.

NUREG 1021, Revision 8, Supplement I Examinee:

Facility Evaluator:

N/A

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Note: The Evaluator will role-play as the SRO / Clearance Authority for this Admin JPM.

Note: Hand the Candidate the Clearance for his review and independent verification of tag placement.

Note: The NOMS Clearance System will not be required / used for this JPM.

Note: Each Control Room clearance tag independent verification can be evaluated in any order and will be documented in separate Performance Steps.

Note: The following Performance Step is for Valve P47-F290B.

Performance Step:

Verify tags hung as follows:

4.10.2

1. For each tag, perform the following:

a.

Confirm that the proper component was selected by comparing the information placed oil the tag, the clearance and in-plant label. Abbreviated terms need not match exactly.

b.

Confirm the component in the specified position.

c.

Confirm the tag is securely fastened to the component in a visible location.

d.

Check Placement 2"d Verification for that tag on the clearance.

Standard:

For valve P47-F290B:

"* Determines that the component was properly selected by comparing the information placed on the tag. the clearance and in-plant label.

"* Confirms the component is in the specified position (closed).

"* Confirms the red tag is securely fastened to the valve control switch.

"* Checks Placement 2"(1 Verification for that tag oil the clearance.

Comment:

Note: It is not required for the Candidate to enter NOMS and electronically sign for Placement 2 "d Verification for that tag on the clearance.

Cue: Inform the Candidate that he will not be required to update NOMS for the Placement 2 nd Verification of tags.

NUREG 1021, Revision 8, Supplement I

Appendix C Page 3 of 6 Form ES-C-I PERFORMANCE INFORMATION Note: The following Performance Step is for Valve P47-F295B.

Performance Step:

Verify tags hung as follows:

4.10.2

1. For each tag, perform the following:

a.

Confirmn that the proper component was selected by comparing the information placed on the tag, the clearance and in-plant label. Abbreviated terms need not match exactly.

b.

Confirm the component in the specified position.

c. Confirm the tag is securely fastened to the component in a visible location.

d.

Check Placement 2 "" Verification for that tag on the clearance.

Standard:

For valve P47-F295B:

"* Determines that the component was not properly selected by comparing the information placed on the tag, the clearance and in-plant label.

Determines red tag was placed on the control switch for valve P42-F295B instead of the control switch for valve P47-F295B.

"* Confirms the component is not in the specified position (closed).

Determines valve P42-F295B was closed instead of valve P47-F295B.

"* Confirms the red tag is not securely fastened to the valve control switch.

Determines red tag was secured on the control switch for valve P42-F295B instead of the control switch for valve P47-F295B.

"* Does not check Placement 2 nd Verification for that tag on the clearance.

Comment:

NUREG 1021, Revision 8, Supplement I

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step:

4.9.2 Standard

Comment:

Correcting discrepancies:

If conflicts between clearances or technical problems arise, Then inform the Clearance Authority.

The Clearance Authority (SRO) is informed that the tag for valve P47-F295B was initially placed on the wrong valve (P42-F295B).

Does not remove the incorrectly placed tag on valve P42-F295B, reposition valve P42-F295B to open, close correct valve P47-F295B, and tag valve P47-F295B control switch.

Note: The Candidate is not allowed to correct the clearance discrepancy (as discussed in NOP-OP-1001). The clearance will have to be revised.

Terminating Cue:

When the Candidate completes the independent verification for the red tag for valve P27-F290B control switch and determines that the red tag for valve P27-F290B control switch was improperly placed and informs the Clearance Authority, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I

Form ES-C-I Question Documentation:

Question:

Response

Result:

SAT OR UNSAT Examiner's Signature and Date:

NUREG 1021, Revision 8, Supplement I Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Job Performance Measure No.

2003 NRC RO A.2 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

N/A Number of Attempts:

Time to complete:

Appendix C Page 6 of 6 Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS:

The plant is operating in MODE 1. The chilled water coils for Controlled Access and Misc. Equipment Areas HVAC System (CA&MEA) Supply Plenum M21-BOOIB has a 2 gpm leak. The chilled water coils are being isolated and tagged per Clearance PY I -P47-0027. The initial placement of the Control Room tags has been completed.

INITIATING CUE:

The Unit Supervisor directs you, as a Reactor Operator, to perform the independent verification of the Control Room tag placement for Clearance PY 1 -P47-0027 in accordance with NOP-OP-1001.

NUREG 1021, Revision 8, Supplement I

PY1-P47-0027 Perry Tagout PY-CYC-009 Equipment ID:

0M21 B0001 B

==

Description:==

Isolate Cooling Coils for Flushing and Leak Repairs Reason:

Results in Loss of P47 Chilled Water flow to CAA Cooling Coil 'B' and Computer Room Cooling Coil 'B' Hazards:

-lectrical Hot Work

-:ire Impairment (PAP-1914)

-CO Tracking (OAI-1 701)

-CO No.

ndependent Verification (PAP-0205)

DEO remporary Shielding (RPI-0122) 3hielding Req. No.

Temp. Mod or INFO Tags (PAP-1402/1404)

Tag No.

Other _

Number Equipment ID 03-000222-000 0M21BOO01B Status Irepared Description LEAN AND INSPECT COILS. REPAIR COIL LEAKAGE.

Description

ýrepared By User Apley, Marc Verification Date 01/14/2003 17:28 Reviewed eviewed By Apley, Marc 01/14/2003 17:32 Second Review Second Review By N/A 01/14/2003 17:32 Approved Approved By TESTER Baker 01/24/2002 20:32 Issued for Work Restoration Review Removal Authorized Clearance Closed Issued for Work By Restoration Review By Removal Authorized By Clearance Closed By 00/00/0000 00:00 00/00/0000 00:00 00/00/0000 00:00 01/24/2003 09:21

' Page I of I AINO asn DNINIVUI. dO0 Isolating Flow per Request - Suggest Shutdown of M21 B and M27 B HVAC Trains due to loss of Chilled Water Flow Work Required prior to Completion:

Attribute Attribute Description Value I

I 00/00/0000 00:00

Tag Hang List for PY1-P47-0027 Perry Tagout PY-CYC-009

, Equipment ID i

Equipment Equipment I

Description Location 60P47F0290B C/S ICCCW OUT FROM CAA CLG J0H13P0904 COIL B C/S 0P47F0290B DISC

-...... CCCW OUT FROM CAA CLG 0-CC-620-A/03 EF1CO9 - X COIL B DISC

,0P47F0290B CCCW OUT FROM CAA CLG 0-CC-679-B/03 COIL B 0)P47F0295B C/S CCCW IN TO CPA CLG COIL 0H13P0904 B C/S

'0P47F0295B DISC CCCW IN TO CAA CLG COIL O-CC-620-A/03 EFIC09-Y B DISC 0P47F0295B CCCW IN TO CPA CLG COIL O-CC-679-8/03 B

01/24/2003 09:21 Page 1 of 1 Notes FOR TRAINi USE ONLY

q~a, inmmw 41 0"lo

-:

,,d4'Atr4,.4h.

cg 1 Perry Tagout Tagout Red Danger Tag Tag Serial Number:

PY-CYC-009-05849 0P47F0290B CCCW OUT FROM CAA CLG COIL B O-CC-679-B/03 Position: TAGGED Perry Tagout Tagout Red Danger Tag Tag Serial Number:

PY-CYC-009-05852 0P47F0296B CCCW IN TO CAA CLG COIL B O-CC-679-B/03 Position: TAGGED DANGER Perry Tagout Tagout Red Danger Tag Tag Serial Number:

PY.CYC-009-05848 0P47F0290B DISC CCCW OUT FROM CAA CLG COIL B DISC O-CC-620-A103 EF1C09-X Position: OFF Perry Tagout Tagout Red Danger Tag Tag Serial Number:

PY-CYC-009-05851 0P47F0296B DISC CCCW IN TO CAA CLG COIL B DISC O-CC-620-A/03 EFIC09 - Y Position: OFF I

41-7 rx

.Ik.L g*

Iw' "

A DO NOT OPERATE SilDA1*NGER DONTOPRT

NUCLEAR OPERATING ADMINISTRATIVE PROCEDURE Procedure Number:

NOP-OP-1001

Title:

Use Category:

Clearance/Tagging Program General Skill Reference Revision:

Page 0

11 of 43 4.3.9 Grounds

1.

IF a grounding device is to be installed, THEN it shall be tracked by one of the following:

Clearance (tagged point)

Clearance (non-tagged point)

2.

IF a bus is to be grounded, THEN all electrical feeds to that bus shall be tagged prior to grounding.

4.3.10 Mechanical Systems

1.

IF preparing a Clearance on a mechanical system required to be depressurized or drained, THEN identify the method for depressurizing or draining.

2.

IF it is necessary to use a check valve as a Clearance boundary, THEN it shall be designated as an Exceptional Clearance.

3.

IF tagging a heat exchanger, THEN consider isolating, venting and tagging both process sides prior to opening for maintenance.

4.3.11 Manual Valve Positioning as Clearance Boundaries

1.

IF tagging manual valves, which have remote operators (reach rods), THEN only the remote operating handle is normally tagged for ALARA reasons.

4.3.12 Motor Operated Valves (MOV's) as Clearance Boundaries

1.

IF tagging motor operated valves as isolation points, THEN the following apply:

The tag for either the control switch (preferably) or the handwheel shall provide the required valve position.

IF the control panel switch is tagged with the required valve position (e.g., open or close), THEN the tag on the valve handwheel should not designate a specific position.

Verify position of the valve using one of the following:

Remote electrical position indicator Process parameters

NUCLEAR OPERATING ADMINISTRATIVE PROCEDURE Procedure Number:

NOP-OP-1001

Title:

Use Category:

Clearance/Tagging Program General Skill Reference Revision:

Page 1

0 12 of 43 Local position indication Manually verify valve positioned (least preferred)

The normal sequence of applying tags is:

1)

Position the component using its control switch.

2)

Hang tag with the required position (i.e., open or closed), on the control panel switch.

3)

Verify valve position by control panel indication.

4)

Tag open motor breakers.

5)

Tag local control switches.

6)

Tag valve handwheel.

4.3.13 Pneumatic Valves as Clearance Boundaries

1.

Fail closed pneumatic valves used as tagging boundaries shall be tagged as follows:

Remove the motive force by either isolating the air supply (if desired vent off the actuator or regulator) or deenergizing the air solenoid valve.

0 Place a Danger Tag on the actuator.

2.

IF fail open pneumatic valves are capable of being blocked closed by a manual actuator or a stem collar locking device, THEN they may be used for tagging boundaries.

WARNING Some types of air operated valves will open due to downstream system pressure. When required as a boundary they must either be blocked closed or downstream pressure prevented from exceeding the lift pressure.

NUCLEAR OPERATING ADMINISTRATIVE PROCEDURE Procedure Number:

NOP-OP-1001

Title:

Use Category:

Clearance/Tagging Program General Skill Reference Revision:

Page 0

17 of 43 4.7 Work Group Review 4.7.1 The Clearance Holder or designee shall review the information on the following screens:

0 Clearance Detail 0

Clearance Tags 0

Work Documents 4.7.2 Verify the Clearance provides the following:

Adequate boundaries The correct job information IF any hazards exist that the Clearance does not provide protection from, THEN verify it is identified as an Exceptional Clearance (Refer to Attachment 1 for examples of when a Clearance shall be identified as an Exceptional Clearance).

4.7.3 IF the Clearance requires any changes, THEN inform the Clearance Preparer/Reviewer and resolve.

4.8 Authorization 4.8.1 The Clearance Authority shall evaluate the Clearance and current plant status to verify:

0 The notes and cautions are understood.

No adverse impact on current plant status will occur.

Required redundant equipment is verified operable.

Refer to the Clearance Attributes screen and document initiation of any required items.

0 The sequence for placement is correct.

0 Are there potential hazards during hanging.

4.8.2 Approve the Clearance.

4.9 Tag Placement 4.9.1 General Requirements Review the Clearance Cover Sheet, Tag Hang list, and Tags for applicable directions prior to positioning components.

NUCLEAR OPERATING ADMINISTRATIVE PROCEDURE Procedure Number:

NOP-OP-1001

Title:

Use Category:

Clearance/Tagging Program General Skill Reference Revision:

Page 1_0 1

18 of 43 0

Position components and place tags in the specified sequence.

Component positions may be verified by utilizing the position on danger tags currently hung.

4.9.2 Correcting Discrepancies Minor discrepancies such as typos, changes in the tag placement order, and functionally equivalent terms (Valve vice VLV, etc.) may be clarified under verbal direction from the Clearance Authority.

IF conflicts between Clearances or technical problems arise, THEN inform the Clearance Authority.

The Clearance Authority shall ensure all discrepancies are resolved with the work group.

IF any changes to the Clearance are required, THEN refer to Clearance Revision, Section 4.19.

4.9.3 Hang tags as follows:

1.

For each tag, perform the following:

a.

Confirm that the proper component is selected by comparing the information on:

The tag The Clearance In-plant label Abbreviated terms need not match exactly.

b.

Verify the component in the specified position.

c.

Place the tag on the component in a secure manner and visible location.

2.

Update the computer tagging system for the placement of tags in the field.

3.

Return the Clearance to the Clearance Authority or independent verifier when completed.

NUCLEAR OPERATING ADMINISTRATIVE PROCEDURE Procedure Number:

NOP-OP-1001

Title:

Use Category:

Clearance/Tagging Program General Skill Reference Revision:

Page 1

0 19 of 43 4.10 Independent Verification of Tag Placement 4.10.1 General Requirements 0

Independent verification may be waived by the Clearance Authority based on ALARA concerns.

Independent verification shall be conducted in accordance with Station Procedures.

4.10.2 Verify tags hung as follows:

1.

For each tag, perform the following:

a.

Confirm that the proper component was selected by comparing the information on the tag, the Clearance and in-plant label. Abbreviated terms need not match exactly.

b.

Confirm the component in the specified position.

c.

Confirm the tag is securely fastened to the component in a visible location.

2.

Update the computer tagging system for the placement of tags in the field.

3.

Return the Clearance to the Clearance Authority.

4.11 Clearance Activation 4.11.1 The Clearance Authority shall verify:

All items required on the Clearance Attributes screen are performed.

0 All tag placements have been checked as required.

All required plant conditions have been established.

4.11.2 IF any new hazards (i.e., excess boundary leakage) are discovered or problems occur during hanging of the Clearance, THEN inform the work group.

)

P47 - Rev. 5

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Appendix C Job Performance Measure Form ES-C-1 Worksheet Perry Task No:

299-910-03-01 Simulated Performance Classroom Determine Dress Out Requirements for a Contaminated Area JPM No: 2003 NRC RO/SRO A.3 NRC Examiner:

N/A Date:

Actual Performance Simulator Plant Task Standard:

Required Materials:

General

References:

Time Critical Task:

Validation Time:

Candidate determines that he must wear Full Protective Clothing and a Discrete Particle Suit in order to enter the RWCU Heat Exchanger Room.

Radiation Work Permit (marked up copy)

Survey Map (marked up copy)

HPI-C0005, Rev. 7 PAP-0 114, Rev. 4 NO 15 minutes READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue:

The plant is operating at 100% power. There has been an increasing temperature trend in the Reactor Water Cleanup (RWCU) System Heat Exchanger Room over the past 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Operations Management has determined that entry into the room is required in order to confirm if any leakage exists, and to quantify the amount.

As a member of the Relief Crew, you have been assigned to enter the room to perform this activity.

Determine the protective clothing requirements for you to enter the RWCU Heat Exchanger Room.

NUREG 1021, Revision 8, Supplement I Facility:

Task

Title:

K/A

Reference:

2.3.4 Examinee

Facility Evaluator:

Method of testing

Perry Nuclear Power Plant RADIATION WORK PERMIT (RWP)

For Training Purposes Only Location: Containment 652' RWP Number: 03XXXX

==

Description:==

Leakage Inspection in RWCU Heat Exchanger Room This SRWP AUTHORIZES entry into the following areas:

IlX LHRAs Xl HRAs Xl RAs Xi ARAs IXl CAs IXl DPZs MWO Number: N/A

Contact:

0. P. Raitor Contact Phone Number: 5932 Work Code: OP Completion Date: 01-JAN-2004 Person-mrem Estimate: 0.5 Person-Hrs Estimate: 4 WORK AREA SURVEY Dose Rates: 3 - 30,000 mrem/hr.

Contamination Levels: <1000 - 150,000 dpm/100 cm2 DOSIMETRY REQUIREMENTS M-G DRD PEA-100 Telemetry TILD PROTECTIVE CLOTHING CA FULL PROTECTIVE CLOTHING DPZ Discrete Particle Suit RESPIRATORY PROTECTION EQUIPMENT Respirator Type: None WORKER INSTRUCTIONS

1.

A documented ALARA brief is required when entering the RWCU Heat Exchanger Room.

2. Locked High Radiation Area Door Guards are required for entries into Locked High Radiation AreasI ALARA NOTES

1. PEA-100s and Telemetry shall be used per direction of RP Supervision.

2.

MG Setpoints should be evaluated for each entry and changes documented in the Narrative Log.

GENERAL RP NOTES PREPARED BY:

Date:

v RP PLANNING

,j Date: -

y RP SUPERVISOR:

O Date:

PHP APPROVAL:

0/,

Date:

WORK SUPERVISOR: 61ý7 Date:

TERMINATED BY:

Date:

For Training Purposes Only A B-DAC calculation is required for ARA >1.0 DAC CONTINUOUS Radiation Protection Coverage is required for entries into work areas > or = 1000 mRem/hr.

A Radiation Protection Brief is required for all entries on this RWP.

MG Setpoints for dose rate are not to be set above 5000 mRem/hr.

RWP NUMBER RADIOLOGICAL SURVEY REPORT o1s-K-.,<y BUILDING CTMT SURVEY NUMBER Y Y, y._ x )<

ELEVATION AREA / ROOM / SYSTEM 652' Containment RWCU Heat Exchar PURPOSE AIR SAMPLE #1 p

N/A uCi/cc C

ON/A AIR SAMPLE #2 N/A uCi/cc p

N/A uCi/cc C

ON/A N/A uCi/cc all dose rates are in mrem/hr @ waist level unless otherwise noted.

All smears are < 1000 dpm/100 cm 2 p,y unless otherwise noted.

Legend:

O - Air Sample,O-Smear XXXXX - Boundary, ### - Direct Frisk

1-Contact/30cm Bkgd - Background MDA-Minimum Detectable Activity NDB-No Detectable Beta SOP - Step Off Pad CA - Contamination Area DPZ - Discrete Particle Zone ARA - Airborne Radioactivity Area RA - Radiation Area NRA - Neutron Radiation Area HRA - High Radiation Area LHRA - Locked High Radiation Area VHRA - Very High Radiation Area N - Neutronm - Alpha, B-Betay - Gamma Smear Smear dpm/1 00cn*

Location B-Y 2i 5oe

/

2-

'50P ty.

3I FLooQ

?oK I0 FLUOIZ 1OV-__

INSTRUMENTS USED SURVEY BY MODEL INSTRUMENT NUMBER CAL DUE DATE Ný,ME (Print)

SIDEDAT

-rC.TCI-g&T-LQ L-7 DD V 0-Z A, L-7 X-LY M/DY/1 REVIEWED BY

-'JI L7 -r-y-. K)

S*-

IS GAME (PT-t)

T.U..

DAT N /~ P,-'4~)-

/'A.4gz1jSC4 I

,T&/

I t- ý-=

A, V-_ -T"' S F F-,-- --r 1 0 'j

Appendix C Page 2 of 4 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Comment:

Performance Step: 2 Standard:

Comment:

Performance Step: 3 Standard:

Comment:

Locate the correct Radiation Work Permit (RWP) in order to determine the Radiation Protection Program requirements for the assigned task.

Locates the Specific RWP that allows entry into the RWCU Heat Exchanger Room for Leakage Inspection.

Cue: Provide Candidate with marked up RWP after he either shows or states that the RWPs are kept at the RRA entrance.

Locate the correct Survey Map in order to determine the contamination levels inside the RWCU Heat Exchanger Room.

Locates the Survey Map for the RWCU Heat Exchanger Room.

Cue: Provide Candidate with marked up Survey Map after he either shows or states that the Survey Maps are kept at the RRA entrance.

Determine the protective clothing requirements for the assigned job task.

Evaluates RWP and associated Survey Map, and determines that he must wear Full Protective Clothing and a Discrete Particle Suit in order to enter the RWCU Heat Exchanger Room.

Terminating Cue:

When the Candidate has determined that he must wear Full Protective Clothing and a Discrete Particle Suit, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I

Form ES-C-I Question Documentation:

Question:

Response

Result:

SAT OR UNSAT Examiner's Signature and Date:

NUREG 1021, Revision 8, Supplement I Appendix C Page 3 of 4 VERIFICATION OF COMPLETION Job Performance Measure No.

2003 NRC RO/SRO A.3 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

N/A Number of Attempts:

Time to complete:

Appendix C Page 4 of 4 Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS:

INITIATING CUE:

The plant is operating at 100% power. There has been an increasing temperature trend in the Reactor Water Cleanup (RWCU) System Heat Exchanger Room over the past 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Operations Management has determined that entry into the room is required in order to confirm if any leakage exists, and to quantify the amount.

As a member of the Relief Crew, you have been assigned to enter the room to perform this activity.

Determine the protective clothing requirements for you to enter the RWCU Heat Exchanger Room.

NUREG 1021, Revision 8, Supplement I

Appendix C Job Performance Measure Form ES-C-I Worksheet Perry Perform Site Accountability Actions for Control Room Staff Task No:

JPM No:

N/A 2003 NRC RO A.4 NRC Examiner:

N/A Date:

Actual Performance Simulator Plant Task Standard:

Required Materials:

General

References:

Time Critical Task:

Validation Time:

Candidate obtains temporary relief as the Licensed Operator 'At the Controls' and then locates the Emergency Personnel Accountability card reader located in either the Unit I or 2 Control Room and simulates inserting his keycard into the card reader.

EPI-B0005, Rev 6, PIC 7 PAP-0126, Rev 2, PLC 2 EPI-B0005, Rev 6, PIC 7 PAP-0126, Rev 2, PlC 2 NO 5 minutes READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue:

The plant is in MODE 3. You are the Licensed Operator 'At the Controls' when a Site Area Emergency is announced. In addition, the Emergency Coordinator has announced that site accountability is now in effect.

The Shift Manager directs you, as a member of the Control Room staff, to perform your action(s) for site accountability.

NUREG 1021, Revision 8, Supplement I Facility:

Task

Title:

K/A

Reference:

2.4.39 Examinee:

Facility Evaluator:

Method of testing Simulated Performance Classroom

Appendix C Page 2 of 5 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Note: The Evaluator will role-play as another licensed Reactor Operator for the Candidate.

Note: The Candidate may explain that he can give his keycard to another member of his crew who will then insert his keycard into the designated accountability card reader for him. If this occurs, then cue the Candidate that he is required to demonstrate the action(s) himself.

Performance Step:

The Licensed Operator 'At the Controls' may be temporarily 6.8.3.1 relieved for personal reasons by another licensed operator as long as a verbal turnover of applicable items below has occurred:

a.

The status of work in progress, with emphasis on unit/personnel safety items and safety related systems.

b. Any changes in the Unit status since shift turnover.

c.

The status of testing and evolutions that has changed since shift turnover.

d. Any alarms or equipment out-of-service that has changed since shift turnover.

Standard:

Obtains temporary relief from another licensed Reactor Operator in order to leave the Horseshoe Area.

Comment:

Cue: As another Reactor Operator on his crew, inform the Candidate that he is temporarily relieved.

Note: The Unit I Control Room Emergency Personnel Accountability card reader is located outside of the Horseshoe Area near the main entrance to the Unit I Control Room.

Note: Per PAP-0 126, Step 6.3.1, the Licensed Operator 'At the Controls' shall not leave the Horseshoe Area until relieved by another licensed operator or senior reactor operator, except as specified in 6.3.2.

Note: PAP-0 126, Step 6.3.2 does not allow the Licensed Operator

'At the Controls' to momentarily leave the Horseshoe Area without relief for the sole purpose of performing site accountability actions.

Note: This Step is not critical. If the Candidate does not obtain temporary relief, this would only be a violation of plant procedure (PAP-0126).

NUREG 1021, Revision 8, Supplement I

Appendix C Performance Step:

5.6.1.1 Standard:

Comment:

Page 3 of 5 Form ES-C-I PERFORMANCE INFORMATION Utilize Card Readers in either Unit I or 2 Control Rooms for accountability purposes.

Locates the Emergency Personnel Accountability card reader in either the Unit I or 2 Control Room.

Inserts (simulates) and then withdraws keycard into the designated accountability card reader.

Cue: The red light has blinked on the Accountability card reader.

Note: Control Room staff shall respond as outlined in Control Room Staff and General Site Accountability Actions (EPI-B0005, ).

Terminating Cue:

When the Candidate completes his actions to demonstrate Site Accountability, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 1

Form ES-C-I Question Documentation:

Question:

Response

Result:

SAT OR UNSAT Examiner's Signature and Date:

NUREG 1021, Revision 8, Supplement I Appendix C Page 4 of 5 VERIFICATION OF COMPLETION Job Performance Measure No.

2003 NRC RO A.4 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

N/A Number of Attempts:

Time to complete:

Appendix C Page 5 of 5 Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS:

The plant is in MODE 3. You are the Licensed Operator 'At the Controls' when a Site Area Emergency is announced. In addition, the Emergency Coordinator has announced that site accountability is now in effect.

INITIATING CUE:

The Shift Manager directs you, as a member of the Control Room staff, to perform your action(s) for site accountability.

NUREG 1021, Revision 8, Supplement I

PAP-0126 Page:

5 Rev.:

2 / C-2 6.1.3 In the event that the Shift Manager (SM) is incapacitated, the on shift Unit Supervisor (US) assumes the SM function.

In the extreme event that the US is incapacitated concurrently with the SM, then the senior on shift licensed Reactor Operator (RO) assumes the SM function.

In either case, action shall be taken immediately to inform plant management, Operations Manager or above.

Actions shall also be taken immediately to obtain replacement personnel.

6.1.4 An additional SRO or SRO Limited to Fuel Handling shall supervise core alterations and shall have no other concurrent duties or responsibilities.

6.1.5 The Operations Section will normally have a minimum of five operating shifts, plus two relief operators.

During each shift cycle, Operations Section personnel assigned to a shift should be available for off-the-job retraining for a period of up to one week.

6.2 Fire Brigade Staffing

6.2.1 The site Fire Brigade consists of a Fire Brigade Leader and four members as described in

<PAP-1910>, Fire Protection Program.

6.2.2 Fire brigade composition may be one less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of members, provided immediate action is taken to restore the fire brigade to minimum requirements.

This does not mean that a shift position can be unmanned upon shift change due to an on-coming member being late or absent.

6.2.3 Fire brigade members shall have no duties during a fire except those directly related to fire-fighting.

6.3 Control Room Staffing

6.3.1 One licensed operator is required to be at the controls in the Horseshoe Area while fuel is in the vessel.

The licensed operator at the controls shall not leave the Horseshoe Area until relieved by another licensed operator or senior licensed operator, except as specified in 6.3.2.

6.3.2 The licensed operator at the controls may momentarily leave the Horseshoe Area without relief in the event of an emergency affecting the safety of operation in order to verify receipt of an annunciator or to initiate corrective actions on back panels located within the Operations Area.

6.3.3 In addition to the requirement of 6.3.1, one senior licensed operator shall be in the Control Room at all times while the reactor is in MODE 1, 2, or 3.

PAP-0126 Page:

11 Rev.:

2 6.8.3 Relief of the Licensed Operator "At the Controls" NOTE:

The Unit Supervisor may relieve the Licensed Operator at the controls.

If the plant is in Mode 1, 2 or 3, another SRO licensed individual is required to be present in the Control Room to assume the duties of the Unit Supervisor.

1.

The Licensed Operator at the controls may be temporarily relieved for personal reasons by another licensed operator as long as a verbal turnover of applicable items below has occurred:

a.

The status of work in progress, with emphasis on unit/personnel safety items and safety related systems.

b.

Any changes in the Unit status since shift turnover.

c.

The status of testing and evolutions that has changed since shift turnover.

d.

Any alarms or equipment out-of-service that has changed since shift turnover.

2.

The Licensed Operator at the controls may be relieved for an extended period provided the requirements of 6.8.1 and 6.8.2 are met.

6.9 Operations Foreman Relief 6.9.1 Operations Foreman Relief Turnover Checklist (Attachment 4),

or similar form, is to be signed by both the on-coming and off-going Operations Foreman.

6.9.2 Operations Foreman Relief/Turnover Instructions:

1.

Before being relieved, the Off-Going Operations Foreman will check the appropriate boxes to indicate that the following Plant Equipment Rounds have been approved or reviewed and initialed:

a.

Outside

b.

BOP

c.

Nuclear Island (RRA/OUT)

d.

Aux Boiler

e.

Radwaste

2.

Just prior to being relieved, the off-going Operations Foreman will verify that all key rings are accounted for and are intact (welded) and check the appropriate box on the checklist.

Rev.:

2 I 1 CONTROL ROOM AREAS Page:

34 -

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EPI-B5 Page:

8 Rev.:

6 / C-4*

5.6 Emergency Response Organization (ERO)

Personnel Response 5.6.1 Control Room/Shift Staffing shall:

1.

Respond as outlined in Control Room Shift Staff and General Site Accountability actions (Attachment 3, Figure 1).

5.6.2 Technical Support Center (TSC) Staff shall:

1.

Use the TSC Hallway "accountability" card reader upon entering the TSC for accountability purposes.

2.

Log into and out of the TSC using the hallway Staffing Board, indicating location/destination upon leaving facility.

3.

Respond as outlined in TSC Staff Accountability Actions (Attachment 4, Figure 2),

when personnel accountability is initiated.

5.6.3 Operations Support Center (OSC)

Staff shall:

1.

Use the TSC Hallway "accountability" card reader upon responding to the OSC.

2.

Respond as outlined in OSC Staff Accountability Actions (Attachment 5, Figure 3),

when personnel accountability is initiated.

5.6.4 Emergency Operations Facility (EOF) Staff shall:

1.

Respond as outlined in EOF Staff Accountability Actions (Attachment 6, Figure 4).

5.6.5 Joint Public Information Center (JPIC) Staff shall:

1.

Respond as outlined in Attachment 3, Figure 1.

5.6.6 Plant management located within the Protected Area upon initiation of personnel accountability, who wish to remain onsite and are not required to staff an emergency facility, shall promptly utilize an accountability card reader in the Control Room or TSC to account for their presence onsite.

5.7 Non-ERO Personnel Response 5.7.1 Plant Personnel not assigned to ERO shall:

1.

Exit the Protected Area and Perry Plant Site using normal exiting procedures once accountability announcement is heard over the Plant PA, Exclusion Area Paging System or via another employee.

EPI-B5 Page:

4 Rev.:

6 / C-7 5.1.4 If the offsite monitoring/decontamination centers are being activated, direct the Administrative Assistant to notify the NRC, State of Ohio, and local counties on the next Follow-up Notification form (PNPP No.

7795) per <EPI-Bl>.

5.2 Shift Manager shall:

5.2.1 Perform the actions outlined in Section 5.1 if the TSC is not yet operational, and utilize TSC staff as they become available to accomplish the actions listed in Sections 5.2 thru 5.4.

5.2.2 Activate the applicable pre-recorded "Emergency" message (Attachment 1) on the Exclusion Area Paging (R53)

System every five (5) minutes until accountability is completed.

1.

Provide additional guidance, if required, to personnel evacuating the site, using the R53 PA feature, for the following:

designated evacuation routes due to a security contingency use of offsite monitoring and decontamination centers 5.2.3 Direct all Control Room staff and Plant Operators (POs) located in the Unit 2 Control Room, to promptly use the designated accountability card readers.

Plant management who are not currently staffing an emergency facility may utilize a Control Room accountability card reader in lieu of evacuation.

5.2.4 If not yet relocated to the OSC, verify the location and status of POs presently dispatched in-plant.

After the OSC is operational, shift personnel such as the Shift I&C/HP/Chemistry Technicians and Plant Operators (POs) will be accounted for through the OSC.

1.

Complete Personnel Accountability Checklist (PNPP No.

7957, )

to account for on-shift POs outside the Control Room, and forward to the CAS via the Secondary Alarm Station (SAS).

5.2.5 Obtain the number of unaccounted for people within the Protected Area from the CAS no later than 30 minutes after accountability was initiated.

Page:

12 / C-7 CONTROL ROOM/SHIFT STAFF & GENERAL SITE ACCOUNTABILITY GUIDELINES EPI-B5 ACCOUNTABILITY INITIATED Yes REPORT TO OSC FOR ES ACCOUNTABILITY PURPOSES NOTES: (1) Plant Management may utilize accountability card readers in the Control Room & TSC in lieu of Evacuating the Protected Area.

(2) Offsite Monitoring/Decon. Centers located at:

Mentor High School Football Stadium (Lake County)

Saybrook Elementary School (Ashtabula County)

Hambden Fire Department (Geauga County)

NF972 SHIFT MANAGER MUST VERIFY STATUS OF POs OUTSIDE CONTROL ROOM, & REPORT NAMES & BADGE NO. OF INDIVIDUALS TO THE SECONDARY ALARM STATION (SAS).

EPI-B5 Rev. :

6

Appendix C Job Performance Measure Form ES-C-I Worksheet Method of testing Simulated Performance Classroom Perry Evaluate Proposed Work Schedule Against Established Overtime Guidelines Task No:

JPM No:

343-710-03-02 299-892-03-01 2003 NRC SRO A. L.a NRC Examiner:

N/A Date:

Actual Performance Simulator Plant Task Standard:

Required Materials:

General

References:

Time Critical Task:

Validation Time:

Candidate determines that Fred can work the proposed overtime without additional authorization and either Bill or John cannot work the proposed overtime without additional authorization.

Candidate completes a Technical Specification Overtime Deviation Request for either Bill or John.

NOP-LP-1002, Rev 0 Access to Computer Workstation with Lotus Notes software (or hardcopy of Technical Specification Overtime Deviation Request Form 7699)

NOP-LP-1002, Rev 0 NO 15 minutes Facility:

Task

Title:

K/A

Reference:

2.1.2 Examinee

Facility Evaluator:

Appendix C Job Performance Measure Form ES-C-I Worksheet READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

The plant is operating at 100% power. You are the Unit Supervisor for your crew. Two (2) Reactor Operators from your crew are needed to work a 12-hour overtime assignment on Sunday (2/10) firom 0800 to 2000.

It is not expected that any of the Reactor Operators who work on Sunday will work the following Monday.

Listed below is the current work week schedule for the three (3)

Reactor Operators on your crew.

Sun Mon Tue Wed Thu Fri Sat 2/3 2/4 2/5 2/6 2/7 2/8 2/9 Bill Off 08-20 08-20 08-16 08-16 08-20 08-20 Fred Off John Off 08-16 08-20 08-20 08-16 08-16 08-16 08-20 08-16 08-20 08-20 off 08-24 Note: All work hours shown exclude turnover time.

Initiating Cue:

Determine which Reactor Operator(s) can work the proposed overtime without any additional authorization and complete any form(s) required in order to fill the two (2) overtime assignments.

4ri~werke /

- e tec-6ý-anr'c Ve TECHNICAL SPECIFICATION OVERTIME OEPT/SEC7IION DEVIATION REQUEST PNPPD/POS - Perry Operations Section PNPP No. 7699 Rev. 09/27/00 DEVIATION CODES:

1 - More than 16 hrs straight 4 - More than 72 hrs in 7 days 2 - More than 16 hrs in 24 hrs 5 - Less than 8 hr break between assignments 3 - More than 24 hrs in 48 hrs (Code 1-4 exclude shift turnover time)

Main Information :

1. Bill SSN:xxx-xx-xxxx CODE:4 START DATE:02/10/2003 END DATE:02/10/2003 REASON: Work additional hours due to flu epidemic.

2. John SSN:yyy-yy-yyyy CODE:3 START DATE:02/10/2003 END DATE:02/10/2003 REASON: Work additional hours due to flu epidemic.

Requestor's Comments:

Director's Comments:

Requestor:

Signature C,,,-61ca t JT6erz-1 General Manager/Director Approval:

/

Date Na-,ýe.- (f a 11 d, -C/,( e - 1, --, 6, " /,v ee Lt C

e 0 d

-,e, 0

" k4v /a -e,7 e t 4, -.ý,

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C,-,' A

., ['*0 Answer Key - Hard Copy DEPT/SECTION TECHNICAL SPECIFICATION OVERTIME DEVIATION REQUEST PNPPD/OPS PNPP No. 7699 Rev. 9/27/00 DEVIATION CODES:

I - MORE THAN 16 HRS STRAIGHT 3 - MORE THAN 24 HRS IN 48 HRS 5 - LESS THAN 8 HR BREAK BETWEEN ASSIGNMENTS 2-MORE THAN 16 HRS IN 24 HRS 4-MORE THAN 72 HRS IN 7 DAYS (CODES 01 -04 EXCLUDE SHIFT TURNOVER TIME)

NAME SOCIAL SECURITY CODE START END DATE REASON No.

DATE Reason shall include as a minimum: 1) the specific work to be performed, 2) why other individuals cannot not be used and 3) why the work cannot be rescheduled. General statements such as "outage support" and "to meet the schedule" are not acceptable.

Bill xxx-xx-xxxx 4

2/10/2003 1 2110/2003 Work additional hours due to flu epidemic.

I John I

yyy-yy-yyyy I

1 3

2/10/2003 211012003 Work additional hours due to flu epidemic.

I I

I Supervisors requesting an overtime deviation are signifying that they are familiar with the condition of the individual involved and that the individual's condition is such that the additional overtime hours can be safely worked.

REQUESTED BY GENERAL MANAGER/DIRECTOR APPROVAL Signature Date Section Signature Date I

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Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Note: This JPM is intended to be performed using the electronic database version of the Technical Specification Overtime Deviation Request (PNPP No. 7699) located in Lotus Notes. However, if the Candidate desires, he can complete a hardcopy of the form.

Note: Ensure a copy of NOP-LP-1002, Fitness For Duty Program, is available for use by the Candidate.

Note: Each Reactor Operator (Bill, Fred, and John) can be evaluated in any order and will be documented in separate Performance Steps.

Appendix C Page 5 of 12 Form ES-C-I PERFORMANCE INFORMATION Note: The following Performance Steps are for Bill.

Performance Step:

The following guidelines are applicable to personnel performing 4.14.3 safety-related functions (e.g., licensed Senior Reactor Operators, Reactor Operators, Health Physicists, Auxiliary Operators, Perry Plant Operators, Perry Plant Attendants and Key Maintenance Personnel).

Overtime Deviation shall be controlled as specified in each plant's licensing documents, and may be supplemented as directed by site management.

1. An individual should not work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time).

2. An individual should not work 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 period, 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, or 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period (all excluding shift turnover time).

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods. (Shift turnover time should not be part of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break period.)

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift or crew.

5. The crew performing fuel loading operations should not normally be expected to work more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months out of each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period when scheduled for consecutive daily duty.

Standard:

Determines that Bill will exceed Guideline #2 for his proposed work week schedule (an individual shall not work more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period).

Determines that Bill cannot work the proposed overtime without additional authorization (a Technical Specification Overtime Deviation Request is requested by his Supervisor and authorized by the Plant Manager or his designees).

Comment:

Appendix C Page 6 of 12 Form ES-C-I PERFORMANCE INFORMATION Note: The following Performance Step is only critical if the Candidate determines that Bill (not John) will be designated as the second Reactor Operator to work the proposed overtime on Sunday.

Note: Provide the Candidate with the following directions before he prepares the electronic version of the Technical Specification Overtime Deviation Request:

1. Use a fictitious Social Security Number for Bill.

2. Do not submit the completed Technical Specification Overtime Deviation Request for approval.

3. Print a copy of the completed Technical Specification Overtime Deviation Request.

4. Closeout the completed Technical Specification Overtime Deviation Request without saving the request.

5. Exit the Lotus Notes electronic database.

Performance Step:

Deviations from the overtime guidelines are normally requested by 4.14.5 the immediate supervisor and authorized by the Plant Manager or his designees using the Technical Specification Overtime Deviation Request (PNPP No. 7699).

Standard:

Using Lotus Notes, accesses the Overtime Deviation electronic database from the Perry Main menu on PY-NOTESO 1.

Properly completes the Technical Specification Overtime Deviation Request.

The following items are critical: Name (Bill), Code (4).

See attached Technical Specification Overtime Deviation Request Answer Key.

Comment:

Note: The 'Start Date' and 'End Date' blocks are not critical items because they are used for administrative purposes only.

As a minimum, the dates should both be 2/10/03, but they could include the entire time interval of the hours worked or limit exceeded.

Note: If the electronic database version of the form is not available, then provide the Candidate with a hardcopy of PNPP No. 7699.

Appendix C Page 7 of 12 Form ES-C-I PERFORMANCE INFORMATION Note: The following Performance Step is for Fred.

Performance Step:

The following guidelines are applicable to personnel performing 4.14.3 safety-related functions (e.g., licensed Senior Reactor Operators, Reactor Operators, Health Physicists, Auxiliary Operators, Perry Plant Operators, Perry Plant Attendants and Key Maintenance Personnel).

Overtime Deviation shall be controlled as specified in each plant's licensing documents, and may be supplemented as directed by site management.

1. An individual should not work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time).

2. An individual should not work 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 period, 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, or 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period (all excluding shift turnover time).

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods. (Shift turnover time should not be part of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break period.)

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift or crew.

5. The crew performing fuel loading operations should not normally be expected to work more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months out of each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period when scheduled for consecutive daily duty.

Standard:

Determines that Fred can work the proposed overtime without additional authorization.

Comment:

Note: Fred should be designated for I of the 2 proposed overtime assignments since he does not require additional authorization.

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION Note: The following Performance Steps are for John.

Performance Step:

The following guidelines are applicable to personnel performing 4.14.3 safety-related functions (e.g., licensed Senior Reactor Operators, Reactor Operators, Health Physicists, Auxiliary Operators, Perry Plant Operators, Perry Plant Attendants and Key Maintenance Personnel).

Overtime Deviation shall be controlled as specified in each plant's licensing documents, and may be supplemented as directed by site management.

1. An individual should not work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time).

2. An individual should not work 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 period, 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, or 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period (all excluding shift turnover time).

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods. (Shift turnover time should not be part of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break period.)

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift or crew.

5. The crew performing fuel loading operations should not normally be expected to work more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months out of each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period when scheduled for consecutive daily duty.

Standard:

Determines that John will exceed Guideline #2 for his proposed work week schedule (an individual shall not work more than 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).)

Determines that John cannot work the proposed overtime without additional authorization (a Technical Specification Overtime Deviation Request is requested by his Supervisor and authorized by the Plant Manager or his designees).

Comment:

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION Note: The following Performance Step is only critical if the Candidate determines that John (not Bill) will be designated as the second Reactor Operator to work the proposed overtime on Sunday.

Note: Provide the Candidate with the following directions before he prepares the electronic version of the Technical Specification Overtime Deviation Request:

1. Use a fictitious Social Security Number for John.

2. Do not submit the completed Technical Specification Overtime Deviation Request for approval.

3. Print a copy of the completed Technical Specification Overtime Deviation Request.

4. Closeout the completed Technical Specification Overtime Deviation Request without saving the request.

5. Exit the Lotus Notes electronic database.

Performance Step:

4.14.5 Standard:

Comment:

Deviations from the overtime guidelines are nonnally requested by the immediate supervisor and authorized by the Plant Manager or his designees using the Technical Specification Overtime Deviation Request (PNPP No. 7699).

Using Lotus Notes, accesses the Overtime Deviation electronic database from the Perry Main menu on PY-NOTESO 1.

Properly completes the Technical Specification Overtime Deviation Request.

0 The following items are critical: Name (John), Code (3).

See attached Technical Specification Overtime Deviation Request Answer Key.

Note: The 'Start Date' and 'End Date' blocks are not critical items because they are used for administrative purposes only.

As a minimum, the dates should both be 2/10/03, but they could include the entire time interval of the hours worked or limit exceeded.

Note: If the electronic database version of the form is not available, then provide the Candidate with a hardcopy of PNPP No. 7699.

Terminating Cue:

When the Candidate has determined that Fred can work the proposed overtime without additional authorization and either Bill or John cannot work the proposed overtime without additional authorization (and completes a Technical Specification Overtime Deviation Request for either Bill or John), the evaluation for this JPM is complete.

Appendix C Page 10 of 12 Form ES-C-1 Question Documentation:

Question:

Response

Result:

SAT OR UNSAT Examiner's Signature and Date:

Appendix C Page 10 of 12 VERIFICATION OF COMPLETION Job Performance Measure No.

2003 NRC SRO A. 1.a Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

N/A Number of Attempts:

Time to complete:

Appendix C Page 11 of 12 Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS:

The plant is operating at 100% power. You are the Unit Supervisor for your crew. Two (2) Reactor Operators from your crew are needed to work a 12-hour overtime assignment on Sunday (2/10) from 0800 to 2000.

It is not expected that any of the Reactor Operators who work on Sunday will work the following Monday.

Listed below is the current work week schedule for the three (3) Reactor Operators on your crew.

Sun Mon Tue Wed Thu Fri Sat 2/3 2/4 2/5 2/6 2/7 2/8 2/9 Bill Off 08-20 08-20 08-16 08-16 Fred Off John Off 08-16 08-20 08-20 08-16 08-20 08-16 08-20 08-20 08-20 08-20 08-16 08-16 off 08-24 Note: All work hours shown exclude turnover time.

INITIATING CUE:

Determine which Reactor Operator(s) can work the proposed overtime without any additional authorization and complete any form(s) required in order to fill the two (2) overtime assignments.

DEPT/SECTION TECHNICAL SPECIFICATION OVERTIME DEVIATION REQUEST PNPP No. 7699 Rev. 9/27/00 DEVIATION CODES:

1 - MORE THAN 16 HRS STRAIGHT 3 - MORE THAN 24 HRS IN 48 HRS 5-LESS THAN 8 HR BREAK BETWEEN ASSIGNMENTS 2 - MORE THAN 16 HRS IN 24 HRS 4 - MORE THAN 72 HRS IN 7 DAYS (CODES 01 -04 EXCLUDE SHIFT TURNOVER TIME)