Text

Draft - Section a Operating
	ML030220415
Person / Time
Site:	Beaver Valley
Issue date:	12/16/2002
From:	Hynes C; FirstEnergy Nuclear Operating Co
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-412/03-302 50-412/03-302
	Download: ML030220415 (107)
	v • d • e

ES-301 Administrative Topics Outline Form-ES-301-1 Facility:

FENOC BVPS Unit 2 Date of Examination:

12/2002 Examination Level:

RO Operating Test Number:

2002-01 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 2.1.7 (3.7)

Ability to evaluate plant performance and make operational Conduct of judgments based on operating characteristics, reactor behavior, Operations and instrument interpretation.

JPM:

Perform a QPTR Manual Calculation 2.1.18 (2.9) Ability to make accurate, clear, and concise logs, records, Conduct of status boards, and reports.

Operations JPM:

Complete Operating Logs A.2 2.2.12 (3.0)

Knowledge of surveillance procedures.

Equipment Control JPM:

Perform AC Sources Alignment Verification A.3 2.3.10 (2.9)

Ability to perform procedures to reduce excessive levels of Radiation radiation and guard against personal exposure.

Control QUESTION: Give a set of conditions, specify actions when high dose rate is encountered.

2.3.1 (2.6)

Knowledge of 10CFR20 and related facility radiation control Radiation requirements.

Control QUESTION: Give plant conditions and a personal exposure history, calculate stay time.

A.4 2.4.29 (2.6) Knowledge of the emergency plan.

Emergency Preparedness QUESTION: List the ERO facilities activated.

2.4.39 (3.3)

Knowledge of RO's responsibilities during emergency plan Emergency implementation.

Preparedness Implntation.

QUESTION: Responsibilities during search and rescue operations.

NUREG-1021, Revision 8 BVPS-2 RO NRC Admin

ES-301 Administrative Topics Outline Form-ES-301-1 Facility:

FENOC BVPS Unit 2 Date of Examination:

12/2002 Examination Level:

SRO Operating Test Number:

2002-01 Administrative Describe method of evaluation:

Topic/Subject Description

1. ONE Administrative JPM, OR

2. TWO Administrative Questions A.1 2.1.7 (4.4)

Ability to evaluate plant performance and make operational Conduct of judgments based on operating characteristics, reactor behavior, Operations and instrument interpretation.

JPM:

Review a QPTR Manual Calculation 2.1.18 (3.0)

Ability to make accurate, clear, and concise logs, records, status Conduct of boards, and reports.

Operations JPM:

Review Operating Logs A.2 2.2.12 (3.4)

Knowledge of surveillance procedures.

Equipment JPM:

Review AC Sources Alignment Verification Control A.3 2.3.1 (3.0)

Knowledge of 10CFR20 and related facility radiation control Radiation requirements.

Control JPM:

Approve Emergency Exposure A.4 2.4.41 (4.1)

Knowledge of emergency action level thresholds and Emergency classifications.

Preparedness JPM:

Classify an EPP Event BVPS-2 SRO NRC Admin NUREG-1021, Revision 8

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

Task

Title:

K/A

Reference:

BVPS Unit 2 Perform a QPTR Manual Calculation 015000A1.04 (3.5/3.7) 015000A4.02 (3.9/3.9)

Task No.:

JPM No.:

2002 NRC Ala RO Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner Date:

X Simulator Actual Performance:

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The Unit is in Mode I at 80% power. The plant computer is NOT available.

QPTR calculation completed and compared to Acceptance Criteria.

Calculator 20ST-2.4A, Quadrant Power Tilt Ratio Manual Calculation, Rev. 4 20ST-2.4A, Rev. 4 QPTR Parameter Sheet The Unit Supervisor directs you to perform a QPTR manual calculation and report the results.

No 10 minutes NUREG 1021, Revision 8, Supplement I X

BVPS NRC Ala RO

Appendix C Page 2 of 5 PERFORMANCE INFORMATION Form ES-C-i 2002 NRC Ala RO (Denote Critical Steps with an asterisk)

NOTE:

The order of QPTR calculation does not have to follow the order of the procedure as long as the method of calculation is correct.

Performance Step: I Standard:

CUE:

Provide Candidate with a copy of 2OST-2.4A and QPTR Parameter Sheet.

Obtain upper and lower quadrant excore nuclear instrument detector outputs for each quadrant.

Locates detector current outputs and enters on Data Sheet 1.

Comment:

"Performance Step: 2 Standard:

Record the excore detector normalization factors.

Locates normalization factors and records their values on Data Sheet 1.

Comment:

Performance Step: 3 Standard:

Standard:

NOTE:

In the following steps, the Candidate should not be evaluated UNSAT for a math error only, as long as the method of calculation is correct.

Multiply each detector current reading by its normalization factor to obtain a corrected current.

Calculates corrected current.

Records the following for "Current (Cor.)":

N41A = 7.263 N41B = 7.363 N42A = 7.232 N42B = 6.575 N43A = 7.196 N43B = 7.906 N44A = 6.930 N44B = 7.056 Comment:

NUREG 1021, Revision 8, Supplement 1 Form ES-C-1 BVPS NRC Ala RO

Appendix C Page 3 of 5 PERFORMANCE INFORMATION 2002 NRC Ala RO (Denote Critical Steps with an asterisk)

Performance Step: 4 Standard:

Standard:

Determine average upper quadrant and average lower quadrant excore NI detector output.

Calculates average currents.

Records the following for "AVG":

Top Detectors = 7.155 Bottom Detectors = 7.250 Comment:

Performance Step: 5 "Standard:

Standard:

Divide each quadrant excore NI detector output by the appropriate (Upper or Lower) average NI detector output.

Calculates tilt ratios.

Records the following for "Tilt Ratio":

N41A = 1.015 N41B = 1.016 N42A = 1.011 N42B = 0.907 N43A = 1.006 N43B = 1.090 N44A = 0.969 N44B = 0.973 Comment:

Performance Step: 6 Standard:

Compare highest Quadrant Power Tilt Ratio to Acceptance Criteria.

Determines that the QPTR exceeds 1.02 on N43B (1.090).

Comment:

Terminating Cue:

When the Candidate reports that the QPTR does not meet the Acceptance Criteria, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 Form E_.-C.-1 BVPS NRC Ala RO

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC Ala RO Job Performance Measure No.:

2002 NRCAla RO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Tim, q to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement I BVPS NRC Ala RO

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC Ala RO INITIAL CONDITIONS:

The Unit is in Mode 1 at 80% power. The plant computer is NOT available.

INITIATING CUE:

The Unit Supervisor directs you to perform a QPTR manual calculation and report the results.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC Ala RO

A9.330B Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 2OST-2.4A Quadrant Power Tilt Ratio Manual Calculation Revision 4 Prepared by Date Pages Issued Effective Date W. K. Giffrow 09126101 1 through 14 Reviewed by Date Validated by Date F. J. Schaffner 09126/01 NIA OSC Meeting No.

Date Approved by Date OSC Not Required

._I

Table Of Contents I.

PURPOSE...................................................................................................................................

5 I1.

DISCUSSION...............................................................................................................................

5 II1. ACCEPTANCE CRITERIA..................................................................................................

5 IV.

EQUIPMENT AND MATERIALS.............................................................................................

5 V.

PRECAUTIONS AND LIMITATIONS......................................................................................

5 VI.

INITIAL CONDITIONS.................................................................................................................

5 VII.

INSTRUCTIONS..........................................................................................................................

8 VIII.

DATA SHEETS, TABLES, FIGURES AND ATTACHMENTS 10 DATA SHEET 1..................................................................................................................................

11 ATT ACHMENT A................................................................................................................................

12 IX.

REFERENCES..........................................................................................................................

13 Table Of Contents Beaver Valley Power Station Unit 2 20ST-2.4A Revision 4 Operating Surveillance Test FOR TRAINING USE ONLYPage 2 of 14 Quadrant Power Tilt Ratio Manual Calculation

Frequency: Woo Surveillance Requirements: 4.2.4.a, BVPS-2 Licensing Requirements IManual Required for Mode(s): 1o Date / Time Completed:

Performed in Mode(s): 1 Total Manhours:

TEST RESULTS: (Completed by Performer)

PERFORMED BY:

Name (Print)

Initial

('4or N/A) o Test Completed SATISFACTORY o

Problems Encountered (See Problem Sheet) o Unscheduled/partial OST (explain)

Reviewer Signature/Date STA Review

/

NSS Approval

/

COMMENTS: (Include Date and Initials) o Comments continued on Problem Sheet o Above 50% of rated thermal power.

on Required at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady-state operation when QPTR alarm is inoperable.

Beaver Valley Power Station Unit 2 20ST-2.4A Revision4 Operating Surveillance Test FOR TRAINING USE ONLYPage 3 of 14 Quadrant Power Tilt Ratio Manual Calculation

Beaver Valley Power Station Operating Surveillance Test FOR T Quadrant Power Tilt Ratio Manual Calculation Unit 2 2OST-2.4A USE Revision "RAINING USE ONLY Page4of 14 OST PROBLEM SHEET See Page and Step No. for problem description. See below for corrective action.

PAGE NO.

STEP NO.

DESCRIBE CORRECTIVE ACTION INITIALS DATE I

PURPOSE To determine by manual calculation the Quadrant Power Tilt Ratio (QPTR) and verify that it does not exceed the limit given in Technical Specification 3.2.4. This procedure may be entered from an AOP.

I1.

DISCUSSION The manual calculation of the Quadrant Power Tilt Ratio is performed as follows:

"* Prior to exceeding 50% power on a load increase.

"* Once every seven days when power is greater than 50% and the QPTR Monitor is OPERABLE, as determined by 20ST-2.4, "Quadrant Power Tilt Ratio Alarm Check".

"" Once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the QPTR Monitor is inoperable in accordance with the BVPS-2 Licensing Requirements Manual.

III.

ACCEPTANCE CRITERIA Note:

An exception to the Acceptance Criteria exists for physics testing (Tech. Spec.

3.10.2).

A.

Quadrant Power Tilt Ratio (QPTR) does not exceed 1.02 (Data Sheet 1) (T.S. 4.2.4.a).

IV.

EQUIPMENT AND MATERIALS A.

A digital voltmeter (DVM), if determined to be necessary during OST performance.

V.

PRECAUTIONS AND LIMITATIONS A.

Perform this OST every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with the QPTR alarm inoperable.

B.

If it is suspected that the meter indication on the power range drawers is erratic due to static in the meter face, a DVM should be used to determine current values. The DVM measurement should be taken at the test jacks on the front of the power range drawers.

VI.

INITIAL CONDITIONS A.

Plant Status Changes This procedure does not affect plant status.

B.

NSSIANSS Sign-on

1.

A QPTR determination is desired to verify conformance to Technical Specification 3.2.4.

Beaver Valley Power Station Unit 2 2OST-2.4A Revision 4 Operating Surveillance Test FOR TRAINING USE ONLYage 5 of 14 Quadrant Power Tilt Ratio Manual Calculation

CAUTION:

IF POWER IS - 75% AND ONE POWER RANGE HIGH NEUTRON FLUX CHANNEL INPUT TO QPTR IS INOPERABLE, QPTR MUST BE VERIFIED AT LEAST ONCE PER 12 HOURS IN ACCORDANCE WITH TECHNICAL SPECIFICATION SURVEILLANCE 4.2.4.b, USING 2RST-3.4, "INCORE ANALYSIS OF QPTR".

2.

If one power range high neutron flux channel input to QPTR is inoperable, AND thermal power < 75%, the remaining three power range high neutron flux channels may be used for calculating QPTR.

3.

No other tests of the power range channels are being performed during this OST.

4.

NSS/ANSS verifies the following:

Section VIA, Plant Status Changes, has been reviewed.

0 Requirements of Section VI.B, NSS/ANSS Sign-on have been verified.

0 Performance of this procedure is authorized.

DATE:

ITIME:

CURRENT PLANT MODE:

NSS/ANSS COMMENTS:

NSS I ANSS Signature C.

Reactor Operator Sign-on

1.

Reactor Operator performs the following:

Acknowledge performance of this procedure.

Reactor Operator Signature D.

Procedure Performer Initial Conditions

1.

Reactor power is being maintained at a steady-state value.

I Initial I Date Beaver Valley Power Station Unit 2 2OST-2.4A Revision 4 Operating Surveillance Test FOR TRAINING USE ONLYPage 6 of 14 Quadrant Power Tilt Ratio Manual Calculation

Beaver Valley Power Station Unit 2 20ST-2.4A TRAIINGUSE NLYRevision 4 Operating Surveillance Test FOR TRAINING USE ON Page 7 of 14 Quadrant Power Tilt Ratio Manual Calculation

2.

Operator(s) performing this procedure has reviewed this procedure.

I Initial I Date I

Initial / Date

Beaver Valley Power Station Unit 2 20ST-2.4A Revision 4 Operating Surveillance Test FOR TRAINING USE ONLY Page 8 of 14 Quadrant Power Tilt Ratio Manual Calculation VII.

INSTRUCTIONS A.

Test Preparation

1.

Record the power range detector QPTR normalization factors, found in the Reactor Engineering Data Book, Data Sheet 3 of 2RST-2.3, "Nuclear Power Range Calibration" OR Data Sheet 5 of 2RST-2.4, "Alignment of Excore Instrumentation for Startup After Reload" OR Data Sheet 3 of 2RST-2.9, "NIS Single Point Calibration" (NSS Office), on Data Sheet 1.

Initial I Date B.

QPTR Determination Note:

If one power range high neutron flux channel input to QPTR is inoperable, AND thermal power < 75%, the remaining three power range high neutron flux channels may be used for calculating QPTR. In this case, the entries on Data Sheet 1 for the OOS detector should be marked "N/A".

1.

Record detector current values for each of the power range detectors in the "Current (Uncor.)" column of Data Sheet 1, using either of the following methods:

a.

Detector current meters located on the power range drawers.

I Initial I Date Note:

If uncertainty exists in reading the current meters, a DVM should be used to obtain the current readings.

b.

Test jacks located below the meter faces using a DVM, in accordance with Attachment A.

I Initial I Date

2.

Multiply each of the detector current readings by its associated normalization factor AND Record the result in the "Current (Cor.)" column of Data Sheet 1.

I Initial I Date

Beaver Valley Power Station Unit 2 20ST-2.4A Revision 4 Operating Surveillance Test FOR TRAINING USE ONL age 9 of 14 Quadrant Power Tilt Ratio Manual Calculation

3.

Perform the following for the Upper Detectors on Data Sheet 1:

a.

Add the values in the "Current (Cor.)" column AND Record the result in the space marked "SUM".

i Initial I Date

b.

Divide the value in the "SUM" space by 4(3) AND Record the result in the space marked "AVG".

I Initial I Date

c.

Determine the Tilt Ratio for each of the upper detectors by dividing each value in the "Current (Cor.)" column by the value of "AVG" AND Record the results in the "Tilt Ratio" column.

I Initial I Date

4.

Perform the following for the Lower Detectors on Data Sheet 1:

a.

Add the values in the "Current (Cor.)" column AND Record the result in the space marked "SUM".

I Initial I Date

b.

Divide the value in the "SUM" space by 4(3) AND Record the result in the space marked "AVG".

I Initial I Date

c.

Determine the Tilt Ratio for each of the lower detectors by dividing each value in the "Current (Cor.)" column by the value of "AVG" AND Record the results in the "Tilt Ratio" column.

I Initial I Date

5.

If uncertainty exists with the calculated tilt values, Request the TILT map from the PCS (Computer Group Number GP048) AND Compare the map with the results of this OST.

I

"J Initial I Date

C. Test Completion

1.

Consult the Acceptance Criteria for acceptable performance.

I Initial / Date

2.

Inform the NSS or ANSS of the completion of this test.

I Initial / Date

3.

Complete the front cover sheet.

I Initial I Date VIII.

DATA SHEETS, TABLES, FIGURES AND ATTACHMENTS A.

Data Sheets

1.

Manual QPTR Calculation B.

Tables NONE C. Figures NONE D.

Attachments

1.

Use of DVM to Obtain Current Readings Beaver Valley Power Station Unit 2 20ST-2.4A Revision 4 Operating Surveillance Test FOR TRAINING USE ON10 of 14 Quadrant Power Tilt Ratio Manual Calculation

DATA SHEET 1 MANUAL QPTR CALCULATION UPPER DETECTORS Current (Uncor.)

Norm Factor Current (Cor.)

Tilt Ratio N41A N42A N43A N44A

.sum LOWER DETECTORS Current (Uncor.)

Norm Factor Current (Cor.)

Tilt Ratio N41 B N42B N43B N44B Performed By I

I_

(Init/Time/Date)

Verified By (Init/Date)

DATA SHEET 1 Beaver Valley Power Station Unit 2 20ST-2.4A Revision 4 Operating Surveillance Test FOR TRAINING USE ONLYPage 11 of 14 Quadrant Power Tilt Ratio Manual Calculation

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

BVPS Unit 2 Task No.:

Task

Title:

K/A

Reference:

Review a QPTR Manual Calculation 015000A1.04 (3.5/3.7) 015000A4.02 (3.9/3.9)

JPM No.:

2002 NRCAla SRO Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

X Simulator Actual Performance:

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The Unit is in Mode 1 at 80% power. The plant computer is NOT available.

QPTR calculation reviewed and compared to Acceptance Criteria.

Calculator 2OST-2.4A, Quadrant Power Tilt Ratio Manual Calculation, Rev. 4 2OST-2.4A, Rev. 4 QPTR Parameter Sheet The Shift Manager directs you to review the QPTR calculation and report the results.

No 10 minutes NUREG 1021, Revision 8, Supplement I BVPS NRC Ala SRO X

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC Ala SRO (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

CUE:

Provide Candidate with a copy of 2OST-2.4A and QPTR Parameter Sheet.

Reviews upper and lower quadrant excore nuclear instrument detector outputs for each quadrant.

Reviews values of detector current output for each quadrant on Data Sheet 1.

Comment:

Performance Step: 2 "Standard:

Reviews the excore detector normalization factors.

Reviews the normalization factors on Data Sheet 1.

Comment:

Performance Step: 3 Standard:

Checks for correct value of current by multiplying each detector current reading by its normalization factor to obtain a corrected current.

Determines corrected current values are SAT.

Comment:

Performance Step: 4 Standard:

Reviews average upper quadrant and average lower quadrant excore NI detector outputs.

Determines the average currents are SAT.

Comment:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC Ala SRO

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC Ala SRO (Denote Critical Steps with an asterisk)

Performance Step: 5 Standard:

Reviews tilt ratios.

Determines N43A value is NOT correct (0.9943 vs. 1.006).

Comment:

Performance Step: 6 Standard:

Compare highest Quadrant Power Tilt Ratio to Acceptance Criteria.

Determines that QPTR exceeds 1.02 on N43B (1.090).

", Comment:

Terminating Cue:

When the Candidate identifies the error and reports the QPTR does not meet the Acceptance Criteria, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I BVPS NRC Ala SRO

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC Ala SRO Job Performance Measure No.:

2002 NRC Ala SRO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Tim to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS N RC Ala SRO

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC Ala SRO INITIAL CONDITIONS:

INITIATING CUE:

The Unit is in Mode 1 at 80% power. The plant computer is NOT available.

The Shift Manager directs you to review the QPTR calculation and report the results.

NUREG 1021, Revision 8, Supplement I BVPS-2 -NRC AlaSRO

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC Ala RO (Denote Critical Steps with an asterisk)

Performance Step: 4 Standard:

Standard:

Determine average upper quadrant and average lower quadrant excore NI detector output.

Calculates average currents.

Records the following for "AVG":

Top Detectors = 7.155 Bottom Detectors = 7.250 Comment:

Performance Step: 5 "Standard:

Standard:

Divide each quadrant excore NI detector output by the appropriate (Upper or Lower) average NI detector output.

Calculates tilt ratios.

Records the following for "Tilt Ratio":

N41A = 1.015 N41B = 1.016 N42A = 1.011 N42B = 0.907 N43A = 1.006 N43B = 1.090 N44A = 0.969 N44B = 0.973 Comment:

Performance Step: 6 Standard:

Compare highest Quadrant Power Tilt Ratio to Acceptance Criteria.

Determines that the QPTR exceeds 1.02 on N43B (1.090).

Comment:

Terminating Cue:

When the Candidate reports that the QPTR does not meet the Acceptance Criteria, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC Ala RO

Appendix C Job Performance Measure Form ES-C-1 Worksheet BVPS Unit 2 Complete Operating Logs Task No.:

0481-007-03-013 JPM No.:

2002 NRC Alb RO K/A

Reference:

2.2.12 (3.0)

NRC Examiner Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom Simulator Actual Performance:

X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The plant is in Mode I at 100% power with all systems in their normal operating alignment.

Candidate determines out-of-specification reading and reports results to the Unit Supervisor.

None 20M-54.3.L5, Surveillance Verification Log, Rev. 39 20M-54.3.L5, Rev. 39 (partial copy)

The Unit Supervisor directs you to complete L-5, Surveillance Verification Log and report your results.

No 15 minutes NUREG 1021, Revision 8, Supplement 1 Facility:

Task

Title:

Date:

X BVPS NRC Alb RO

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC Aib RO (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Completes L-5 log.

Correctly performs L-5 log and determines that 2SIS-TK-21A level channels indicate greater than the 5% allowance:

Comment:

Performance Step: 2 Standard:

Informs Unit Supervisor of out-of-specification readings.

Informs Unit Supervisor to refer to Technical Specification 4.5.1.a.1 for out-of-specification SI accumulator levels.

comment:

Terminating Cue:

When the Candidate informs the Unit Supervisor to refer to Technical Specifications, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC Alb RO

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC Alb RO Job Performance Measure No.:

2002 NRCAlb RO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time, to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC Al b RO

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET 2002 NRC Alb RO "INITIAL CONDITIONS:

The plant is in Mode 1 at 100% power with all systems in their normal operating alignment.

INITIATING CUE:

The Unit Supervisor directs you to complete L-5, Surveillance Verification Log and report your results.

NUREG 1021, Revision 8, Supplement I BVPS NRC Alb RO

A9.330B Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 20M-54.3.L5 SURVEILLANCE VERIFICATION LOG Revision 39 Prepared by Date Pages Issued C. R. Kuhn 08109102 1 through 48 Reviewed by Date Validated by Date C. J. Eberle 08/09102 N/A OSC Meeting No.

Date OSC Not Required PAF-02-03415

Beaver Valley Power Station Unit 2 20M-54.3.L5 STATION LOGS TN evision 39 FOR TRAINING USE ONL age2of 48 SURVEILLANCE VERIFICATION LOG

[Operating Modes 1. 2 Date No.

Surveillance Tech S-e (Required every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months unless noted) 1 Verification of the following statement can satisfy the control rod surveillances 4.1.1.1.1.b through specified. If the following statement is satisfied, 15-3 through L5-7 are NIA and may be 4.1.1.1.t.d 16 omitted; otherwise, performn L5-3 through 15-7.

4.1.3.2 4.1.3.2.1 Verify all rods are a 225 steps on the Group Demand Counters AND DRPI is within +/-

4.1.3.5.b 12 steps of the Group Demand Counters; otherwise, NIA signoffs below and perform 4.1.3.6 L5-3 through L5-7.

1 START STOP 000(o- 0800 SROtDESIGNEE START STOP 0800- 1600 DATE f

START STOP 1600-2400

Beaver Valley Power Station Unit 2 20M-54.3.L5 STATION LOGS Revision 39 FOR TRAINING USE ONLY Page8of48 SURVEILLANCE VERIFICATION LOG Operating Modes 1, 2,3,4 DATE No.

SrveilancePerformed No.

Survelllance

Tech, 0000" 0800 1 600 (Required every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months unless noted)

Spec.

0800 1600 2400 134 if in Modes 3 or 4 and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operalion has occurred, perform 4.4.6,2.b 2OST-6.2, *Reactor Coolant System Water Inventory Balance' or verify performance within last 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . 2OST-6.2A, "Computer Generated Reactor Coolant System Water Inventory Balance-may be performed instead of 2OST-6.2 when RCS Tavg is Igreater than 530F. (Otherwise N/A) 47 Record and verify that Containment Pressure Indicators agree within 3.0 PSIG of Table 4.3-2 one another.

Items 1c, 2c, 3b3, 4c

[2LMS*PI950]

PSIG

[2LMS*PI951]

PSIG

[2LMS*PI952]

PSIG

[2LMS*P]953]

PSIG 47a Record the Containment Wide Range Pressure Recorder {2LMS-PR1061 pressure Not T.S.

PSIA 28 Verify ACCUMULATOR LEVEL/PRESS HIGH/LOW Annunciator A1-4A is NOT 4.5.1.a.1 through ILLUMINATED due to a valid alarm.

33 I *Required in MODES 1, 2, 3 when pressurizer pressure above 1000 psig.

28 Record Accumulator level and pressure, verify the two indicators on each 4.5.1.a. 1 through accumulator agree within 5% for level, 30 PSIG for press.

33 2SIS-TK21A

[2SIS-U9201

[L06I0A]

[2SIS-U19221

[I-061 IA]

[2SIS-PI9211

[P0610A]

PSIG

[2SIS-PI923l

[P061 IAl PSIG 28 2S I S-TK21B

[2SIS-L19241

[L0620A]

through

[2SIS-L1926]

[L0621A]

33

[2SIS-PI925]

[P0620A]

PSIG

[2SIS-PI9271

[P0621A]

PSIG REMARKS:

/

1

/

START STOP START STOP START STOP 0000-0800 0800-1600 1600-2400 SRO/DESIGNEE DATE

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

Task

Title:

K/A

Reference:

BVPS Unit 2 Review Operating Logs 2.2.12 (3.0)

Task No.:

JPM No.:

1300-002-03-023 2002 NRC Alb SRO Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner.

Date:

X Simulator Actual Performance:

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The plant is in Mode 1 at 100% power with all systems in their normal operating alignment.

Candidate identifies out-of-specification reading and reports results.

None 20M-54.3.L5, Surveillance Verification Log, Rev. 39 20M-54.3.L5, Rev. 39 (markup copy)

You are directed to perform a review of the L-5, Surveillance Verification Log and report your results.

No 5 minutes NUREG 1021, Revision 8, Supplement 1 X

BVPS NRC Alb SRO

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC Alb SRO (Denote Critical Steps with an asterisk)

Performance Step: I Standard:

Reviews L-5 log.

Correctly reviews L-5 log and identifies that 2SIS-TK-21A level channels indicate greater than the 5% allowance:

Comment:

Performance Step: 2 Standard:

Determines T.S. requirements.

Correctly refers to Technical Specification action statement 3.5.1.a to restore the accumulator to operable status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Comment:

Terminating Cue:

When the Candidate references the Technical Specifications, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I BVPS NRC Al b SRO

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC Alb SRO Job Performance Measure No.:

2002 NRC Alb SRO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC Alb SRO

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET 2002 NRC Alb SRO INITIAL CONDITIONS:

INITIATING CUE:

The plant is in Mode I at 100% power with all systems in their normal operating alignment.

You are directed to perform a review of the L-5, Surveillance Verification Log and report your results.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC Alb SRO

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System accumulator shall be OPERABLE with:

a.

The isolation valve open,

b.

Between 7532 and 7802 gallons of borated water,

c.

Between 2300 and 2600 ppm of boron, and

d.

A nitrogen cover-pressure of between 585 and 665 psig.

APPLICABILITY:

MODES 1, 2 and 3.*

ACtION:

a.

With one accumulator inoperable, except as a result of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.1 Each accumulator shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1.

Verifying, by the absence of alarms, the contained borated water volume and nitrogen cover-pressure in the tanks, and

2.

Verifying that each accumulator isolation valve is open.

b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the accumulator solution.

Pressurizer Pressure above 1000 psig.

BEAVER VALLEY - UNIT 2 3/4 5-1 Amendment No.

125

A9.330B Beaver Valley Power Station Unit 2 FOR TRAINING USE ONL 20M-54.3.L5 SURVEILLANCE VERIFICATION LOG Revision 39 Prepared by Date Pages Issued C. R. Kuhn 08/09102 1 through 48 Reviewed by Date Validated by Date C. J. Eberle 08109/02 N/A OSC Meeting No.

Date OSC Not Required PAF-02-03415

Beaver Valley Power Station Unit 2 20M-54.3.L5 Beaver Valley Power Station Unit 2 20M-54.3.L5 STATION LOGS Revision 39 SURVEILLANCE VERIFICATION LOM A'R TRAINING USE ONL ge2of 48 Operating Modes 1, 2 Date No.

Surveillance Tech. Specs.

(Required every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months unless noted)

I Verification of the following statement can satisfy the control rod surveillances 4.1.1.1.1.b through specified. If the following statement is satisfied, L5-3 through 15-7 are NIA and may be 4.1.1.1.1.d 16 omitted; otherwise, perform 15-3 through 15-7.

4.1.3.1.2 4.1.3.2.1 Verify all rods are a 225 steps on the Group Demand Counters AND DRPI is within +

4.1.3.5.b 12 steps of the Group Demand Counters; otherwise, NIA signoffs below and perform 4.1.3.6 1-L5-3 through L5-7.

0800

/ 1000 t

/

START STOP START STOP START STOP RO1 0000-0600 0800-1600 1600-2400 SRO/DESIGNEE DATE

Beaver Valley Power Station Unit 2 20M-54.3.L5 STATION LOGS Revision 39 FOR TRAINING USE ONLYPage8°f48 SURVEILLANCE VERIFICATION LOG Operating Modes 1, 2, 3, 4 DATE Performed No.

Surveillance Tech.

0000 0800 1600 (Required every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months unless noted)

Spec.

0800 1600 2400 134 If in Modes 3 or 4 and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation has occurred, perform 4.4.6.2.b 20ST-6.2, "Reactor Coolant System Water Inventory Balance" or verify performance N/A within last 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . 2OST-6.2A, "Computer Generated Reactor Coolant System Water Inventory Balance" may be performed instead of 2OST-6.2 when RCS Tavg is greater than 530F. (Otherwise N/A) 47 Record and verify that Containment Pressure Indicators agree within 3.0 PSIG of Table 4.3-2 one another.

Items 1c, 2c, 3b3, 4c

[2LMS*PI950]

PSIG 0.1

[2LMS*PI951]

PSIG 0.2

[2LMS*P]952]

PSIG

-0.2

[2LMS*PI953]

PSIG 0.3 47a Record the Containment Wide Range Pressure Recorder [2LMS-PR1 06] pressure Not T.S.

11.8 "PSIA 28 Verify ACCUMULATOR LEVEL/PRESS HIGH/LOW Annunciator A1-4A is NOT 4.5.1.a.1 through ILLUMINATED due to a valid alarm.

R01 33

Required in MODES 1, 2, 3 when pressurizer pressure above 1000 psig.

28 Record Accumulator level and pressure, verify the two indicators on each 4.5.1.a. 1 through accumulator agree within 5% for level, 30 PSIG for press.

33 2SIS-TK21A

[2SlS-L1920]

[L0610A]

55

[2SIS-LI922]

[L061 1 A]

63

[2SIS-PI921]

[P0610A]

PSIG 620

[2SlS-PI923]

[P061 1A]

PSIG 640 28 2SIS-TK21B

[2SIS-LI924]

[L0620A]

58 through

[2SIS-LI926]

[L0621A]

56 33

[2SIS-PI925]

[P0620A]

PSIG 610

[2SlS-PI927]

[P0621A]

PSIG 625 REMARKS:

0800 I 1000

/

START STOP START STOP START STOP R01 0000 -0800 0800- 1600 1600 -2400 SRO/DESIGNEE DATE

Beaver Valley Power Station Unit 2 20M-54.3.L5 STATION LOGS Revision 39 FOR TRAINING USE ONLYPage9of48 SURVEILLANCE VERIFICATION LOG Operating Modes 1, 2, 3, 4 DATE Performed Performed___

No.

Surveillance Tech.

0000 0800 1600 (Required every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months unless noted)

Spec.

0800 1600 2400 28 2SIS-TK21C

[2SIS-L1928]

[L0630A]

55 through

[2SlS-L1930]

[L0631A]

53 33

[2SIS-PI929]

[P0630A]

PSIG 605

[2SIS-PI931]

[P0631A]

PSIG 615

'Required in MODES 1, 2, 3 when pressurizer pressure above o

1000 psig.

35 Verify accumulator TK21A, B, C outlet isolation valves [2SIS*MOV865AB,C] are 4.5.1.a.2 open by observing the red Open lights are ON on BB-A R01 I *Required in Modes 1, 2 & 3 when pressurizer pressure above 1000 psig.

35a Verify accumulator TK21A, B, C outlet isolation valves [2SlS*MOV865A, B,C] control 4.5.1.c circuit power is disconnected by removal of the plugs in the lock out jack from the ROf

"* circuits (Window Al -48)

.Required in Modes 1, 2 & 3 when pressurizer pressure above 1000 psig.

50 Record the Reactor Containment Sump narrow range level indications and verify 4.4.6.2.a.4 level is < 10.75 inches

[2DAS-L1220]

IN 2.6

[2DAS*LI2221 IN

1.4 REMARKS

0800

/ 1000

/

START STOP START STOP START STOP R01 0000 - 0800 0800 - 1600 1600 -2400 SRO/DESIGNEE DATE

Appendix C Job Performance Measure Form ES-C-1 Worksheet BVPS Unit 2 Perform AC Sources Alignment Verification Task No.:

0481-014-03-013 JPM No.:

2002 NRC A2 RO K/A

Reference:

2.2.12 (3.0)

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The plant is in Mode I at 100% power with all systems in their normal operating alignment.

"* Emergency Diesel Generator No. 1 was declared inoperable and removed from service 20 minutes ago.

"* 20ST-36.7 is in progress and Train "A" equipment has been verified.

Candidate correctly completes Data Sheet I and informs the Unit Supervisor to refer to Technical Specifications.

None 20ST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification, Rev. 8 20ST-36.7, Rev. 8 (markup copy)

The Unit Supervisor directs you to perform Data Sheet I of 20ST-36.7, for Train "B" equipment only.

No 10 minutes NUREG 1021, Revision 8, Supplement I Facility:

Task

Title:

X BVPS-2 NRC A2 RO

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC A2 RO (Denote Critical Steps with an asterisk)

NOTE: Candidate may complete sign-offs for Initial Conditions. These steps are not part of the JPM.

Performance Step: 1 Standard:

Comment:

Performance Step: 2 Standard:

Comment:

Terminating Cue:

Complete Data Sheet 1.

Correctly completes Data Sheet 1 and identifies that the neon light for ACB 342B is NOT lit.

CUE:

If the Candidate initiates a bulb check, inform the Candidate that the bulb check is SAT.

CUE:

If necessary, direct the Candidate to complete the remaining breaker verifications.

Reports results and applicability of T.S. 3.8.1.1 or 3.8.1.2.

Informs Unit Supervisor that Acceptance Criteria is NOT met and to refer to T.S. 3.8.1.1 or 3.8.1.2.

CUE:

If necessary, prompt the Candidate to supply the information regarding T.S. applicability.

When the Candidate informs the Unit Supervisor to refer to T.S.

3.8.1.1 or 3.8.1.2, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A2 RO

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC A2 RO Job Performance Measure No.:

2002 NRC A2 RO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Tirve to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS-2 N RC A2 RO

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET 2002 NRCA2 RO "INITIAL CONDITIONS:

INITIATING CUE:

The plant is in Mode 1 at 100% power with all systems in their normal operating alignment.

"* Emergency Diesel Generator No. 1 was declared inoperable and removed from service 20 minutes ago.

"* 2OST-36.7 is in progress and Train "A" equipment has been verified.

The Unit Supervisor directs you to perform Data Sheet 1 of 2OST-36.7, for Train "B" equipment only.

NUREG 1021, Revision 8, Supplement 1 BVPS-2 NRC A2 RO

A9.330B Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 2OST-36.7 Offsite to Onsite Power Distribution System Breaker Alignment Verification Revision 8 Prepared by Date Pages Issued W. K. Giffrow 217102 1 through 14 Reviewed by Date Validated by Date R. C. Plummer 2/15102 NIA OSC Meeting No.

Date OSC Not Required DRR-02-00634

Table Of Contents I.

PURPOSE...................................................................................................................................

5 II.

DISCUSSION..............................................................................................................................

5 III.

ACCEPTANCE CRITERIA..................................................................................................

5 IV. EQUIPMENT AND MATERIAL..............................................................................................

5 V.

PRECAUTIONS AND LIM ITATIONS......................................................................................

5 VI.

INITIAL CONDITIONS.................................................................................................................

5 VII.

INSTRUCTIONS..........................................................................................................................

7 VIII. DATA SHEETS, TABLES, FIGURES, AND ATTACHMENTS..............................................

10 DATA SHEET 1..................................................................................................................................

11 DATA SHEET 2..................................................................................................................................

12 IX. REFERENCES..........................................................................................................................

13 Table Of Contents Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Operating Surveillance Test f oerTRAINING USE ONW of 14 Offsite to Onsite Power Distribution Syste Alignment Verification

Frequency: W ISurveillance Requirements: 4.8.1.1.1.a & 4.8.1.2 Required for Mode(s): 1, 2, 3, 4, 5, 6, #, @

Date / Time Completed:

Performed in Mode(s): ALL Total Manhours:

TEST RESULTS: (Completed by Performer)

PERFORMED BY:

Name (Print)

Initial

('/or N/A)

ROI ROI 0 __ Test Completed SATISFACTORY 0

Problems Encountered (See Problem Sheet) 0 _

Unscheduled/partial OST (explain)

Reviewer Signature/Date STA Review

/

NSS Approval

/

COMMENTS: (Include Date and Initials) o Comments continued on Problem Sheet During movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies.

Within one hour PRIOR to a preplanned removal of a diesel generator from service OR within one hour AFTER an unplanned removal of a diesel generator from service (Diesel Inoperable). (T.S. 3.8.1.1)(Ic2 Beaver Valley Power Station Unit 2 2OST-36.7 sevision 8 Operating Surveillance Test F

TISl~lle 3 of 14 Offsite to Onsite Power Distribution Sy reaker Alignment Verification

OST PROBLEM SHEET See Page and Step No. for problem description. See below for corrective action.

.1

.L I _____________

Beaver Valley Power Station Unit 2 2OST-36.7 SUS I

evision Operating Surveillance Test eO R-kT AINING USE ONLLLge 4 of 14 Offsite to Onsite Power Distribution Sy~er~ ar' Alignment Verification PAGE NO.

STEP NO.

DESCRIBE CORRECTIVE ACTION INITIALS DATE

I.

PURPOSE This procedure demonstrates the operability of the two physically independent circuits between the offsite transmission network and the onsite Class I E distribution system.

I1.

DISCUSSION The operator will perform this OST by filling out the attached Data Sheet 1 or Data Sheet 2.

Ill.

ACCEPTANCE CRITERIA SNote:

Satisfactory completion means that the required circuits are operable as Nedetermined by correct breaker lineup and indicated power availability.

A. Satisfactory completion of Data Sheet I for normal offsite alignment (Modes 1-6, or "during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies).

B.

Satisfactory completion of Data Sheet 2 while in Backfeed.

IV.

EQUIPMENT AND MATERIAL NONE V.

PRECAUTIONS AND LIMITATIONS A.

Circuit breakers should NOT be operated for the purpose of aligning to the conditions specified on Data Sheet I or 2, unless NSS/ANSS has been notified AND approval to operate breaker has been given.

VI.

INITIAL CONDITIONS A.

Plant Status Chances This procedure does not affect plant status.

Beaver Valley Power Station Unit 2 2OST-36.7 TRAINING USE evision Operating Surveillance Test FOR TRAINING USE ONLFgee5 of 14 Offsite to Onsite Power Distribution System Breaker Alignment Verification

B.

NSS/ANSS Sign-on

1.

NSS/ANSS verifies the following:

Performance of this procedure is authorized.

DATE: 11/17/02 jTIME: 0800 ICURRENT PLANT MODE: 1 NSS/ANSS COMMENTS:

None.

"NSS I ANSS Signature Shift Mananer C. Reactor Operator Sian-on

1. Reactor Operator perform the following:

Acknowledge procedure performance.

Reactor Operator Signature D. Procedure Performer Initial Conditions

1. The operator performing this test has reviewed this procedure.

I Initial I Date Beaver Valley Power Station Unit 2 2OST-36.7 Operating Surveillance Test FOR TRAINING USE ONI

' o Offsite to Onsite Power Distribution System Breaker Alignment Verification

VII.

INSTRUCTIONS A. Test Preparation

1. Completion of Data Sheet 1, NOT on Backfeed. (Otherwise N/A)

a.

The plant is in operational Mode 1, 2, 3, 4, 5, 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies.

I Initial I Date

b.

The onsite Class I E distribution system is being powered through the Unit Station Service Transformers OR the System Station Service Transformers.

I

.Initial I Date

2.

Completion of Data Sheet 2, on Backfeed. (Otherwise N/A)

a. The plant is in operational Mode 5, 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies.

N/A / Today Initial I Date

b.

The onsite Class 1 E distribution system is being powered through the Unit Station Service Transformers, Backfeed through the Main Transformer.

NIA I Today Initial I Date Beaver Valley Power Station Unit 2 20ST-36.7

%a*i

evision8 Operating Surveillance Test FOR TRAINING USE ONLtdge 7eofl,4 Offsite to Onsite Power Distribution System Breaker Alignment Verification

3.

Review OST schedule and determine if this is the scheduled weekly performance of this OST.

RO1 I Today Initial I Date

a.

For scheduled weekly performance, Blackout Breakers ACB 2A2 and ACB 2D12 are to be checked locally. (Otherwise N/A)

NIA I Today Initial I Date OR

b.

If this is not the scheduled weekly performance, verification of Blackout Breakers ACB 2A2 and ACB 2D12 position may be performed via review of Padlock Manipulation Log. (Otherwise N/A)

ROI I Today Initial I Date B.

Performance of the OST Note:

Either Step VII.B.1 OR Step VII.B.2 should be completed AND the other step should be N/A. Only the data sheet required for the current mode of operation should be filled out and completed. The unused data sheet is to be left blank.

1. When in Modes 1 through 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies. (NOT on Backfeed) complete Data Sheet 1. (Otherwise N/A)

a. Data Sheet 1 completed satisfactorily.

I Initial i Date

b.

If Data Sheet 1 cannot be completed satisfactorily notify NSS AND refer to Technical Specifications 3.8.1.1 or 3.8.1.2 as applicable.

I Initial I Date Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Operating Surveillance Test F

eTRAI NG USE ONLY Offsite to Onsite Power Distribution Systet fer Alignment Verification

c.

If this procedure is being performed prior to taking a Diesel Generator out of service, Notify the NSS/ANSS to refer to Licensing Requirements 2.5, 2.6, 2.1, and 2.2. (Otherwise Mark N/A)

N/A I Today Initial I Date

2.

When in Modes 5, 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies, AND station power is obtained by backfeeding, complete Data Sheet 2. (Otherwise N/A)

a.

Data Sheet 2 completed satisfactorily.

NIA I Today "Initial I Date

b.

If Data Sheet 2 cannot be completed satisfactorily notify NSS AND refer to Technical Specifications.

NIA I Today Initial I Date C. Test Completion

1. Consult the acceptance criteria for acceptable performance.

i Initial I Date

2.

Inform the NSS/ANSS of the completion of this test.

I Initial I Date

3.

Complete the front cover sheet.

I initial i Date Beaver Valley Power Station Unit 2 2OST-36.7 Revision 8 Operating Surveillance Test FOR TRAINING USE ONt~' 9of 14 Offsite to Onsite Power Distribution System Breaker Alignment Verification

Beaver Valley Power Station Unit 2 2OST-36.7 Operating Surveillance Test FOR TRAINING USE -NL vision 8.

Offsite to Onsite Power Distribution System Breaker Alignment Verification DATA SHEET 1 WITHOUT BACKFEED (For Modes I through 6, or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies, see Note 1)

ITEM REQUIRED POSmON (O or SOI INITIAL)

OR READING (READING I INITIAL) 138KV BUS 2-Train A 138KV OCB 85 CLOSED (RED UGHT ON)

S

/ RO1 MTR OPER DISC SW 89-2A CLOSED (RED UGHT ON)

S

/ RO1 2A SSST Volt Sel.

A: Bus FDR. (Phase Y) 124

/ R01 Pos A-B 125V (Note 2)

Pos B-C 125V (Note 2) 125 1 RO1 Pos C-A 125V (Note 2) 124 B RI _

4KV Bus 2A ACB 42A OPEN (DIM WHITE LIGHT ON) 0 R01 (NEON LAMP ON) (Note 3)

ON t RO1 OR CLOSED (TWO RED LIGHTS ON)

(NEON LAMP OFF) 4KV Bus 2A ACB 2A2-'

Locked in the DISC DISC I

RO1 (disconnect) position (Note 4) 4KV Bus 2A ACB 2A10 CLOSED (RED LIGHT ON)

S

/ ROl 4KV Bus 2AE ACB 2E7 CLOSED (RED LIGHT ON)

S j

R01 138KV BUS 1-Train B 138KV OCB 94 CLOSED (RED LIGHT ON)

I 28 SSST Volt Sel.

D Bus FDR. (Phase Y)

Poe A-B 125V (Note 2)

/

Pos B-C 125V (Note 2)

I Pos C-A 125V (Note 2)

I 4KV Bus 20 ACB 342B OPEN (DIM WHITE LIGHT ON)

(NEON LAMP ON) (Note 3)

/

OR CLOSED (TWO RED LIGHTS ON)

/

(NEON LAMP OFF) 4KV Bus 2D ACB 2D12

Locked in the DISC DISC

/

R01

_(disconnect) position (Note 4) 4KV Bus 2D ACS 2010 CLOSED (RED UGHT ON)

I 4KV Bus 2DF ACB 2F7 CLOSED (RED LIGHT ON)

/

Notes:

1.

It is intended that both circuits be verified as Indicated, although during Mode 5, 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies, only one of the two circuits Is [eoulred by Tech Specs to be demonstrated operable.

2.

All voltage readings are nominal and the meters are not required to be calibrated. Readings are made on the 4KV Common Voltmeter (VB-C)

3.

illuminated neon lamp signifies that ACB is setup for Automatic Bus Transfer (During Mode I operation only).

4.

Verify locally each scheduled weekly performance. For additional performances, verification may be via review of Padlock Manipulation Log.

DATA SHEET 1

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

BVPS Unit 2 Task No.:

Review AC Sources Alignment Verification JPM No.:

2002 NRC A2 SRO K/A

Reference:

2.2.12 (3.4)

NRC Examiner Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom X

Simulator Actual Performance:

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

The plant is in Mode 1 at 100% power with all systems in their normal operating alignment.

"* Emergency Diesel Generator No. 1 was declared inoperable and removed from service 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago.

"* The PO has completed 2OST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification.

"* Emergency Diesel Generator No. 2 was tested satisfactorily per T.S.

4.8.1.1.2.a.5.

Candidate identifies the Data Sheet 1 error and determines the correct T.S. action requirement.

None 20ST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification, Rev. 8 T.S. 3.8.1.1 20ST-36.7, Rev. 8 (markup copy)

T.S. 3.8.1.1 Initiating Cue:

Time Critical Task:

Validation Time:

The Shift Manager directs you to review the completed 20ST-36.7 and report your results.

No 10 minutes NUREG 1021, Revision 8, Supplement 1 Task

Title:

Date:

X BVPS N RC A2 SRO

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC A2 SRO (Denote Critical Steps with an asterisk)

Performance Step: I Standard:

Comment:

'Performance Step: 2 Standard:

Comment:

Terminating Cue:

Reviews Data Sheet 1.

Correctly reviews Data Sheet I and identifies that the neon light for ACB 342 is NOT lit.

CUE:

If the Candidate asks for the status of the bulb, inform the Candidate that a bulb check was SAT.

NOTE:

Provide the Candidate a copy of the T.S. handout.

Reports results and T.S. action requirement.

Informs Shift Manager that Acceptance Criteria is NOT met and that Action Statement T.S. 3.8.1.1.c requires restoring 1 of the inoperable sources to operable status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

CUE:

If necessary, prompt the Candidate to determine the T.S. action statement requirement for inoperable circuit and diesel generator.

When the Candidate informs the Shift Manager of the results of the review, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC A2 SRO

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC A2 SRO Job Performance Measure No.:

2002 NRC A2 SRO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Tirpq to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC A2 SRO

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET 2002 NRC A2 SRO INITIAL CONDITIONS:

INITIATING CUE:

The plant is operating at 100% power with all systems in their normal operating alignment. DG 1 was declared inoperable and removed from service 40 minutes ago. The PO has successfully completed OST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification.

The Shift Manager directs you to review 2OST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification.

NUREG 1021, Revision 8, Supplement I BVPS NRC A2 SRO

A9.330B Beaver Valley Power Station Unit 2 i"OR TRAINING USE ONLY 2OST-36.7 Offsite to Onsite Power Distribution System Breaker Alignment Verification Revision 8 Prepared by Date Pages Issued W. K. Giffrow 2/7102 1 through 14 Reviewed by Date Validated by Date R. C. Plummer 2/15102 NIA OSC Meeting No.

Date OSC Not Required DRR-02-00634

Table Of Contents

i.

PURPOSE...................................................................................................................................

5 II.

DISCUSSION..............................................................................................................................

5 Ill.

ACCEPTANCE CRITERIA..................................................................................................

5 IV.

EQUIPMENT AND MATERIAL.................................................................................................

5 V.

PRECAUTIONS AND LIM ITATIONS......................................................................................

5 VI.

INITIAL CONDITIONS.................................................................................................................

5 VII.

INSTRUCTIONS..........................................................................................................................

7 VIII. DATA SHEETS, TABLES, FIGURES, AND ATTACHMENTS 10 DATA SHEET 1..................................................................................................................................

11 DATA SHEET 2..................................................................................................................................

12 IX. REFERENCES..........................................................................................................................

13 Table Of Contents Beaver Valley Power Station Unit 2 2OST-36.7 Operating Surveillance Test OR TRAINING USE of 14 Offsite to Onsite Power Distribution System Breaker Alignment Verification

v L

Comments continued on Problem Sheet During movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies.

@ Within one hour PRIOR to a preplanned removal of a diesel generator from service OR within one hour AFTER an unplanned removal of a diesel generator from service (Diesel Inoperable). (T.S. 3.8.1.1 )(yIc.2)

Beaver Valley Power Station Unit 2 2OST-36.7

,,Revision8 Operating Surveillance Test IO IRAiNIN( USL ONL ge 3 of 14 Offsite to Onsite Power Distribution Sy eaker Alionment Verification Frequency: W Surveillance Requirements: 4.8.1.1.1.a & 4.8.1.2 Required for Mode(s): 1, 2, 3, 4, 5, 6, #, @

Date / Time Completed:

Performed in Mode(s): ALL Total Manhours:

TEST RESULTS: (Completed by Performer)

PERFORMED BY:

Name (Print)

Initial (4 or N/A)

PO1 P01 o] ___Test Completed SATISFACTORY o

Problems Encountered (See Problem Sheet) o]

Unscheduled/partial OST (explain)

Reviewer Signature/Date STA Review

/

NSS Approval

/

COMMENTS: (Include Date and Initials)

OST PROBLEM SHEET See Page and Step No. for problem description. See below for corrective action.

PAGE NO. I STEP NO.

DESCRIBE CORRECTIVE ACTION INITIALS DATE Beaver Valley Power Station U

ntA-2OST-36.7 Operating Surveillance Test r0RieAINING USE ONL-'e 4

Offsite to Onsite Power Distribution System Breaker Alignment Verification

Beaver Valley Power Station Unit 2 2OST-36.7 Operating Surveillance Test rOR TRAINING USE O pae5 of 14 Offsite to Onsite Power Distribution System Breaker Alignment Verification I.

PURPOSE This procedure demonstrates the operability of the two physically independent circuits between the offsite transmission network and the onsite Class 1 E distribution system.

II.

DISCUSSION The operator will perform this OST by filling out the attached Data Sheet I or Data Sheet 2.

Ill.

ACCEPTANCE CRITERIA Note:

Satisfactory completion means that the required circuits are operable as determined by correct breaker lineup and indicated power availability.

"... A.

Satisfactory completion of Data Sheet I for normal offsite alignment (Modes 1-6, or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies).

B.

Satisfactory completion of Data Sheet 2 while in Backfeed.

IV.

EQUIPMENT AND MATERIAL NONE V.

PRECAUTIONS AND LIMITATIONS A.

Circuit breakers should NOT be operated for the purpose of aligning to the conditions specified on Data Sheet I or 2, unless NSS/ANSS has been notified AND approval to operate breaker has been given.

VI.

INITIAL CONDITIONS A. Plant Status Chanaes This procedure does not affect plant status.

Beaver Valley Power Station Unit 2 2OST-36.7

~b bA~dI~(~

SE ~j~~evsion 8 Operating Surveillance Test r's TRAINING USE ONI ree6of14 Offsite to Onsite Power Distribution System Breaker Alignment Verification B.

NSSIANSS Sian-on

1. NSS/ANSS verifies the following:

Performance of this procedure is authorized.

DATE: 11/17/02 jTIME: 0800 ICURRENT PLANT MODE: 1 NSSIANSS COMMENTS:

None.

NSS I ANSS Signature Shift Manager C. Reactor Operator Sign-on

1.

Reactor Operator perform the following:

Acknowledge procedure performance.

Reactor Operator Signature PO1 D. Procedure Performer Initial Conditions

1. The operator performing this test has reviewed this procedure.

PO1 I Today Initial I Date

Beaver Valley Power Station

,...Unit 2 20ST-36.7 rOR TAINIG USONV vision8 Operating Surveillance Test rOR TRAINING USE ^N" of 8 Offsite to Onsite Power Distribution System Breaker Alignment Verification VII.

INSTRUCTIONS A. Test Preparation

1.

Completion of Data Sheet 1, NOT on Backfeed. (Otherwise N/A)

a.

The plant is in operational Mode 1, 2, 3, 4, 5, 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies.

PO1 I Today Initial I Date

b.

The onsite Class 1 E distribution system is being powered through the Unit Station Service Transformers OR the System Station Service Transformers.

PO1 I Today Initial I Date

2.

Completion of Data Sheet 2, on Backfeed. (Otherwise N/A)

a.

The plant is in operational Mode 5, 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies.

NIA I Today Initial I Date

b.

The onsite Class 1 E distribution system is being powered through the Unit Station Service Transformers, Backfeed through the Main Transformer.

NIA I Today Initial I Date

Beaver Valley Power Station Unit 2 2OST-36.7

/%ý

,vision8 Operating Surveillance Test FOR TRAINING USEONPfe 8 of 14 Offsite to Onsite Power Distribution System Breaker Alignment Verification

3.

Review OST schedule and determine if this is the scheduled weekly performance of this OST.

PO1 I Today Initial I Date

a.

For scheduled weekly performance, Blackout Breakers ACB 2A2 and ACB 2D12 are to be checked locally. (Otherwise N/A)

NIA I Today Initial I Date OR

b.

If this is not the scheduled weekly performance, verification of Blackout Breakers ACB 2A2 and ACB 2D12 position may be performed via review of Padlock Manipulation Log. (Otherwise N/A)

PO1 I Today initial I Date B. Performance of the OST Note:

Either Step VII.B.1 OR Step VII.B.2 should be completed AND the other step should be N/A. Only the data sheet required for the current mode of operation should be filled out and completed. The unused data sheet is to be left blank.

1. When in Modes 1 through 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies. (NOT on Backfeed) complete Data Sheet 1. (Otherwise N/A)

a.

Data Sheet I completed satisfactorily.

POI I Today Initial I Date

b.

If Data Sheet 1 cannot be completed satisfactorily notify NSS AND refer to Technical Specifications 3.8.1.1 or 3.8.1.2 as applicable.

PO1 I Today Initial I Date

Beaver Valley Power Station Unit 2 20ST-36.7 Revision8&

Operating Surveillance Test 0R TRAINING USE 0NLVage 9 of 14 Offsite to Onsite Power Distribution System Breaker Alignment Verification

c.

If this procedure is being performed prior to taking a Diesel Generator out of service, Notify the NSS/ANSS to refer to Licensing Requirements 2.5, 2.6, 2.1, and 2.2. (Otherwise Mark N/A)

N/A I Today Initial I Date

2.

When in Modes 5, 6 or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies, AND station power is obtained by backfeeding, complete Data Sheet 2. (Otherwise N/A)

a.

Data Sheet 2 completed satisfactorily.

N/A I Today Initial I Date

b.

If Data Sheet 2 cannot be completed satisfactorily notify NSS AND refer to Technical Specifications.

NIA I Today Initial I Date C. Test Completion

1. Consult the acceptance criteria for acceptable performance.

I Initial I Date

2.

Inform the NSS/ANSS of the completion of this test.

i Initial I Date

3.

Complete the front cover sheet.

I Initial I Date

Beaver Valley Power Station Unit 2 2OST-36.7 S........

Revision 8 Operating Surveillance Test FOR TRAINING USE O eyN of 14 Offsite to Onsite Power Distribution System Breaker Alignment Verification DATA SHEET I WITHOUT BACKFEED (For Modes 1 through 6, or during movement of recently irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies, see Note 1)

REQUIRED POSITION (0 or S I INITIAL)

ITEM OR OR READING (READING I INITIAL) 138KV BUS 2-Train A 138KV OCB 85 CLOSED (RED LIGHT ON)

S

/ Po1 MTR OPER DISC SW 89-2A CLOSED (RED LIGHT ON)

S

/Po1 2A SSST Volt Sel.

A Bus FDR. (Phase Y)

Pos A-B 125V (Note 2) 124 P01 Pos B-C 125V (Note 2) 125 I P01 Pos C-A 125V (Note 2) 124

/ P01 4KV Bus 2A ACB 42A OPEN (DIM WHITE LIGHT ON) 0

/ P01 (NEON LAMP ON) (Note 3)

ON

/ P01 OR CLOSED (TWO RED LIGHTS ON)

(NEON LAMP OFF) 4KV Bus 2AACB 2A2-'

Locked in the DISC DISC i

P01 (disconnect) position (Note 4) 4KV Bus 2A ACB 2A10 CLOSED (RED LIGHT ON)

S

/ P01 4KV Bus 2AE ACO 2E7 CLOSED (RED LIGHT ON)

S

/ PO1 138KV BUS 1-Train B 138KV OCB 94 CLOSED (RED LIGHT ON)

S

/ P01 2B SSST Volt Sel.

D Bus FDR. (Phase Y) 125

/ P01 Pos A-B 125V (Note 2) 124 i P01 Pos B-C 125V (Note 2) 124

/ P01 Pos C-A 125V (Note 2) 125

/ P01 4KV Bus 2D ACS 342B OPEN (DIM WHITE LIGHT ON) 0

/ P01 (NEON LAMP ON) (Note 3)

OFF

/ P01 OR CLOSED (TWO RED UGHTS ON)

/

(NEON LAMP OFF)

I 4KV Bus 20 ACB 2D12ýý'

Locked in the DISC DISC

/

P01 (disconnect) position (Note 4) 4KV Bus 20 ACB 2D10 CLOSED (RED LIGHT ON)

S I P01 4KV Bus 2DF ACB 2F7 CLOSED (RED UGHT ON)

S I P01 Notes:

1.

It Is Intended that both circuits be verified as indicated, although during Mode 5, 6 or during movement of recently Irradiated fuel assemblies, and during movement of fuel assemblies over recently irradiated fuel assemblies, only one of the two circuits Is reured by Tech Specs to be demonstrated operable.

2.

All voltage readings are nominal and the meters are not required to be calibrated. Readings are made on the 4KV Common Voltmeter (VB-C)

3.

Illuminated neon lamp signifies that ACB is setup for Automatic Bus Transfer (During Mode I operation only).

4.

Verify locally each scheduled weekly performance. For additional performances. verification may be via review of Padlock Manipulation Log.

DATA SHEET I

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.

SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, and

b.

Two separate and independent diesel generators each with:

1.

Separate day tank containing a minimum of 350 usable gallons of fuel,

2.

A separate fuel storage system containing a minimum of 53,225 usable gallons of fuel,

3.

A separate fuel transfer pump,

4.

Lubricating oil storage containing a minimum total volume of 504 gallons of lubricating oil, and

5.

Capability to transfer lubricating oil from storage to the diesel generator unit.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

a.

With one offsite circuit inoperable, demonstrate the OPERABILITY of the remaining A.C.

sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

Restore the offsite circuit to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one diesel generator(') inoperable, demonstrate the OPERABILITY of the A.C.

offsite sources by performing Surveillance Requirement 4.8.1.1.1.a within 1

hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; and if the diesel (1) Fuel oil contained in the storage tanks not meeting the properties in accordance with 4.8.1.1.2.d.2 or 4.8.1.1.2.e shall be brought within the specified limits within 7 days.

BEAVER VALLEY - UNIT 2 3/4 8-1 Amendment No.

105

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) generator became inoperable due to any cause other than an independently testable component, testing or preplanned preventative maintenance, demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Surveillance Requirement 4.8.1.l.2.a.5 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (2 7 unless the absence of any potential common mode failure for the remaining diesel generator is demonstrated.

Restore the diesel generator to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With one offsite circuit and one diesel generator(I inoperable, demonstrate the OPERABILITY of the remaining A.C.

sources by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; and if the diesel generator became inoperable due to any cause other than an independently testable component, testing or preplanned preventative maintenance, demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Surveillance Requirement 4.8.1.1.2.a.5 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (2) unless the absence of any potential common mode failure for the remaining diesel generator is demonstrated.

Restore one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Restore the other A.C. power source (offsite circuit or diesel generator) to OPERABLE status in accordance with the provisions of Action Statement a or b, as appropriate with the time requirement of that Action Statement based on the time of initial loss of the remaining inoperable A.C.

power source.

A successful test of diesel OPERABILITY per Surveillance Requirement 4.8.1.1.2.a.5 performed under this Action Statement for an OPERABLE diesel or a restored to OPERABLE diesel satisfies the diesel generator test requirement of Action Statement b.

(1) Fuel oil contained in the storage tanks not meeting the properties in accordance with 4.8.1.1.2.d.2 or 4.8.1.1.2.e shall be brought within the specified limits within 7 days.

(2)

This action is required to be completed regardless of when the inoperable diesel generator is restored to OPERABILITY.

BEAVER VALLEY -

UNIT 2 3/4 8-2 Amendment No.

79

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

Task

Title:

K/A

Reference:

BVPS Unit 2 Radiological Controls Administrative Questions 2.3.10 (2.9) 2.3.1 (2.6)

Task No.:

JPM No.:

N/A 2002 NRC A3 RO Examinee:

Facility Evaluator:

N/A Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

N/A Both questions answered correctly.

None 1/2-ADM-1601, Radiation Protection Standards, Rev. 5 1/2-ADM-1 630, Radiation Worker Practices, Rev. 3 None N/A No 5 minutes NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A3 RO Questions

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC A3 RO Questions ANSWER KEY RO Admin A3 Question 1 You and a co-worker are isolating a pump with a leaking seal in a high noise area in the plant.

Ten minutes after arriving at the pump your alarming dosimeter (ARD) sounds a dose rate alarm. Your co-worker's ARD is not alarming.

Place the following actions in the correct order of performance in response to the ARD alarm.

Note the indicated dose rate Notify Radiation Protection Technician Leave the work area Have your co-worker check their indicated dose rate ANSWER:

Reference:

Correct order is A, D, C & B.

112-ADIM-1630, Radiation Worker Practices, Rev. 3 NUREG 1021, Revision 8, Supplement I A.

B.

C.

D.

BVPS-2 NRC A3 RO Questions

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC A3 RO Questions ANSWER KEY RO Admin A3 Question 2 An evolution that is expected to take several hours must be performed in a Radiation Area. The individual who will perform the activity has a year to date exposure of 3160 mR (TEDE). The dose rate in the area where the emergency evolution will be performed is 80 mR/hr, and there is no airbome radioactivity present.

Determine the worker's MAXIMUM stay time while performing the activity to prevent exceeding any administrative dose guidelines.

ANSWER:

4000 mR Administrative Exposure Limit 3160 mrem YTD Exposure 4000 mrem - 3160 mrem = 840 mR available (840 mrem)/(80mrem/hr) = 10.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

Reference:

112-ADM-1601, Radiation Protection Standards, Rev. 5 NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A3 RO Questions

Appendix C Page 4 of 6 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC A3 RO Questions Job Performance Measure No.:

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question 1:

Response

Question 2:

Response

Result:

Examineres Signature:

2002 NRC A3 RO N/A N/A SAT UNSAT Date:

NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A3 RO, Questions

Appendix C Page 5 of 6 Form ES-C-1 JPM CUE SHEET 2002 NRC A3 RO Questions CANDIDATE COPY Question I RO Admin A3 NO Reference Allowed You and a co-worker are isolating a pump with a leaking seal in a high noise area in the plant.

Ten minutes after arriving at the pump your alarming dosimeter (ARD) sounds a dose rate alarm. Your co-worker's ARD is not alarming.

Place the following actions in the correct order of performance in response to the ARD alarm.

A.

Note the indicated dose rate B.

Notify Radiation Protection Technician C.

Leave the work area D.

Have your co-worker check their indicated dose rate NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A3 RO Questions

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET 2002 NRC A3 RO Questions CANDIDATE COPY Question 2 RO Admin A3 NO Reference Allowed An evolution that is expected to take several hours must be performed in a Radiation Area. The individual who will perform the activity has a year to date exposure of 3160 mR (TEDE). The dose rate in the area where the emergency evolution will be performed is 80 mR/hr, and there is no airborne radioactivity present.

Determine the worker's MAXIMUM stay time while performing the activity to prevent exceeding any administrative dose guidelines.

NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A3 RO Questions

Beaver Valley Power Station Procedure Number:

1/2-ADM-1601

Title:

Unit:

Level Of Use:

Radiation Protection Standards 1/2 General Skill Reference Revision:

Page Number:

5 19 of 126 If an adult's accumulated occupational dose for the year reaches or exceeds one or more of the following Guides, the individual should not receive additional occupational exposure unless authorized as specified in the site Administrative and Radiation Protection procedures:

TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) from external and internal exposure:

TOTAL ORGAN DOSE EQUIVALENT (TODE) from internal and external exposure:

EYE (LENS) DOSE EQUIVALENT (LDE) from external exposure:

SHALLOW-DOSE EQUIVALENT to the skin of the WHOLE BODY (SDE-WB) from external exposure:

SHALLOW-DOSE EQUIVALENT to any EXTREMITY (SDE-X) from external exposure:

4 rems (40 mSv) 40 rems (400 mSv) 12 rems (120 mSv) 40 rems (400 mSv) 40 rems (400 mSv) 7.2.3.3 Individual Exposure Control 7.2.3.3.1 Authorization - To control Routine exposure or a Planned Special Exposure, an individual may be authorized to receive an appropriate fraction of the external and/or internal exposure that would result in an accumulated dose equal to a Guide or Limit.

7.2.3.3.2 Restriction/Review - When an individual has received or exceeded the amount of exposure authorized, the individual should be restricted from receiving occupational dose unless additional exposure is authorized. Prior to authorizing additional exposure, the individual's dose status should be reviewed, including the results of TLD badge processing and/or internal dose assessments, if the individual's exposure may exceed the preset percentage, e.g., 80% of the applicable guide.

7.2.3.3.3 TLD Badge Exchange/Bioassay - if an individual's TLD badge is exchanged or if the individual is monitored with a bioassay before the individual's authorized exposure is expended, the unused portionof the authorized exposure may be used while the TLD badge is being processed or the bioassay results are being evaluated.

7.2.3.2.1 7.2.3.2.2 7.2.3.2.3 7.2.3.2.4 7.2.3.2.5

Procedure Number:

Beaver Valley Power Station 1/2-ADM-1630

Title:

Unit:

Level Of Use:

RADIATION WORKER PRACTICES 1/2 General Skill Reference Revision:

Page Number:

1 3 1

43 of 45 7.6.2.1.3 Have all other work party members check their accumulated dose reading and indicated dose rate.

7.6.2.1.4 If practicable, immediately exit the RCA after placing your work in a safe configuration, as applicable. Notify Health Physics. If it is not practicable to immediately leave the RCA (e.g., if the alarm occurs while working in subatmospheric containment), notify Health Physics as soon as possible and request instruction.

3.1 8 )

7.6.2.1.5 Logging out after this type of alarm will result in the generation of an access control terminal printer tape. Take this tape to Health Physics after log off.

7.6.2.2 Dose rate alarms which occur during transit to or from the local work area may occur when passing localized higher radiation dose rate areas. This type of alarm (transient in nature) does not typically indicate a problem. The potential for a transit dose rate alarm will be included in briefings performed by Health Physics.

Notify Health Physics if any unexpected (unbriefed) dose rate alarm occurs, regardless of where the alarm occurs.

7.6.2.3 In the event of a dose rate alarm at the local work area take the following actions:

7.6.2.3.1 Note the indicated dose rate.

7.6.2.3.2 Note the accumulated dose reading.

7.6.2.3.3 Have all other work party members check their indicated dose rate and accumulated dose reading.

7.6.2.3.4 Leave the work area. Work party members are not permitted to complete a task while in dose rate alarm.

7.6.2.3.5 Notify the radiation technician providing coverage for the job/area. Health Physics will determine the cause of the increased radiation levels and take appropriate corrective actions (e.g., a resurvey of the area may be required to raise the default dose rate alarm.(3.1.5) 7.6.2.3.6 Logging out after this alarm will result in the generation of an access control terminal printer tape. Take this tape to Health Physics.

7.6.2.4 A battery alarm indicates that at least eight hours of ARD battery power remains.

In the event of a battery alarm take the following actions:

7.6.2.4.1 Note the accumulated dose reading.

Note the indicated dose rate reading.

7.6.2.4.2

Appendix C Job Performance Measure Form ES-C-1 Worksheet BVPS Unit 2 ADorove Emeraency Exposure Task No.:

1350-006-03-023 JPM No.:

2002 NRC A3 SRO K/A

Reference:

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

X Simulator Actual Performance:

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

A Site Area Emergency has been declared at Unit 2.

An individual is trapped and bleeding in a Locked High Radiation Area and immediate response is necessary to save their life.

It has been clearly determined that actions establishing adequate or equivalent protection, with less dose are not readily available.

"* A qualified individual has volunteered to perform the rescue activity and has been briefed on risks of projected radiation exposure.

"* The individual has a year to date exposure of 880 mR (TEDE).

"* The area dose rate is 1,110 mR/hr and there is no airborne radioactivity present.

"* The rescue activity could take up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Correctly determine requirements to authorize the rescue activity.

None EPP/IP 5.3 Emergency Exposure Criteria and Control, Rev. 8 EPP/IP 5.3, Rev. 8 As the Emergency Director, you are to evaluate the situation and determine and authorize actions as appropriate.

No 5 minutes NUREG 1021, Revision 8, Supplement 1 Facility:

Task

Title:

2.3.4 (3.1)

X BVPS NRC A3 SRO

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC A3 SRO (Denote Critical Steps with an asterisk)

Performance Step: 1 Evaluates Attachment 1, Emergency Exposure Authorization Limits.

Standard:

Determines emergency exposure authorization is allowed.

Comment:

Terminating Cue:

When the Candidate reports their determination for authorizing the exposure, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC A3 SRO

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC A3 SRO Job Performance Measure No.:

2002 NRC A3 SRO Examinee's Name:

Date Performed:

Facility Evaluator:

N/A Number of Attempts:

N/A Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC A3 SRO

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET 2002 NRC A3 SRO INITIAL CONDITIONS:

INITIATING CUE:

"* A Site Area Emergency has been declared at Unit 2.

"* An individual is trapped and bleeding in a Locked High Radiation Area and immediate response is necessary to save their life.

"* It has been clearly determined that actions establishing adequate or equivalent protection, with less dose are not readily available.

"* A qualified individual has volunteered to perform the rescue activity and has been briefed on risks of projected radiation exposure.

"* The individual has a year to date exposure of 880 mR (TEDE).

"* The area dose rate is 1,110 mR/hr and there is no airborne radioactivity present.

"* The rescue activity could take up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

As the Emergency Director, you are to evaluate the situation and determine and authorize actions as appropriate.

NUREG 1021, Revision 8, Supplement I BVPS NRC A3 SRO

EPPAIP 5.3 A5.735B FOR TRAINING USE ONLY EMERGENCY EXPOSURE CRITERIA AND CONTROL Rev. 8 I

FOR TRAINkiNG US, ONLY EPP/Implementing Procedure EPP/IP 5.3 A5.735B EMERGENCY EXPOSURE CRITERIA AND CONTROL APPROVAL PAGE Intent Related Revision __ Yes X No IF YES OSC and Site Approval OSC Meeting Number Reviewed Manager, Emergency Preparedness Approved Director, Plant Services Manager, Emergency Preparedness Director, Plant Services Rev. 8 Date Date IF NO Reviewed Date Approved Date Date I

I i

F OR TAAINING USE ONLY EPP/lmplementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL A.

PURPOSE This procedure provides guidance and criteria for dose limitation in situations where it may be necessary for individuals to exceed established exposure limits to save a life or to minimize the consequences of an accident. Authorization for such exposures is provided by 10 CFR 50.47(B)(1 1).

B.

REFERENCES 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.

2.0 ICRP Publication 26, "Recommendation of the International Commission on Radiological Protection" 3.0 ICRP Publication 28, "The Principals and General Procedures for Handling Emergency and Accidental Exposures of Workers" 4.0 EPP 400-R-92/01 (and subsequent revisions), "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" 5.0 Title 10, Code of Federal Regulations Part 20 6.0 Title 10, Code of Federal Regulations Part 50 7.0 NUREG-0654/FEMA-REP-1 "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."

8.0 BVPS Health Physics Manual 9.0 NUMARC, Implementation of the New EPA Protective Action Guides in Existing Emergency Programs Rev. 8 1

FOR TRAINING USE ONLY EPP/Implementing Procedure EPPAP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL C.

RESPONSIBILITIES The Emergency Director has the responsibility and authority to ensure that the radiation exposure of personnel performing functions necessary to contend with the emergency condition, are maintained As Low As Reasonably Achievable (ALARA) and in keeping with the provisions of this EPP/IP. The Emergency Director is the only individual who may authorize dose extensions in excess of 10 CFR 20.

D.

ACTION LEVELS/PRECAUTIONS/CRITERIA 1.0 ACTION LEVELS 1.1 An emergency condition at the Beaver Valley Power Station has resulted in radiation levels within the Station greatly in excess of normal levels which require special considerations for exposure control.

2.0 PRECAUTIONS 2.1 Emergency exposure limits apply only to BVPS and contractor personnel who are qualified as radiation workers at the Beaver Valley Power Station and have been issued BVPS dosimetry.

2.2 The establishment of these emergency exposure controls in no manner suggests that the exposures are acceptable. Although 10 CFR 50.47(b)(1 1) requires that the EPP contain emergency exposure control measures, any exposure greater than 10 CFR 20 provisions is reportable to the NRC.

3.0 CRITERIA 3.1 Definitions 3.1.1 Accident Exposure:

Exposure to radiation or radioactive materials that results from an unexpected event.

Accident exposure refers to the immediate consequences of the unexpected event and the immediate corrective/mitigative actions of personnel present at the scene when the event occurred. Accident exposures are not controlled by the Health Physics Manual (HPM) or the Emergency Preparedness Plan (EPP), but may be reportable to the NRC under 10 CFR 20 and/or 10 CFR 50.72.

Rev. 8 2

FOR TRAINING USE ONLY EPP/Implementing Procedure EPPAIP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.1.2 Emergencv Exposure:

Exposure to radiation or radioactive materials that is the result of actions taken in response to an emergency condition classified and declared pursuant to the BVPS Emergency Preparedness Plan.

Emergency exposure refers to radiation exposure caused by those assessment, corrective, and mitigative actions that are required on an immediate basis to save human lives, or to prevent or minimize the collective exposure of large populations.

Such activities are directed by the Control Room or by the TSC/EOF. Planned Special Exposures (see 3.1.4) are not considered emergency exposures.

3.1.3 Life Savin! Action: Those actions related to the search and rescue of injured persons.

3.1.4 Planned Special Exposure (PSE): As defined in 10 CFR 20, an infrequent exposure to radiation, separate from and in addition to the annual dose limits. The HPM delineates requirements to be met in classifying an exposure as a PSE. PSEs might be warranted in the recovery phase.

However, it is unlikely that the PSE requirements could be met during the initial phases of the emergency.

3.2 All emergency exposure extensions are subject to the following conditions:

3.2.1 All exposures shall be maintained such that the TEDE is as low as reasonably achievable during emergencies, noting that it may be necessary to tradeoff individual personal exposure against collective population exposure offsite, or in the interest of saving human lives.

3.2.2 Emergency exposure limits apply only during emergencies declared pursuant to the Emergency Preparedness Plan.

3.2.3 The Emergency Director, with the advice of the Radiological Controls Coordinator, shall approve all emergency exposures in excess of 10 CFR 20 limits. This approval shall be documented.

However, the approval may be relayed verbally and documented later.

Rev. 8 3

FOR TRAINING USE ONLY EPP/Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.2.4 Emergency Exposure limits apply only to BVPS and contractor personnel who are qualified as radiation workers at the Beaver Valley Power Station and have been issued BVPS dosimeters.

3.2.5 Personnel who have received previous accident or emergency exposure in excess of 25 rem TEDE shall not participate in further emergency exposure situations.

3.2.5.1 Since accident and emergency exposures are not required to be included in personnel exposure histories, it may be necessary to interview contractor and visitor personnel regarding such exposures.

3.2.6 Personnel who have declared pregnancy in accordance with the HPM, shall not participate in emergency exposure situations.

3.2.7 With the exception of emergency exposures in excess of 25 rem TEDE, participation in emergency exposure situations need not be voluntary on the part of the individual emergency worker.

3.2.8 The dose of personnel authorized to receive emergency exposures shall be monitored and recorded as provided in the Health Physics Manual.

3.3 Exposure Limitation 3.3.1 Except as provided below, control of radiation exposures during an emergency shall be governed by the HPM.

3.3.2 The exposure of emergency response organization personnel should be maintained such that routine radiation exposure limits and administrative controls contained within the HPM are met.

These routine exposure limits may be exceeded during the performance of emergency activities identified in paragraphs 3.3.3

- 3.3.5, provided that the conditions of paragraph 3.2 are met.

Rev. 8 4

FOR TRAINING USE ONLY EPP/lmplementing Procedure EPPAIP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.3.3 For activities performed on an immediate basis to prevent the failure of equipment necessary to protect the public health and safety, the TEDE of personnel directly involved shall not exceed 10 rem.

This limit is applicable only if actions establishing adequate or equivalent protection, with a lower dose consequence, are not readily available.

3.3.4 For activities necessary on an immediate basis (1) to save human life, (2) to restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, or (3) to prevent or mitigate a release of radioactivity to the environment for which offsite protective measures may be required, the TEDE of personnel directly involved shall not exceed 25 rem. This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available.

3.3.5 For activities necessary on an immediate basis (1) to save human life, (2) to restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, or (3) to prevent or mitigate a release of radioactivity to the environment for which offsite protective measures may be required, the TEDE of personnel directly involved may exceed 25 rem, provided:

3.3.5.1 This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available, and, 3.3.5.2 Personnel assigned to these activities shall be volunteers, and, 3.3.5.3 Personnel assigned to these activities shall be briefed on, and understand, the risks associated with the estimated radiation exposure. For life saving activities, this briefing shall include a discussion on the probability of a successful rescue, and, Rev. 8 5

FOR TRAINING USE ONLY EPP/Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.3.5.4 Concurrence of the Senior Vice President, or designee, shall be obtained for any exposure projected to exceed 75 rem TEDE.

3.3.6 In addition to the TEDE limits established above, the dose equivalent to the lens of the eye shall be limited to three (3x) the limits specified in paragraph 3.3.3 and 3.3.4 above. The CDE to any organ (including the skin and body extremities) shall be limited to ten (lox) the limits specified in paragraph 3.3.3 and 3.3.4 above.

3.4 The internal exposure of BVPS emergency workers performing activities in the environment (i.e., outside plant buildings) is monitored and controlled as follows:

3.4.1 Monitoring of internal exposure and assessment of CEDE may be waived for BVPS field monitoring team members under the following conditions:

3.4.1.1 The emergency involves a substantial core melt sequences with actual or potential early containment failure or bypass, and, 3.4.1.2 The release plume is present in the areas where the personnel are assigned, and, 3.4.1.3 An evacuation of the public has been ordered, but is incomplete, and, 3.4.1.4 The field monitoring team is assigned tasks out-of doors associated with quantifying an unmonitored release from the plant in support of decisions related to the need for extending protective measures, and, Rev. 8 6

FOR TRAINING USE ONLY EPP/Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.4.1.5 If the DDE is likely to exceed 5 rem (i.e., assumes DDE to TEDE ratio of 5) for the duration of the exposure, personnel involved shall be volunteers, and, shall have been briefed on, and understand, the risks associated with the estimated radiation exposure and the uncertainty regarding the unmonitored CEDE, and, 3.4.1.6 If the DDE is likely to exceed 5 rem (i.e., assumes DDE to TEDE ratio of 5) potassium iodide shall be issued, and, 3.4.1.7 Conditions for emergency exposure delineated in paragraph 3.2 apply to these individuals.

3.4.2 Monitoring of internal exposure and assessment of CEDE of emergency personnel working out-of-doors shall be accomplished by establishing pocket dosimeter administrative guides set at that value of DDE that would maintain the sum of the DDE and CEDE below limits specified in paragraph 3.3. In addition:

3.4.2.1 These adjustments should be made using EDE to TEDE ratios determined from dose projections performed during the emergency using actual release source terms, if available.

Ratios determined prior to the release from default source terms may be useful as bounding values.

3.4.2.2 These dosimeter administrative guides shall be adjusted on the basis of actual field monitoring data, as these data become available, and, 3.4.2.3 Conditions for emergency exposure delineated in paragraph 3.2 apply to these individuals.

Rev. 8 7

FOR TRAINING USE ONLY EPP/Implementing Procedure EPP/]P 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.4.3 Monitoring of internal exposure and assessment of CEDE is not required if the release has not started, or if plume is no longer present, as this reduces the potential for uptake such that CEDE is negligible. In this case, emergency worker administrative guides are based on DDE.

3.5 Post-Exposure Evaluations 3.5.1 Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance.

3.5.2 An exposure evaluation shall be performed to determine the individual dose.

This dose may include assessment of the following dose quantities as applicable to the exposure situation:

SDE, DE, DDE, ALL, CDE, CEDE, and TEDE. This evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results.

This evaluation shall be documented in an appropriate format and filed with the individual's exposure records. Appropriate reports shall be submitted to the Onsite Safety Committee and the USNRC.

3.5.3 If an individual's external dose exceeds 10 rem DDE, 30 rem dose equivalent to the lens of eye, and/or 100 rem dose equivalent skin or an extremity, the details of the exposure incident shall be brought to the attention of a physician.

The physician shall determine the need, extent, and nature of any clinical, biological, or biochemical examinations.

3.5.4 If an individual's external dose exceeds 25 rem DDE, 150 rem dose equivalent to the lens of eye, and/or 250 rem dose equivalent skin or an extremity, the individual shall be examined by a physician.

The physician shall determine the need, extent, and nature of any clinical, biological, or biochemical examinations, or necessary medical surveillance.

Rev. 8 8

-R TRAINING U t ONLY EPP/Implementing Procedure EPPAIP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL 3.5.5 If an individual's intake exceeds 1.0 ALL, the details of the exposure incident shall be brought to the attention of a physician.

The physician shall determine the need, extent, and nature of any clinical, biological, biochemical examinations, or necessary medical treatment.

E.

PROCEDURE 1.0 In the event emergency exposure is necessary, the following actions should be performed. Although it is preferable to perform and document these steps prior to the exposure, if necessary the Emergency Director may verbally authorize the increased exposure and complete the documentation at a later time.

1.1 Per Attachment 1, determine the appropriate Emergency Exposure Authorization Limit.

1.2 Complete Section A of the Emergency Exposure Authorization Form (Attachment 2). Line 6 of the form must be signed by the Emergency Director.

1.3 The individual to receive the increased exposure will complete Section B.

1.4 The individual will be briefed on the radiological and other conditions in the area (or expected in the area), the tasks to be performed, ALARA measures applicable to the task, and contingency measures, prior to entry to the affected area. Included in this briefing shall be a discussion of the biological risks associated with the exposure to be incurred.

1.5 The individual performs the assigned tasks.

1.6 Following the exposure, the Radiological Controls Coordinator, or designee, will complete and sign Section C and D of the Emergency Exposure Authorization Form.

Rev. 8 9

FOR TRAINING USE ONLY EPP/lmplementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL F.

FINAL CONDITIONS This procedure will be terminated when all sections of Attachment 1, "Emergency Exposure Authorization Form" have been completed and/or assignments are made for necessary exposure reports.

The original of Attachment 1 should be filed in the individual's personnel exposure history records and a copy sent to the Manager, EPP for inclusion in event records.

G.

ATTACHMENTS 1.0 Emergency Exposure Authorization Limits 2.0 Emergency Exposure Authorization Form Rev. 8 10

FOR TRAINING USE ONLY EPP/Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL ATTACHMENT 1 (1 of 1)

EMERGENCY EXPOSURE AUTHORIZATION LIMITS Rev. 8 I

11

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

Task

Title:

K/A

Reference:

BVPS Unit 2 Emergency Plan Administrative Questions 2.4.29 (2.6) 2.4.39 (3.3)

Task No.:

N/A JPM No.:

2002 NRC A4 RO Examinee:

Facility Evaluator:

N/A Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

N/A Both questions answered correctly.

None EPP/I-4, Site Area Emergency, Rev. 17 EPP/IP 5.1, Search And Rescue, Rev. 7 None N/A No N/A NUREG 1021, Revision 8, Supplement 1 BVPS-2 NRC A4 RO Questions

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC A4 RO Questions ANSWER KEY RO Admin A4 Question I List FOUR Emergency Response Facilities that are required to be activated upon declaration of a Site Area Emergency at BVPS.

ANSWER:

Operations Support Center (OSC)

Technical Support Center (TSC)

Emergency Operations Facility (EOF)

Joint Public Information Center (JPIC)

Reference:

EPPII-4, Site Area Emergency, Rev. 17 NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A4 RO Questions

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC A4 RO Questions ANSWER KEY RO Admin A4 Question 2 An Alert level classification has been declared due to an in-plant fire. An individual has been determined to be missing following an evacuation of an affected area, as discovered during personnel accountability efforts. The individual is believed to be injured or trapped in an area away from the area of the fire.

Which activity takes precedence, fighting the fire or rescuing the trapped individual?

ANSWER:

Rescue of a victim shall take precedence over fire-fighting efforts.

Reference:

EPP/IP 5.1, Search And Rescue, Rev. 7 NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A4 RO Questions

Appendix C Page 4 of 6 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC A4 RO Questions Job Performance Measure No.:

2002 NRC A4 RO Examinee's Name:

Date Performed:

Facility Evaluator:

N/A Number of Attempts:

N/A Time to Complete:

Question Documentation:

Question 1:

Response

Question 2:

Response

Result:

SAT Examiner's Signature:

UNSAT Date:

NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A4 RO Questions

Appendix C Page 5 of 6 Form ES-C-1 JPM CUE SHEET 2002 NRC A4 RO Questions CANDIDATE COPY RO Admin A4 Question 1 NO Reference Allowed List FOUR Emergency Response Facilities that are required to be activated upon declaration of a Site Area Emergency at BVPS.

NUREG 1021, Revision 8, Supplement 1 BVPS-2 NRC A4 RO Questions

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET 2002 NRC A4 RO Questions CANDIDATE COPY Question 2 RO Admin A3 NO Reference Allowed An Alert level classification has been declared due to an in-plant fire. An individual has been determined to be missing following an evacuation of an affected area, as discovered during personnel accountability efforts. The individual is believed to be injured or trapped in an area away from the area of the fire.

Which activity takes precedence, fighting the fire or rescuing the trapped individual?

NUREG 1021, Revision 8, Supplement I BVPS-2 NRC A4 RO Questions

Procedure Number.

Beaver Valley Power Station EPP-Nm4

Title:

Unit:

Level Of Use:

1/2 General Skill Reference SITE AREA EMERGENCY Revision:

Page Number.

17 4 of 14 NOTE:

Activating the Emergency Response Organization beepers will begin activation of the following:

Technical Support Center (TSC), Operations Support Center (OSC), Emergency Operations Facility and the Joint Public Information Center (JPIC).

1.6 A SRO (from the unaffected Unit) SHALL complete the blanks below and notify the Emergency Response Organization (ERO).

1.6.1 From a PAX phone, dial 4370.

1.6.2 Interrupt the greeting by IMMEDIATELY entering XXXX.

1.6.3 When prompted, enter scenario number XXXX.

1.6.4 When prompted, verify scenario number (9 for YES or 6 for NO).

(Continue)

"This is (Your Name) at Beaver Valley Power Station. At (time) hrs.,

Unit has declared a SITE AREA EMERGENCY due to:

(Choose One and Continue)

a. Report to your emergency facility.

I repeat, report to your emergency facility.

OR

b. Report to your alternate emergency facility. I repeat, report to your alternate emergency facility."

CHECK LI 1:1 0

EPP/lmplementing Procedure SEARCH AND RESCUE 2.0 PRECAUTIONS 2.1 If an individual is trapped or disabled in a high radiation area, the rescue must be performed as expeditiously as possible to minimize the dose to the victim and the doses to the rescue personnel, and to ensure that first aid can be provided as soon as possible.

2.1.1 In an emergency situation, exposure in excess of normal limits to rescue and first aid personnel is appropriate if necessary to save a life. Refer to EPP/IP-5.3, "Emergency Radiation Exposure Criteria and Control".

2.2 Rescue of a victim shall take precedence over fire-fighting efforts, unless the fire must be suppressed to effect rescue, or if the fire poses an immediate threat to the lives of others.

Rescue of a victim shall take precedence over isolation of high energy fluids (Steam, hot water under pressure, hydraulic fluids, etc.) unless isolation of the system is necessary to effect rescue; or if failure to isolate the system will seriously affect reactor safety or will place the lives of other personnel in immediate danger.

E.

PROCEDURE 1.0 Initial Response 1.1 As soon as it is recognized that one or more individuals are missing, the security supervisor at the Central Alarm Station shall attempt to determine the possible location of the missing individuals, by paging the individual, by conferring with the individual's supervisors and co-workers, via brief searches of the last known location (if possible), and/or calling the individual's home.

If following these efforts, the individual is still unaccounted for, the Security Coordinator shall be notified and the following information reported:

Name(s) of individual(s) missing Summary of efforts performed to locate the individual(s)

Last known location of the individual(s)

Rev. 7 EPP/IP 5.1 2

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

Task

Title:

K/A

Reference:

BVPS Unit 2 Classify an EPP Event 2.4.41 (4.1)

Task No.:

JPM No.:

1350-004-03-023 2002 Audit A4 SRO Scenario No. 1 Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The simulator scenario just completed.

The proper EPP classification is made within 15 minutes.

None EPP/I-1 B, Recognition and Classification of Emergency Conditions, Rev. 2 None Classify the events in the scenario just completed in accordance with EPP/I-1 B, Recognition and Classification of Emergency Conditions.

YES 5 minutes NUREG 1021, Revision 8, Supplement 1 X

BVPS-2 Audit A4 SRO

Appendix C Page 2 of4 Form ES-C-1 PERFORMANCE INFORMATION 2002 Audit A4 SRO Scenario No. 1 (Denote Critical Steps with an asterisk)

Note: The Candidate is being evaluated on classifying the scenario events just completed.

Performance Step: 1 Classify the event in accordance with the Emergency Plan.

Standard:

Properly classifies the event within 15 minutes.

Scenario #1: Site Area Emergency based on Tab 2.3, Failure of Rx Protection Scenario #2: Alert based on Tab 1.2, RCS Barrier Scenario #3: Alert based on Tab 2.3, Failure of Rx Protection, or Tab 3.1, Loss of Power NOTE:

A loss of both 4kV busses for greater than 15 minutes is classified as a Site Area Emergency per Tab 3.1.

Scenario #4: Alert based on Tab 1.2, RCS Barrier Comment:

Terminating Cue:

When the Candidate classifies the event, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I BVPS-2 Audit A4 SRO

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION 2002 Audit A4 SRO Scenario No. I Job Performance Measure No.:

2002 NRC A4 SRO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS-2 Audit A4 SRO

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET 2002 Audit A4 SRO Scenario No. 1 INITIAL CONDITIONS:

INITIATING CUE:

The simulator scenario just completed.

Classify the events in the scenario just completed in accordance with EPP/I-1 B, Recognition and Classification of Emergency Conditions.

NUREG 1021, Revision 8, Supplement 1 BVPS-2 Audit A4 SRO

ML030220415

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