Text

Final - Section a Operating (Folder 3)
	ML050900374
Person / Time
Site:	Beaver Valley
Issue date:	01/15/2005
From:	Hynes C; FirstEnergy Nuclear Operating Co
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	Download: ML050900374 (72)
	v • d • e

Appendix C Job Performance Measure F

o

~

ES-C-1 Worksheet F ac i I i t y :

BVPS Unit 2 Task No.: 1300-023-03-023 Task

Title:

Amrove a TaaainQ Reauest WA

Reference:

2.2.13 (3.8)

Examinee:

Facility Evaluator:

JPM No.: 2005 NRC SRO Admin No. 3 NRC Examiner Date:

Method of testina:

Simulated Performance:

Actual Performance:

X Classroom X

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

Initial Conditions:

The plant is operating at 100% power with all systems in their normal operating alignment. A tagout section has been prepared to isolate and drain [2QSS*P22A], Refueling Water Cooling Pump for maintenance.

Task Standard:

Review a clearance tagout section and identify errors.

Required Materials:

None General

References:

NOP-OP-1001, Clearancenagging Program, Rev. 4 Handouts:

Tagging Section with errors 20M-13.3.8.1, Valve List - 2QQS, Rev. 9 20M-13.3.C, Power Supply And Control Switch List, Issue 4, Rev. 7 OP Manual Fig. No. 13-2, Quench Spray System, Rev. 13 NOP-OP-1001, Clearancenagging Program, Rev. 4 Initiating Cue:

The Shift Manager directs you to conduct a review of the attached tagout section that is ready for approval for completeness and accuracy.

Report your results when finished.

Time Critical Task:

Yes Validation Time:

12 minutes BVPS-2 NRC ADMIN NO. 3 NUREG 1021, Revision 9

Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 3 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

NOTE:

This task is normally performed using the eSOMS clearance computer and signed electronically. If necessary, for the purpose of this JPM, inform the Candidate to review a hardcopy of the tagout for approval in place of performing an electronic review.

4 Performance Step: 1 Review the tagout section for accuracy and completeness Standard:

Candidate verifies tagout section is appropriate for the task.

Standard:

Candidate identifies and reports the following tagout errors:

Breaker MCC-2-17-6C is tagged in the On position. The correct position is Off.

Valve 2QSS-21 is not a correct discharge isolation point (2QSS*P22B vs. P22A). The correct valve is 2QS-20.

Valve 2QSS-239 is tagged in the Shut position. The correct position is Open.

CUE:

If the Candidate asks for direction following identification of the first error, direct the Candidate to review the remainder of the tagout section.

Comment:

I Terminating Cue:

When the Candidate reports the results of the review, the evaluation for I

this JPM is complete.

STOP TIME:

BVPS-2 NRC ADMIN NO. 3 NUREG 1021, Revision 9

Clearance Coversheet Tagout: 2B W 1 Clearance: 2W10-13 -QSS-004 Component to be Worked:

Attribute Description Equipment Required For Mode Change Restored/Removed Prior to Mode ESF Clearance Required Schedule Clearance Type Time to Post (In Minutes) 7 8 to Remove (In Minutes)

BVPS Attribute I

Value No NOT APPLICABLE No 2w10 Danger A9.330. W 02/28/05 1O:OO Number / Equipment ID Description 20001 561 0 33-007888-000 12 WEEK SCHEDULE - REPLACE MECHANICAL SEAL BORIC ACID WAS CLEANED PER WORK ORDER #02-023791-000, LEAKAGE WAS FROM THE MECHANICAL PRTlAW D SEAL AND NEEDS REPLACED. (See 02-09422 CA 4)

IFMP QSS-P22A-MOTOR

- - - - - - - - - - - - - - - i OOLING PUMPS CHANGE RESERVOIR OIL AND OBTAIN OIL SAMPLE FOR ANALYSIS 00091 064 HANGE RESERVOIR OIL AND OBTAIN OIL SAMPLE FOR ANALYSIS REFUELING WATER bRTjAWD IREFUELING WATER COOLING PUMPS QSS-P22A 00063975

/2QSS-P22A LUBE MOTOR BEARINGS REFUELING WATER COO LUBE MOTOR BEARINGS REFUELING Clearance Verification:

Status Description Prepared Prepared By Reviewed Reviewed By Second Reviewed Second Reviewed By 1

Verification Date I

R.O.-#I i

Loday Name R.O. #2 Today+

Page 1 of 2 NO P - 0 P-1001 proved storation Review sued for Work Approved By Issued for Work By Restoration Review By

Status nemoval Authorized aarance Closed Ground Disc List:

Description Name Verification Date Removal Authorized By Clearance Closed Bv NOP-0 P-1001 Page 2 of 2

Clearance Tq

'st 8 VPS Tagout: 2BVh

-I Clearance: 2WlO-13 -QSS-004

REFUELING WATER COOLING PUMP MOTOR THERMAL OVERLOAD

2-CNTB-735-CONTROL ROOM 0

Caution 3 1 4 9 KNIFE SWITCH FOR A (2QSS-P22Al 1' 2-CNTB-707 -

-BAY14 I 0

paution )2QSS-P22A-CS REFUELING WATER COOLING PUMP P22A SUCTION NORTH BY PUMP 2-SFGB-718 -

-722 0

Danger 2QSS-239 REFUELING WATER COOLING PMP P22A DISCH DRAIN 2-SFGB-718 -

-NORTH BY PUMP 13-21E4

__I._

+--

Place. 2n Verif DatelTirn r

Rest Restoration As Left Seq Configuration Configuratic Notes 7 TAGREMOVED

- - - - - - I --.-I

- - - - TAG REMOVED A9.330. W 02/28/05 7 0:OO Rest. l s l Verif DatelTi mc NOP-OP-I001 Page I of 2

Clearance Tal t

Tagout: 2BVP-,,-1 Clearance: 2W10-13 -QSS-004 Tag No.

0 Serial

~-

Tag Equipment Type _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Equipment Description Equipment Location Danger 2QSS-234 REFUELING WTR COOLING PUMP P22A SUCTION TCN BY PUMP 2-SFGB-718 -

-NORTH B VPS Component Print Number 2QSS-21 13-2 F4 F

i i

~

i i

i

~

d

[

Seq onfiguration Notes Datemime Datemime 2QSS-16 13-2 E3 2QSS-239 13-2 E4 13-2 E4 2QSS-234

~-

7 PEN I

I I

Component MCC-2-17-6C A9.330. W Annotations OPENING MCC-2-17-6C BRINGS IN ANN. A6-1 F 02/28/05 I0:OO NOP-0 P-1001 Page 2 of 2

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

BVPS Unit 2 Task No.:

1320-008-03-023 Task

Title:

Determine Action Required For Failed AC JPM No.:

2005 NRC SRO Sources Surveil lance Admin No. 1 WA

Reference:

2.1.12 (4.0)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testinq:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

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

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The plant is operating at 100% power with all systems in their normal operating alignment. The 2-1 EDG was declared inoperable and removed from service 30 minutes ago due to a ruptured engine cylinder. The PO has completed 20ST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification.

Procedure errors are identified and Technical Specification action requirements are determined for a failed surveillance test.

None 20ST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification, Rev. 8 BVPS Unit 2 Technical Specifications LCO 3.8.1.1 20ST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification, Rev. 8 (marked up copy)

BVPS Unit 2 Technical Specifications LCO 3.8.1.1 The Shift Manager directs you to review the completed 20ST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification for completeness. Report your results when finished.

No 14 minutes BVPS-2 NRC ADMIN NO. 1 NUREG 1021, Revision 9

AppendixC Page 2 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

.I Performance Step: 1 Review procedure for completeness.

Standard:

Candidate determines that signoffs are missing for the following steps:

. VI.D.l (Operator performing test has reviewed procedure)

VII.A.l.b (Class 1 E power through the USST's or SSST's)

Comment:

.I Performance Step: 2 Review Data Sheet 1 for completeness.

Standard:

Candidate determines that the neon light for 4KV breaker ACB 342B is marked as OFF.

NOTE:

This is the required lineup for live bus transfer that would be indicated if the neon light was ON.

Comment:

BVPS-2 NRC ADMlN NO. 1 NUREG 1021, Revision 9

Appendix C Page 3 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 PERFORMANCE INFORMATION 4 Performance Step: 3 Determine Technical Specification Action Statement requirements.

Standard:

Candidate determines that OST does not satisfy the Acceptance Criteria.

Standard:

Candidate identifies applicability of T.S. Action Statement 3.8.1.1.c with one offsite circuit and one diesel generator inoperable.

NOTE:

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

handout.

NOTE:

Refer to attached Technical Specification LCO 3.8.1.1 Action c for applicable requirements for an inoperable offsite circuit and diesel generator.

Comment:

Terminating Cue:

When the Candidate identifies the Technical Specification action statement requirement, the evaluation for this JPM is complete.

r STOP TIME:

BVPS-2 NRC ADMIN NO. 1 NUREG 1021, Revision 9

Prepared by Date W. K. Giffrow 2/7/02 Reviewed by Date R. C. Plummer 2/15/02 OSC Meeting No.

Date OSC Not Required A9.330B Pages Issued 1 through 14 Validated by Date N/A DRR-02-00634 Beaver Valley Power Station Unit 2 20ST-36.7 Offsite to Onsite Power Distribution System Breaker Alignment Verification Revision 8

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 2 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Alignment Verification Table Of Contents I.

(I.

Ill.

IV.

V.

VI.

v11.

VIII.

PURPOSE 5

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

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

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

5 INITIAL CONDITIONS................................................................................................................. 5 lNSTRUCTlONS.......................................................................................................................... 7 DATA SHEETS, TABLES, FIGURES, AND ATTACHMENTS....................................................

10 DATA SHEET 1 1 1 DATA SHEET 2.........

12 IX.

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

13 Table Of Contents

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 3 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Alignment Verification Performed in Mode(s): ALL TEST RESULTS: (Completed by Performer)

(>' or N/A)

Frequency: W Required for Mode(s): 1, 2, 3, 4, 5, 6, #, @

ISurveillance Requirements: 4.8.1.1.1.a & 4.8.1.2 IDate I Time Completed: Today

/ Now Total Manhours:

0.5 Name (Print)

Initial PERFORMED BY:

Plant Operator PO E-.--.-

Test Completed SATISFACTORY Problems Encountered (See Problem Sheet) c 4

Unscheduledlpartial OST (explain)

I I

2-1 EDG inoperable I

Reviewer SignatureIDate STA Review I

NSS Approval I

I I

COMMENTS: (Include Date and Initials)

I I

IC 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 preDlanned 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.l)(.'.*)

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 4 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Alignment Verification OST PROBLEM SHEET See Page and Step No. for problem description. See below for corrective action PAGE NO. STEP NO.

DESCRIBE CORRECTIVE ACTION I N IT1 ALS DATE

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 5 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Alianment Verification

1.

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 1 or Data Sheet 2.

111.

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 1 or 2, unless NSS/ANSS has been notified AND approval to operate breaker has been given.

VI.

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

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 6 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Alignment Verification DATE: Today TIME: NOW B. NSS/ANSS Siun-on CURRENT PLANT MODE: 1 1, NSS/ANSS verifies the following:

NSS / ANSS Signature SM C. Reactor Operator Siqn-on

1.

Reactor Operator perform the following:

0 Acknowledge procedure performance.

Reactor Operator Signature PO D. Procedure Performer Initial Conditions

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

Initial / Date

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 7 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Alignment Verification VII.

INSTRUCTIONS A. Test PreDaration

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.

---=-l--i-af 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.

Initial / 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 l T o d c 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.

N / A / I O d U Initial l Date

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 8 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Align men t Verification

3.

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

PO I 1oda.K Initial I Date

a.

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

N/A I Todav 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)

PO I Todav Initial I Date 6. Performance of the OST Note:

Either Step VII.B.l OR Step Vll.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.

ffllTodav 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.

PO I Todav Initial I Date

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 9 of 14 Operating Surveillance Test 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 NSSIANSS to refer to Licensing Requirements 2.5, 2.6, 2.1, and 2.2. (Otherwise Mark N/A)

PO /Todav Initial / 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.

M A / Todav Initial / Date

b.

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

/Todav Initial / Date C. Test Completion

1. Consult the acceptance criteria for acceptable performance.

A l T o d a v Initial / Date

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

--J=JTOdav Initial / Date

3.

Complete the front cover sheet.

PO /Today Initial / Date

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 10 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Alignment Verification VIII.

DATA SHEETS, TABLES, FIGURES, AND ATTACHMENTS A.

B.

C.

D.

Data Sheets

1. Without Backfeed

2.

Tables NONE Fiqures NONE Attachments NONE When Backfeeding through Main Transformer

Beaver Valley Power Station Unit 2 20ST-36.7 Revision 8 Page 11 of 14 Operating Surveillance Test Offsite to Onsite Power Distribution System Breaker Alignment Verification DATA SHEET 1 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)

ITEM 138KV BUS 2-Train A 138KV OCB 85 MTR OPER DISC SW 89-2A 2A SSST Volt. Sel.

A Bus FDR. (Phase Y)

POS A-B POS B-C POS C-A 4KV Bus 2A ACB 342A 4KV Bus 2A ACB 2A2' '

3KV Bus 2A ACB 2A10 4KV Bus 2AE ACB 2E7 138KV OCB 94 28 SSST Volt. Sel D Bus FDR. (Phase Y)

POS A-B Pos 0-C POS C-A 4KV Bus 2D ACE 3428 4KV Bus 2 0 ACB 2D12L '

4KV Bus 2DF ACB 2F7 REQUIRED POSITION OR READING ZLOSED (RED LIGHT ON)

ZLOSED (RED LIGHT ON) 125V (Note 2) 125V (Note 2) 125V (Note 2)

OPEN (DIM WHITE LIGHT ON)

(NEON LAMP ON) (Note 3)

OR CLOSED (TWO RED LIGHTS ON)

(NEON LAMP OFF)

-%ked in the DISC idisconnect) position (Note 4)

ZLOSED (RED LIGHT ON)

ZLOSED (RED LIGHT ON) 125V (Note 2) 125V (Note 2) 125V (Note 2)

OPEN (DIM WHITE LIGHT ON)

(NEON LAMP ON) (Note 3)

OR CLOSED (TWO RED LIGHTS ON)

(NEON LAMP OFF)

-ocked in the DISC idisconnect) position (Note 4) 2LOSED (RED LIGHT ON)

ZLOSED (RED LIGHT ON)

(0 or SI INITIAL)

OR (READING I INITIAL) s I PO

~

s !Po s 1 PO

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 reauired by Tech Specs to be demonstrated operable.

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

2.

3.

Illuminated neon lamp signifies that ACB is setup for Automatic Bus Transfer (During Mode 1 operation only)

4.

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

DATA SHEET 1

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:

- GENERAL NOTE - _

Specification 3.0.4.b is not applicable to diesel generators.

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'l) inoperable, demonstrate the OPERABILITY of the A.C. offsite 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; 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. 144

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 performin Surveillance Requirement 4.8.1.1.2.a.5 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 .

23 (1) 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 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.

c.

With one offsite circuit and one diesel generator of the remaining inoperable A.C. power source.

A (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 OPEMBILITY.

BEAVER VALLEY - UNIT 2 3/4 8-2 Amendment No. 79

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued)

d.

With two of the required offsite A.C. circuits inoperable, restore one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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 .

Following restoration of one offsite source, follow Action Statement a with the time requirement of that Action Statement based on the time of initial loss of the remaining inoperable offsite A.C. circuit.

e.

With two of the required diesel generators inoperable,

demonstrate the OPERABILITY of two offsite A.C. circuits 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; restore one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 .

Following restoration of one diesel generator unit, follow Action Statement b with the time requirement of that Action Statement based on the time of initial loss of the remaining inoperable diesel generator. A successful test of diesel OPERABILITY per Surveillance Requirement 4.8.1.1.2.a.5 performed under this Action Statement for a restored to OPERABLE diesel satisfies the diesel generator test requirement of Action Statement b.

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignment, indicated power availability, and

b.

Demonstrated OPERABLE at least once per 18 months by transferring (manually and automatically) unit power supply from the unit circuit to the system circuit.

(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 8-3 Amendment No. 79

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

BVPS Unit 2 Task No.: 001 1-003-01-01 3 I

Task

Title:

Review an Estimated Critical Position JPM No.:

2005 NRC SRO Calculation Admin No. 2 WA

Reference:

2.1.23 (4.0)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testinq:

S im u I at ed Perform an ce :

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

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

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

A plant startup is being performed 5 days after a reactor trip from 100% power.

Core burnup is 10,000 MWD/MTU.

RCS boron concentration is 1000 ppm.

The plant computer is NOT available.

ECP errors correctly identified and the boron concentration for startup value is calculated within the specified tolerance.

Calculator; ECP Answer Sheet 20M-50.4.F, Performing An Estimated Critical Position Calculation, Rev. 4 BV-2 Curve Book 20M-50.4.F, (with completed DATA SHEET 1)

BV-2 Cycle 11 Curves The Shift Manager directs you to perform a review of a completed ECP calculation in accordance with 20M-50.4.F, Performing An Estimated Critical Position Calculation. Report your results when finished.

No 20 minutes BVPS-2 NRC ADMlN NO. 2 NUREG 102 1, Revision 9

Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 2 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

v Performance Step: 1 (Data Sheet 1)

Standard:

(Step lV.l.1.b)

(Part 8.2)

(Part B.2)

(Part B.5)

(Part C.1, Line I )

(Part C.III, Line 1)

(Part C.V, Line 1)

(Part C.III, Line 2)

Review the ECP calculation Candidate correctly identifies the following errors and determines the boron concentration required for startup.

Performed By signature is missing.

CB-24A is incorrectly circled. Correct figure is CB-24B. 4 Control Rod reactivity values are incorrect in Columns II and Ill. -

The correct number is 725.

Reactivity Change value is incorrect. The correct number is 3707. I Reactivity Change value is incorrect (carryover from previous step)

Boron Change value is incorrect. The correct number is 501. I Boron Conc. for Startup value is incorrect. The correct number is 1501.

Boron Change value is incorrect. The correct number is 526.,-

(Part C.V, Line 2)

--,Boron Conc. For Startup value is incorrect. The correct number is 1526. (Accept value between 1476 - 1576).

Comment:

Terminating Cue:

When the Candidate completes the review of the calculation and reports the results, the evaluation for this JPM is complete.

STOP TIME:

BVPS-2 NRC ADMIN NO. 2 NUREG 1021, Revision 9

Appendix C Page 3 of 4 Form ES-C-1 2005 NRC ADMIN NO. 2 VERI F I CAT IO N 0 F COMPLETION JPM No.

Examinees Name:

Examiners Name:

Date Performed:

Fa ci I i t y Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

2005 NRC SRO No. 2 Response :

Resu It : Sat i sf acto ry/U nsat isfactory Examiners Signature:

Date:

BVPS-2 NRC ADMlN NO. 2 NUREG 1021, Revision 9

Appendix C Page 4 of 4 Form ES-C-1 2005 NRC ADMIN NO. 2 JPM CUE SHEET INITIAL CONDITIONS:

. A plant startup is being performed 5 days after a reactor trip from 100% power.

Core burnup is 10,000 MWDIMTU.

RCS boron concentration is 1000 ppm The plant computer is NOT available.

INITIATING CUE:

The Shift Manager directs you to perform a review of a completed ECP calculation in accordance with 20M-50.4.F, Performing An Estimated Critical Position Calculation. Report your results when finished.

BVPS-2 NRC ADMIN NO. 2 NUREG 1021, Revision 9

Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Operating Procedures Paae 12 of 27 Reactivity Defects I

4 ANSWER SHEET Performing An Estimated Critical I Position Calculation (1)

(11)

( I l l )

Prior to Expected at (I1 - I)

Shutdown Criticality Difference DATA SHEET 1 1 Power (Fig CB-21) (OR Consult Rx ENGR) 2040 pcm FORM ECP-1 0 (zero) pcm

(-)

- 2040 pcm A. Critical Data 2 Control Rods PRIOR TO SHUTDOWN I

(725) 1 (725) 0 pcm 600 pcm 1 (+)

+600 pcm I

Date 5 days'ago Time 0000 Boron Conc. 1000 ppm Power 100 Yo 3 Xenon (Fig. CB-23) 2606 pcm 628 pcm

' 4 Samarium (Fig CB-22)

Xenon 100 oh (Use Fig CB-12 or NIA) 0 pcm (i) - 2606 pcm 842 pcm (i) + 214 pcm 1 Samarium 100 YO (Use Fig CB-22 or NIA)

Control Rod Position A 226 C 226 B

X D

226 (11)

EXPECTED AT CRITICALITY Xenon 0

Yo (Use Fig CB-23 or N/A)

Samarium 134 yo (Use Fig CB-22 or N/A)

Control Rod Position A 226 C 226 B 226 D 130 B. Reactivity Balance - (Record absolute values in Columns I and II)

- 3707 DATA SHEET 1

Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Operating Procedures Paae 13 of 27 i

I v

ANSWER SHEET Performing An Estimated Critical Position Calculation (1)

(11)

(111)

(IV)

(V)

(I) + (11)

Boron Conc

~

Boron Change Boron Conc. at Differential Boron Worth Shutdown for Startup (Ill)+ (IV)

(Fig. CB-20)

Reactivity Change (B.5)

DATA SHEET 1 (continued)

FORM ECP-1

1.

2.

C. Critical Boron Concentration

- 7.4 pcm (501 1 1

(1501) ppm (k) +518 ppm 1000 ppm 1518 ppm (i)

-3832pcm

(-1

- 7.05 pcm

(- 3707)

(-1 ppm (k) +544 ppm 1000 ppm 1544 ppm (1)

Boron Sample ppm (11)

(111)

(IV)

Boron Conc. For Boron Deviation Differential Boron Startup C. 1. h (1) -(II)

Worth (Fig. CB-20) pcm ppm (k) ppm ppm (526)

D. Estimated Rod Position Correction (V)

Rod Worth Correction (Ill) x (IV)

(+)

pcm (1 526)

(VI)

(VI I)

(VIII)

Rod Worth Corrected Rod Corr Critical Rod Pos.

Expected At Worth Expected At (Circle Figure used) 1 '

(Flg CB-24A. 248. 24C OR Consult RX ENGR)

Criticality (V) + (VI)

Criticality (8.2) pcm pcm Steps DATA SHEET 1

7 4

Prepared by Date J. P. Keegan 09/23/02 Reviewed by Date J. E. Burnecke 09/24/02 PORC Meeting No.

Date OSC Not Required Beaver Valley Power Station Pages Issued 1 through27 Validated by Date NIA PAF-02-03855 Unit 2 20M-50.4.F Performing An Estimated Critical Position Calculation A9 3308 Revision 4

Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Operating Procedures Page 2 of 27 Performing An Estimated Critical Position Calculation

1.

PURPOSE The purpose of this procedure is to provide instruction in completing an Estimated Critical Position (ECP) calculation prior to placing the reactor in a critical condition. This procedure includes instructions for completing the ECP Form, instructions for performing a 1/M plot, and the 1/M plot figure. All other curves referenced by this procedure are found in the Operators controlled copy of the Unit 2 Curve Book and the Core Operating Limits Report in the Unit 2 Licensing Requirements Manual (LRM).

II.

PRECAUTIONS AND LIMITATIONS A. If the count rate on either source range channel rises by a factor of two or more during any step involving a boron concentration change, the operation shall be stopped immediately and remain suspended until a satisfactory evaluation of the situation has been made.

B. The approach to criticality must be plotted by an inverse count rate versus control rod position (1/M Plot) for every startup..

C. If on the approach to criticality, it is apparent that the reactor will go critical below the Rod Insertion Limit, notify the SWUS to ensure appropriate actions taken in accordance with 20M-50.4.D, Reactor Startup From Mode 3 To Mode 2.

appropriate action taken in accordance with 20M-50.4.DI Reactor Startup From Mode 3 To Mode 2.

I D. If the reactor is critical below the Rod Insertion Limit, notify the SWUS to ensure I

E. If during withdrawal of Banks C or D, it appears that the reactor will go critical at a rod height of less than 500 pcm OR Bank D is at maximum rod height for criticality, notify the SWUS to ensure appropriate action taken in accordance with 20M-50.4.D, Reactor Startup From Mode 3 To Mode 2.

A 1/M plot shall be performed on every reactor startup by a reactor engineer or another qualified individual. The approval for each rod withdrawal shall originate with the individual responsible for the 1/M plot and be communicated to, and approved by the SRO. Only the SRO may direct rod m~vernent..~

I F.

G. Estimated Critical Position calculations shall be independently verified prior to initiati~n..~

111.

INITIAL CONDITIONS A. The SM has requested this procedure be performed.

I

Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Operating P roced u res Page 3 of 27 Performing An Estimated Critical Position Calculation IV.

INSTRUCTIONS Note:

Steps A through G explain how to complete Data Sheet 1 (2), Form ECP-1 (Xenon-Free ECP Calculation) Parts A through G.

Data Sheet 2, Xenon-Free ECP Calculation, may be used in lieu of Data Sheet 1 for a Xenon-free startup if data from a recent Xenon-free startup is available as a reference point. Contact Reactor Engineering for applicability determination.

The ECP data taken for this procedure is dependent upon RCS Tavg between 546°F and 548°F at startup.

A. Critical Data

1. Fill in the information on Data Sheet 1 (2), Part A, Column I (Critical Data, Prior to Shutdown) from the following sources:

a.

Boron Concentration, Last boron sample during steady state operation from the NOMS log. (Boron Concentration from last Xenon-Free startup for Data Sheet 2.)

b.

Date and Time of the boron sample used for Step IV.A.1.a.

c.

Power-Reactor power at the time of the boron sample. This value can be obtained from cycle power history located in the Reactor Engineering Data Book. (Data Sheet 1)

d.

Burnup-Cycle burnup from the last Xenon-Free startup. This value can be obtained from cycle power history located in the Reactor Engineering Data Book or contact Reactor Engineering. (Data Sheet 2)

e. Xenon-Percent equilibrium xenon at the time of the boron sample. Estimate this value using BV-2 Curve Book, Figure CB-12, Integral Worth of Xenon vs.

Time After Startup. If Reactor Engineering is requested to determine the value of Xenon, N/A the appropriate space on Part A, Column I. (Data Sheet 1)

Samarium-Percent equilibrium samarium at the time of the boron sample (last Xenon-Free startup for Data Sheet 2). If the reactor operated at approximately 100% steady-state power for 2 8 days prior to shutdown, enter 1 00% for the samarium value. If Reactor Engineering is requested to determine the value of Samarium worth, N/A the appropriate space on Part A, Column I.

f.

g.

Rod Position-Control bank rod position at the time of the boron sample. (last critical position from Xenon-Free startup for Data Sheet 2)

2.

Fill in the information on Data Sheet 1(2), Part A, Column I I (Critical Data, Expected at Criticality) as follows:

Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Page 4 of 27 Operating Procedures Performing An Estimated Critical Position Calculation I

a.

Date and time criticality is expected to occur.

b.

Bumup-Cycle burnup when criticality will occur (most recent). This value can be obtained from cycle power history located in the Reactor Engineering Data Book or contact Reactor Engineering. (Data Sheet 2)

Xenon-Percent xenon at the expected time of criticality. Estimate this value using BV-2 Curve Book, Figure CB-23, Reactivity Insertion Due to Xenon vs.

Time Following Plant Trip After Steady State Operation At Various Power Levels. If Reactor Engineering is requested to determine the value of Xenon worth, N/A the appropriate space on Data Sheet 1, Part A, Column I I.

Samarium-Percent Samarium at the expected time of criticality. Estimate this value using BV-2 Curve Book, Figure CB-22, Samarium Buildup After Shutdown From Equilibrium Samarium. If Reactor Engineering is requested to determine the value of Samarium worth, N/A the appropriate space on Data Sheet 1 (2), Part A, Column II.

c.

d.

e.

Control Rod Position-Record the desired critical rod position. (usually Bank-D 63 100 steps)

8. Reactivitv Balance

1. Determine the power reactivity defect for Data Sheet 1, Part B, Column I (Prior to Shutdown) and record in the appropriate space on Data Sheet 1 as follows:

a.

Based on the power level and RCS Boron concentration at the PRIOR TO SHUTDOWN condition, use BV-2 Curve Book Figure CB-21, Power Defect vs.

Percent Power to determine the power defect.

OR

b. Have the Reactor Engineer provide the power defect using either the PC version of the Nuclear Design Report (PCNDR) or other NRC approved nuclear design codes.

2. For the control rod positions listed on Data Sheet 1 (Z), Part A (Critical Data) determine and record the control rod reactivity defect for Part 6, Columns I and I I as follows:

a.

BV-2 Curve Book Figure 24A, 24B, or 24C, Integral Rod Worth vs. Steps Withdrawn Banks D and C Moving with Overlap.

OR

b.

Have the Reactor Engineer provide the current value using either the PC version of the Nuclear Design Report (PCNDR) or other NRC approved nuclear design codes.

Beaver Valley Power Station Unit 2 20M-50.4.F Revision 4 Page 5 of 27 Station Startup Operating Procedures Performing An Estimated Critical Position Calculation A

B

3.

C Determine Xenon worth for Data Sheet 1, Part B, Columns I and II as follows:

Percent Equil Xenon Part A Critical Data Prior to Shutdown Expected at Criticality Column I 100 Column II 0

Equilibrium Xenon BOL, MOL, or EOL 1

Xenon Worth Col A x Col B/lOO%

CB-12 or CB-23 I

I 2606 pcm 2606 pcm 2606 pcm 0

pcm OR A

B

b.

Have the Reactor Engineer provide Xenon values in pcm using a computer program that approximates Xenon worth.

4.

Determine Samarium worth for Data Sheet 1(2), Part B, Columns I and II as follows:

C

a.

If BV-2 Curve Book, Figure CB-22, was used in Step IV.A.2.d, perform the following calculations and record the value obtained in Column C below on Data Sheet 1(2), Part B, Columns I and II:

Prior to Shutdown Column I Expected at Criticality Column II I

I Percent Equil Equilibrium Samarium Col A x Col B/IOO%

Samarium BOL, MOL, or EOL Samarium Worth Part A Critical Data CB-22 100 628 pcm 628 pcm 134 628 pcm 842 pcm OR

b. Have the Reactor Engineer provide Samarium values in pcm using a computer program that approximates Samarium worth.

5. Calculate the reactivity change as follows:

a.

On Data Sheet 1(2), Part B, Reactivity Balance, subtract Column I from Column II for each line.

b.

Enter the results in Column Ill, Difference

c.

Sum all the values in Column Ill and enter on Line 5.

Beaver Valley Power Station Station Startup Operating Procedures Performing An Estimated Critical Position Calculation Unit 2 20M-50.4.F Revision 4 Page 6 of 27

d.

Record this value on Data Sheet 1 (2), Part C, Column I, Line 1 C. Critical Boron Concentration for Startup

1. Data Sheet 1 Calculations

a.

b.

C.

d.

e.

f.

I Using BV-2 Curve Book, Figure CB-20, HZP Differential Boron Worth vs.

Boron Concentration, AND the Boron Concentration from Part A, Column I, enter the Differential Boron Worth on Data Sheet 1, Part C, Column 11, Line 1 Divide the Reactivity Change (Column I, Line 1) by the Differential Boron Worth (Column I I, Line 1) and enter the value on Data Sheet 1, Part C, Column Illl Line 1. Be cautious of signs.

Enter the Boron Concentration from Part A, Column I on Data Sheet 1, Part C, Column IV, Line 1.

Add the Boron Change (Column I l l, Line 1) to the Boron Concentration At Shutdown (Column IV, Line 1) and enter this value on Data Sheet 1, Part C.

Column V, Line 1.

Using BV-2 Curve Book, Figure CB-20, HZP Differential Boron Worth vs.

Boron Concentration, AND the Boron Concentration from Data Sheet 1, Part C, Column V, Line 1, enter the Differential Boron Worth on Data Sheet 1, Part C, Column I I, Line 2.

Divide the Reactivity Change (Column I, Line 1) by the Differential Boron Worth (Column II, Line 2) and enter the value on Data Sheet 1, Part C, Column Ill, Line 2. Be cautious of signs.

Enter the Boron Concentration from Data Sheet 1, Part A, Column I on Data Sheet 1, Part C, Column IV, Line 2.

Add the Boron Change (Column Ill, Line 2) to the Boron Concentration At Shutdown (Column IV, Line 2) and enter this value on Data Sheet 1, Part C.

Column VI Line 2.

2.

Data Sheet 2 Calculations

a.

Using BV-2 Curve Book, Figure CB-20, HZP Differential Boron Worth vs.

Boron Concentration, AND the Boron Concentration from Data Sheet 2, Part A, Column I, enter the Differential Boron Worth on Data Sheet 2, Part C, Column II.

b.

Divide the Reactivity Change (Column I) by the Differential Boron Worth (Column II) and enter the value on Data Sheet 2, Part C, Column Ill. Be cautious of signs.

c.

Enter the Boron Concentration from Data Sheet 2, Part A, Column I on Data Sheet 2, Part C, Column IV.

Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Operating P roced u res Page 7 of 27 Performing An Estimated Critical Position Calculation

d.

Add the Boron Change (Column Ill) to the Boron Concentration At Last Xenon-Free Startup (Column IV) and enter this value on Data Sheet 2, Part C.

Column V.

e.

Using BV-2 Curve Book, Figure CB-13, Critical Boron Concentration vs.

Bumup, enter the Critical Boron Concentration for the cycle burnup at the last Xenon-Free startup on Data Sheet 2, Part C, Column VI.

f.

Using BV-2 Curve Book, Figure CB-13, Critical Boron Concentration vs.

Burnup, enter the Critical Boron Concentration for the current cycle burnup on Data Sheet 2, Part C, Column VII.

g.

Subtract the value in Column VI1 from the value in Column VI and enter the result on Data Sheet 2, Part C, Column VIII.

h. Subtract the value in Column Vlll from the value in Column V and enter the result on Data Sheet 2, Part C, Column IX. This will be the final boron concentration required for startup.

3. Verify that the expected critical boron concentration on Data Sheet 1, Part C, Column V, Line 2 (Data Sheet 2, Part C, Column IX) is within the limits of BV-2 Curve Book, Figure CB-26, Operating Limits To Ensure a Negative MTC.

D.

Note:

Estimated Rod Position Correction (Based on Boron SamDle)

The following steps correct the Estimated Critical Rod position recorded on Data Sheet l(2) Part A, Column II for any differences between the measured boron sample and the calculated boron concentration for startup on Data Sheet 1, Part C, Column V, Line 2 (Data Sheet 2, Part C, Column IX).

1. Enter the latest boron sample results from Chemistry on Data Sheet 1 (2), Part D, Column I.

2.

Enter the calculated boron concentration for startup from Data Sheet 1, Part C, Column V, Line 2 (Data Sheet 2, Part C, Column IX) on Part D, Column 11.

3. Subtract Column II from Column I and enter on Part D, Column I l l

4. Using BV-2 Curve Book, Figure CB-20, HZP Differential Boron Worth vs. Boron Concentration, AND the Boron Concentration from Part D, Column I enter the Differential Boron Worth on Part D, Column IV.

5. Multiply Columns Ill and IV and record the result on Part D, Column V. Be cautious of signs.

6.

Record the Control Rod Worth expected at criticality from Part B, Column 2, Line 2, on Part D, Column VI.

7. Add Columns V and VI to obtain the corrected control rod worth at criticality and record this value as a negative number on Part D, Column VII.

Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Page 8 of 27 0 pe rat i ng P rocedu res Performing An Estimated Critical Position Calculation

8.

Determine the corrected Estimated Rod Position using the reactivity worth in Part D, Column VI1 and record on Part D, Column Vlll by using one of the following:

a.

BV-2 Curve Book, Figure 24A, 24B, or 24C, Integral Rod Worth vs. Steps Withdrawn Banks D and C Moving with Overlap.

OR

b.

Have the Reactor Engineer provide the current value using either the PC version of the Nuclear Design Report (PCNDR) or other NRC approved nuclear design codes.

E. Allowable Critical Rod Position Band

1. In Data Sheet 1 (2), Part E, Allowable Critical Rod Position Band, fill in each column as explained in the table and fill in the blanks in the lines below the table

2.

If during withdrawal of Banks C or D, it appears that the reactor will go critical at a rod height of less than 500 pcm (item E.V) OR Bank D is at maximum Rod height for criticality, notify the SWUS to ensure appropriate action taken in accordance with 20M-50.4. D, Reactor Startup From Mode 3 To Mode 2.

F. Shutdown Marqin Verification

1. Perform a shutdown margin calculation in accordance with 20ST-49.2, Shutdown Margin Calculation (Plant Shutdown).

2.

Enter the corresponding results from 20ST-49.2 in the first column of Data Sheet 1 (2), Part F, Shutdown Margin Verification.

3. Verify the shutdown margin once every hour while in Mode 2 until the reactor is critical. Additional columns are provided for this reverification.

G. List Actual Critical Conditions

1. Enter the date and time the reactor is critical on Log S1-4, 5 or 6 NCO Report.

2. Record the actual critical conditions in Data Sheet 1 (2), Part G, List Actual Critical Conditions, and the critical date and time.

H Perform 1/M Plot(s)

Note:

Taking an average of 10 baseline source range channel background reading(s) is statistically proven to be the most accurate method of determining source range channel baseline counts.

1. Using the source range scaler-timer, determine the average of 10 baseline source range counts from each source range channel and record results on Data Sheet 3, Part A.

a.

Select the N31 -N32-OFF switch to either N31 or N32 position

i Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Page 9 of 27 Operating Procedures Performing An Estimated Critical Position Calculation

b.

Select DISPLAY-PRESET switch to the PRESET-SEUDISPLAY-COUNT position.

Dial thumbwheel to 60.0. Thumbwheel has one decimal place.

c.

d. Set sampling mode switch to either AUTO or MANUAL.

e.

If sampling mode switch set to MANUAL, perform the following to obtain count rate (otherwise omit this substep) 1 )

Press RESET button.

2)

Press START button.

3)

After the readout displays a value, press the STOP button.

4)

Press RESET button.

5)

Repeat Steps H.l.e.l) through H.l.e.4) for the other nine readings

6)

Place sampling mode switch in AUTO.

f.

For each channel, sum all ten readings and divide this number by 600 to determine the total baseline average in CPS.

2.

Record final source range baseline average for each channel on Data Sheet 3, Parts B and C.

3. During control rod banks A, B and C withdrawals, it is preferred to determine inverse count rate ratios (ICRR) (for 1/M plot data points) by completing Data Sheet 3, Part B, 1/M Plotting For Control Banks A, B and C Movement, for each source range channel as follows:

Allow counts to stabilize prior to taking reading. Time for stabilization will increase as you approach criticality. Stable counts may be indicated by a straight line trace on Note:

NR-45.

a.

Set the audio channel multiplier to 10, 100, 1 K or 1 OK for a steady, distinguishable tone.

b.

Ensure sampling mode switch is in AUTO position.

c.

Select the N31 -N32-OFF switch to either N31 or N32 position

d. Select DISPLAY-PRESET switch to the PRESET-SEC/DISPLAY-COUNT position.

e.

Dial thumbwheel to a value of 10.0. Thumbwheel has one decimal place.

f.

Press RESET button.

g.

Record the readout under the CPS column for the appropriate source range channel.

Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Operating Procedures Page 10 of 27 Performing An Estimated Critical Position Calculation

h.

Divide the average baseline source range counts value (Co) of the appropriate channel as recorded on Data Sheet 3, Part A by the value displayed (in CPS) on the scaler-timer.

i.

Enter the resultant ICRR value under the ICRR column for the appropriate source range channel.

4.

5.

Repeat Step H.3 for the other source range channel Plot the ICRR data point on separate copy of Figure 1 for each source range channel during Control Rod Banks movements.

Continue control bank rod withdrawal to the next step position listed on Data Sheet 3.

6.

7.

Continue repeating Steps H.3 through H.6 for each control rod bank pull.

CAUTION: P-6 SETPOINT FOR SOURCE RANGE INSTRUMENTATION IS USUALLY REACHED 20 TO 30 STEPS ON CONTROL BANK D BEFORE REACTOR CRITICALITY IS REACHED.

Note:

Data Sheet 3, Part C provides a reference guide of the Control Banks C and D step sequence and overlap. Because criticality can be approached anytime during Bank D movement, it is recommended to plot 1/M points early during Bank D movement and if desired, at any sequence of steps at the discretion of the SRO.

8. After Control Bank C has been withdrawn past 11 9 steps, continue with Data Sheet 3, Part C, 1/M Plotting For Control Bank D Movement.

1/M Plot accuracy improves as the reactor gets closer to criticality. Renormalization is not required, however graphical accuracy may be further improved by renormalizing.

Note:

9. If desired to renormalize the 1/M plot, perform the following: (Otherwise step is N/A)

a.

Stop Control Rod withdrawal

b.

Determine a new source range baseline count rate average for each source range channel by performing Steps H.l through H.2 above and completing a new copy of Data Sheet 3, Part A, Baseline Count Rate Determination.

Record final new source range baseline average for each channel on Data Sheet 3, Part C.

c.

d.

Obtain a new copy of Figure 1 for each channel.

I Beaver Valley Power Station Unit 2 20M-50.4.F Station Startup Revision 4 Operating Procedures Page 11 of 27 Performing An Estimated Critical Position Calculation

e. Plot the new source range baseline average value on Figure 1 for each channel.

f.

Resume Control Rod withdrawals.

g.

Obtain ICRR data at any sequence of Control Bank C or 0 steps in accordance with Steps H.3 through H.7 and record the data on Data Sheet 3, Part C to determine 1IM plot points to approach criticality.

h.

Plot the ICRR points on new separate copies of Figure 1 for each source range channel during Control Bank D movements.

I.

Documentation

1. File all of the following completed documents:

a.

b.

Form ECP-1 (Data Sheet 1) OR Xenon-Free ECP Calculation (Data Sheet 2) 1/M Plots (Data Sheet 3 and Figure 1) (both channels)

Performed By R.O. #2 Verified By Reviewed By Date SM/US I

Route the completed copy of this procedure to Document Control via the Operation Clerks daily transmittals.

Beaver Valley Power Station Unit 2 20M-50.4. F Station Startup Revision 4 Operating Procedures Page 12 of 27 Performing An Estimated Critical Position Calculation Xenon 100 %

(Use Fig CB-12 or NIA)

A. Critical Data (1)

(11)

(111)

DATA SHEET I FORM ECP-1 2040 pcm

1. Power (Fig CB-21) (OR Consult W ENGR)

I PRIOR TO SHUTDOWN

~

0 (zero) pcrn

(-) - 2040 pcm 1 2 Control Rods (Circle g d

)

(Fig C -24A 248, 24C ORCons ENGR)

Samarium 100 (Use Fig CB-22 or N/A) 0 pcm 600 pcm (k)

+ 600 pcm 1 Control Rod Position A 226 C 226

, B g 7 6 D 226

3. Xenon (Fig. CB-23)

~ -

I

~

(11)

EXPECTED AT CRITICALITY Date TqdaY/

Time 0000 0

pcm (2) -2606 pcm Xenon 0

Yo (Use Fig CB-23 or NIA)

Samarium 134 0/0 (Use Fig CB-22 or N/A) 1 4 Samarium (Fig. CB-22)

Control Rod Position A 226 C 226 B 226 D 130 I

628 pcm 842 pcm

(+)

+ 214 pcm B. Reactivity Balance - (Record absolute values in Columns I and I I )

I 2606 Dcm 1 5. Reactivity Change (Sum of 1-4) =

DATA SHEET 1

Beaver Valley Power Station Unit 2 20M-50 4.F Station Startup Revision 4 0 perati n g Procedures Page 13 of 27 Performing An Estimated Critical Position Calculation Reactivity Change (B.5)

DATA SHEET 1 (continued)

Boron Change Differential Boron Worth (Fig. CB-20)

( I ) + (11)

FORM ECP-1

2.

C. Critical Boron Concentration

- 7.4 pcm

(+) -3832pcm

(-)

ppm (5) +518 ppm

- 7.05

(-)

ppm

(+_)+544 ppm

( 1 )

(11)

(111)

Boron Sample Boron Conc. For Boron Deviation Startup C.l.h (1) - (11) ppm ppm (k) ppm (IV)

Differential Boron Worth (Flg CB-20) i

-E!?/

PPm I Boron Conc I

for Startup Shutdown j

(111)

+ (IV)

Boron Conc. at (V)

(VI)

(VI I)

Rod Worth Rod Worth Corrected Rod Correction Expected At Worth Expected At

( I l l ) x (IV)

Criticality (B.2)

Criticality (V) + (VI)

D. Estimated Rod Position Correction (VIII)

Corr Critical Rod Pos (Circle Figure used)

(Flg CB-24A 24B. 24C OR Consul: RX ENGRi

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

BVPS Unit 2 Task No.: 1300-009-03-023 Task

Title:

Review a Gaseous Waste Discharqe JPM No.:

2005 NRC SRO Authorization Admin No. 4 K/A

Reference:

2.3.8 (3.2)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testina:

Simulated Performance:

Actual Perform a nce :

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

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

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The plant is in Mode 1 at 100% power. [2GWS-TK21A], Gaseous Waste Storage Tank is in the process of being released via an RWDA-G. The discharge started two hours ago and is expected to continue for another 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months .

Identify the error contained in a partially completed RWDA-G and correctly calculate a 2-hour bleed flow rate in accordance with 1/20M-19.4A.B.

Calculator 1/20M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent, Rev. 12 1/20M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent, Rev. 12 (partially completed) 1/2-HPP-3.006.F01, Gaseous Radioactive Waste Discharge Authorization (Partially Completed) 2GWS-TK21A Parameters Table As the Unit Supervisor, you are to perform a review of the attached RWDA-G to verify that the information entered is correct, and calculate a 2-hour bleed flow rate in accordance with 1/20M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent, Step IV.A.20. Report your results when finished.

No 10 minutes BVPS-2 NRC ADMIN NO. 4 NUREG 1021, Revision 9

Page 2 of 6 PERFORMANCE INFORMATION Form ES-C-I 2005 NRC ADMIN NO 4 Appendix C (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Candidate reviews the procedure for completeness Standard:

Candidate reviews the procedure verifying that the procedure is signed up to Step IV.A.20.

NOTE:

This step may be performed at any time during the JPM.

Comment:

V Performance Step: 2 Candidate reviews the RWDA-G.

Standard:

Standard :

(Step IV.A.8 Note)

Candidate reviews the partially completed RWDA-G for required data entry and completeness.

Candidate determines the Discharge Start date exceeds the 72-hour limit CUE:

Inform the Candidate that Chemistry will obtain a confirmatory sample and to continue with the JPM.

Comment:

Performance Step: 3 Candidate obtains required data for 2-hour bleed flow rate Stand a rd :

Comment:

Candidate reviews the Data Sheet to obtain the current gaseous waste storage tank pressure and time.

BVPS-2 NRC ADMIN NO. 4 NUREG 1021, Revision 9

Appendix C Page 3 of 6 Form ES-C-1 2005 NRC ADMIN NO. 4 PERFORMANCE INFORMATION Terminating Cue:

When the Candidate verifies the bleed flow rate is within limits, the evaluation for this JPM is complete.

4 Performance Step: 4 Calculate 2-hour bleed flow rate.

(Step IV.A.20.a)

Standard:

Candidate determines the discharge flow rate = 1.53 scfm as follows:

(132cu. $.)(55.0 -34.5)( I ) = 1.53 Bleed Flo~i Rate (SCFM) =

(14.7 psi)(l30-0)

Comment:

4 Performance Step: 5 Verify bleed flow rate is within limits.

Standard:

Candidate verifies the calculated value is less than the RWDA-G limit of 2 scfm.

NOTE:

The JPM may be stopped at this point.

Comment:

STOP TIME:

BVPS-2 NRC ADMIN NO. 4 NUREG 1021, Revision 9

Appendix C Page 4 of 6 Form ES-C-1 2005 NRC ADMIN NO. 4 VERI Fl CAT1 ON OF COMPLETION JPM No.:

Examinees Name:

Examiners Name:

Date Performed:

2005 NRC SRO No. 4 Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question.

Response

Result: Satisfactory/Unsatisfactory Examiners Signature:

BVPS-2 NRC ADMIN NO.

4 Date:

NUREG 1021, Revision 9

Appendix C Page 5 of 6 Form ES-C-1 2005 NRC ADMIN NO. 4 JPM CUE SHEET INITIAL CONDITIONS:

The plant is in Mode 1 at 100% power. [2GWS-TK21A], Gaseous Waste Storage Tank is in the process of being released via an RWDA-G. The discharge started two hours ago and is expected to continue for another 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months .

INITIATING CUE:

As the Unit Supervisor, you are to perform a review of the attached RWDA-G to verify that the information entered is correct, and calculate a 2-hour bleed flow rate in accordance with 1/20M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atrnos Vent, Step IV.A.20. Report your results when finished.

BVPS-2 NRC ADMIN NO. 4 NUREG 1021. Revision 9

1/2-HPP-3.06.006.F01 RTL A9.520B BEAVER VALLEY POWER STATION-2 RWDA-G-00811 GASEOUS Radioactive Waste Discharge Authorization Monitor Alarms Adjusted HI-HI HI HI H-p.

HI-HI H-P-RM-&?b8B 2 -36E+05 1.18E+05 T H T T RM-GW-109(5) 3.60E+05 1,20E+05 rmfT Prere {isites of ODCM y2-OX-3-03 Table 13 met INIT HsP*

Discharge Stop Prepared RT Signature Date Sample ID Sample Date/Time :

J. Hall 2-25-05 TEST 24-FEB-05 14:00 I

I Reviewed By Chemistry Notified RP Supervision Sig Date Chemist Signature Date Approved By Approved By U1 Shift Mngr S i g Date U2 Shift Mngr Sig Date K. York 2-25-05

9.

Furdak 2-25-05 A. Hariner 2-25-05 B. Sommer 2-25-05 ini t I

I 3,60E+05 1,20E+05 Total Discharge

---l-'-T1-3.60E+05 1 - 20E+05 minutes

Appendix C Page 6 of 6 Form ES-C-1 2005 NRC ADMIN NO 4 JPM CUE SHEET 60 120 2GWS-TK21A Parameters Table 44.8 psig 34.5 psig TIME ZGWS-TK21A PRESSURE i

1 (2GWS-PR125) i 0

I 55.0 psig BVPS-2 NRC ADMIN NO. 4 NUREG 1021, Revision 9

Beaver Valley Power Station Unit 1/2 1120M-19.4A. B Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Prepared by D. A. Kirk Date 10/26/02 Reviewed by Date R. C. Plummer 10/29/02 PORC Meeting No.

Date PORC Not Required A9.330B Pages Issued 1 through 18 Validated by N/A Date PAF-02-04210

Beaver Valley Power Station Unit 112 1 /20M-19.4A. B GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Page 2 of 18

1.

PURPOSE To provide instructions for discharging the contents of Unit 2 Gaseous Waste Storage Tank to the Unit 1 Atmospheric Vent. One copy of this procedure will be used by Operators at both Unit 1 and Unit 2 to ensure continuous administrative control throughout the evolution. This procedure is written to be started by an operator at Unit 2.

II.

PRECAUTIONS Do NOT operate a unit cross connect isolation valve without first coordinating the activity with the Unit 1/2 Control Room.

Each step of this procedure must be performed in sequence with all preceding steps signed off as a prerequisite for the next step unless the SM/US at both units give permission to deviate.

Do NOT have more than one Gaseous Waste Storage Tank(s) permit being discharged at a time.

Do NOT discharge a gaseous waste storage tank until chemistry notification is complete.

The maximum calculated bleed flow rate should NOT exceed 2 CFM.

Ensure that the activity discharge rate to the atmospheric vent does NOT exceed the limit specified in the discharge permit.

Do NOT discharge a Unit 2 Gaseous Waste Storage Tank that is being filled.

Ill.

INITIAL CONDITIONS A.

B.

C.

D.

E.

F.

G.

A. The SMlUS at Unit 2 has given permission to perform this procedure.

Unit2 SM /Todav SM / US B. The Control Room Operator at Unit 2 has notified the Control Room Operator at Unit 1 of the intent to discharge the contents of a Unit 2 Gaseous Waste Storage Tank.

Unit2 RO Initial C. Personnel are available to periodically monitor storage tank pressure at the Gaseous Waste Storage Tank Panel [PNL-2GWSTP].

Unit 2 RO Initial

Beaver Valley Power Station Unit 112 1120M-19.4A. B GASEOUS WASTE DISPOSAL SYSTEM Opera ti ng Procedures Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Page 3 of 18 D. The SM/US at Unit 1 has given permission to perform this procedure.

I The SM's OR US's at Unit 1 AND Unit 2 signatures denotes approval for discharge, that only one batch RWDA-G is being discharged at one time, and the appropriate alarms have been adjusted.

J Unit 1 SM Initial E. The meteorological instrumentation required by Unit 2 Licensing Requirement Manual 3.3 Meteorological Monitoring Instrumentation LR 3.3 is operable.

Unit 1 SM Initial F. The applicable radioactive gaseous effluent monitoring instrumentation channels specified by 1/2-ODC-3.03, ODCM: "Controls For RETS and REMP Programs",

Attachment F, 3.3.3.10 is operable OR the applicable action statement has been met.

Unit I SM Initial G. The maximum process vent system flowrate should NOT exceed 1450 CFM on

[FR-1 GW-1081.

Unit 1 RO Initial Note:

The Radiation Technician must enter the Control Room to adjust the alarm setpoints on the analog instrument as required by the RWDA-G and initial it.

H. Radiation Protection has been contacted to adjust the HI and HI-HI alarm setpoints.

Unit 1 RO Initial I.

A gaseous waste discharge permit (Radioactive Waste Discharge Authorization Gas-RWDA) has been obtained AND the SM's OR US's at Unit 1 and Unit 2 have signed and dated the RWDA-G at the PRE (discharge authorization block).

Unit?

SM ITodav SM I US Unit2 SM /Today SM I US

Beaver Valley Power Station GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 112 1 I20M-19.4A. B Revision 12 Page 4 of 18 I Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent I

I Note:

Notifying Chemistry will enable the chemist to obtain the appropriate tritium sample. The chemist will sign and date the RWDA-G at PRE (discharge authorization block) for verification of this notification.

J.

The US OR the Operator has notified the chemist of the intent to discharge the gaseous waste storage tank.

Unit 2 RO initial

Beaver Valley Power Station Unit 112 1/20M-19.4A.B GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Page 5 of 18 IV.

INSTRUCTIONS A.

Procedure CAUTION:

DO NOT HAVE MORE THAN ONE GASEOUS WASTE STORAGE TANK(S)

PERMIT BEING DISCHARGED AT A TIME.

I. Check that the high and high-high setpoints on [RIS-GW-l08B] agree with the setpoint in the Radiation Monitor Setpoint Log.

Unit 1 RO Initial

2.

Perform a channel check AND source check of [RM-1 GW-108BI.

Unit 1 RO Initial

a.

Perform a channel check of [FR-lGW-108].

3. Hand carry this procedure to the Control Room Operator at Unit 2.

Unit 1 RO Initial Unit 1 RO Initial

4. Mark the date, time, RWDA-G authorization number, and Operator's initials on

[2GWS-PR125] at the beginning of the discharge.

Unit 2 RO Initial

a.

If [2GWS-PR125] is unavailable, monitor pressure using Control Room computer trend. (Otherwise N/A)

Unit 1 N/A Initial

5. Hand carry this procedure to the Control Room Operator at Unit 1 Unit 2 RO Initial

Beaver Valley Power Station Unit 112 1/20M-19.4A.B GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Page 6 of 18

6.

Check closed [FCV-1 GW-105] Decay Tank Bleed Control Valve by checking

[AM-1 GW-1051 in MANUAL with output at 0%.

Unit 1 RO Initial

7. After receiving concurrence of transfer from the Operator at Unit 2, open

[1GW-276] Unit 2 Isolation to GW Decay Tanks Discharge header. (Unit 1 Decay Tank Valve Room)

Unit 1 RO Initial

8.

Hand carry this procedure to the Control Room operator at Unit 2.

Unit 1 RO Initial 1 Note:

An amroved RWDA-G is effective for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the samDle time.

9.

Record the date, time, gaseous waste storage tank pressure in PSIG, and Operator initials on the RWDA-G at the beginning of each discharge.

Unit 2 RO Initial

a.

If a discharge is not initiated within the allowable period, have a confirmatory sample analyzed to extend the effective period of the authorization.

(Otherwise N/A)

Unit 2 RO Initial IO. Open the outlet valve [2GWS-SOV125A2-G2] at [PNL-2GWSTP] for the Gaseous Unit 2 RO Waste Storage tank being discharged.

Initial

11. Open [2GWS-AOV105], Gaseous Waste Storage Tank Outlet Header Is01 Vlv, by placing its control switch to the OPEN position, Benchboard-Section A.

Unit 2 RO Initial

Beaver Valley Power Station Unit 112 1/20M-19.4A.B GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Page 7 of 18 Note:

In conducting his review, the SM OR US shall consider the correct source selection, radiation monitor setpoints, radiation monitor setpoint checks, dilution flow, RWDA-G in use, procedure in use, boundary valve alignment, Chemistry notification, Radiation Protection notification, intended discharge rate and proper documentation to the current step.4

12. Prior to INITIATION of all radioactive waste discharges, request that the SM OR US review the steps and alignments conducted to this point and authorize the INITIATION of di~charge.~

RO Initial

13. Hand carry this procedure to the Control Room Operator at Unit 1.

Unit2 RO Initial

14. Open the discharge header trip valve [n/-lGW-103] Benchboard-Section A.

Unit 1 RO Initial

15. Mark the date, time, RWDA-G authorization number, and Operator's initials on

[ l RR-2001, Radiation Monitor Level Recorder at the beginning of the discharge.

Unit 1 RO Initial Note:

Pressure in the Gaseous Waste Storage Tank being discharged must be monitored periodically during the discharge.

16. Slowly open [FCV-1 GW-1051 Decay Tank Bleed Control Valve, by placing

[AM-lGW-105] to MANUAL AND, if the maximum bleed flow rate specified in the discharge permit is:

a.

< 2 cfm, verify [FR-lGW-105], GW Decay Tank Flow to Injector, remains on-scale AND less than this limit.

b.

2 2 cfm, raise output to 100%

Unit 1 RO Initial

17. Notify the Unit 1 Chemist that the gaseous waste discharge is starting.

Unit 1 RO Initial

Beaver Valley Power Station GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 112 1/20M-19.4A.B Revision 12 Page 8 of 18 I Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent I

18. Hand carry this procedure to the Control Room Operator at Unit 2.

Unit 1 RO Initial

19. Verify [2GWS-PR125] Gaseous Waste Storage Tank pressure decrease for the tank being discharged.

Unit 2 RO Initial

a.

If [2GWS-PR125] is unavailable, monitor pressure using Control Room computer trend. (Otherwise N/A)

Unit 2 N/A Initial

20. Two hours after the discharge has been initiated, perform the following steps:

a.

Confirm the bleed flow rate using the following equation:

(132cu. ft.)(Pi - Pf)(No. of Tanks being discharged)

(14.7 psi)(Tf - Ti)

Bleed Flow Rate (SCFM) =

Unit 2 Initial Pi

=

Initial Gaseous Waste Storage Tank pressure in PSlG from

[2GWS-PR125] OR if [2GWS-PR125] is unavailable, pressure from Control Room computer trend.

Pf

=

Current Gaseous Waste Storage Tank pressure in PSlG from

[2GWS-PRI 251 OR if [2GWS-PRl25] is unavailable, pressure from Control Room computer trend.

Ti

=

Time the discharge started Tf

=

Current time (Tf-Ti) shall have units of minutes

~

Beaver Valley Power Station Unit 112 1120M-19.4A.B GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Page 9 of 18

~

b.

Contact the Shift Chemist AND Verify that proper tritium sampling has been completed.

Unit 2 Initial If a proper tritium sample has NOT been obtained, stop the discharge AND do NOT reinitiate until a Chemist is prepared to obtain the sample.

(Otherwise N/A)

Unit 2 Initial

c.

If the bleed flow rate exceeds 2 SCFM, THEN Stop the discharge by performing Steps IV.A.21 and IV.A.22 AND Notify Radiation Protection of the problem. (Otherwise N/A)

Unit 2 Initial

21. Hand carry this procedure to the Control Room Operator at Unit 1.

Unit 2 Initial If [2GWS-PR125] is unavailable, pressure may be monitored using Control I Note:

Room comwter trend.

I

22. To terminate the discharge when [2GWS-PR125] Gaseous Waste Storage Tank pressure has decreased sufficiently (must remain above 2 PSIG) OR to stop the discharge temporarily (such as but NOT limited to meteorological conditions becoming unfavorable), perform the following:

a.

Close [FCV-lGW-l05] Decay Tank Bleed Control Valve by placing

[AM-1 GW-1051 to MANUAL and set output at 0%.

Unit I Initial

b.

Close tTV-1 GW-1031 Decay Tank Header to cooling tower.

Unit 1 Initial

c.

Close [I GW-2761 Unit 2 Isolation to GW Decay Tanks discharge header.

Unit I Initial

Beaver Valley Power Station Unit 1/2 1/20M-19.4A.B GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Page 10 of 18

d.

Mark the date, time RWDA-G authorization number and Operators initials on

[l RR-2001, Radiation Monitor Level Recorder.

Unit I Initial

e.

Hand carry this procedure to the Control Room Operator at Unit 2.

Unit I Initial

f.

Close [2GWS-AOV105], Gaseous Waste Storage Tank Outlet Header lsol Vlv.

Unit 2 Initial

g.

Mark the date, time, RWDA-G authorization number and Operators initials on

[2GWS-PRI 251.

Unit 2 Initial

h.

Record the date, time, Gaseous Waste Storage Tank pressure in PSIG, and Operators initial on the RWDA-G.

Unit 2 Initial

23. If the discharge is to be restarted, perform Attachment 1, (Continuation of gaseous waste discharge). (N/A if no further discharge is required)

a.

Commence first continuation of gaseous discharge.

Unit 2 Initial

b.

Commence second continuation of gaseous discharge.

Unit 2 Initial

c.

Commence third continuation of gaseous discharge.

Unit 2 Initial

Beaver Valley Power Station Unit 112 1/20M-19.4A.B GASEOUS WASTE DISPOSAL SYSTEM Operating Procedures Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent Revision 12 Page 11 of 18 Note:

The SM OR US at Unit 1 AND the SM OR US at Unit 2 signatures denotes that only one batch RWDA-G was discharged at one time and that the appropriate alarms have been reset.

24. When the discharge is to be terminated, Close [2GWS-SOV125A2 I

(1 25B2)( 125C2)( 125D2)( 125E2)( 125F2)( 125G2), Gaseous Waste Storage Tank Outlet Isolation.

I Unit 2 Initial

25. Determine the Total Discharge Time in minutes and record on the RWDA-G.

Unit 2 Initial

26. Notify Radiation Protection to reset the HI and HI-HI alarm setpoints.

Unit 2 Initial

27. The SM OR US at Unit 1 AND the SM OR US at Unit 2 shall review the RWDA-G to confirm that the data entered by the Operator is complete and correct and sign and date the RWDA-G at POST Review.

I Unit 1 I

SM I US Unit 2 I

SM I US

6. Procedure Completion

1.

Notify the SM/US at Unit 1 AND Unit 2 of the completion of this procedure.

Performed By I

Verified BY I

Reviewed By I

S MIU S Forward the completed copy of procedure to Document Control via the Operations Clerkls daily transmittal.

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

BVPS Unit 2 Task No.:

1350-004-03-023 Task

Title:

Classify an Event and Determine JPM No.:

2005 NRC SRO WA

Reference:

2.4.40 (4.0) 1350-007-03-023 Protective Action Recommendations Admin No. 5 Examinee:

Facility Evaluator:

Method of testinq:

Si m u la ted Perform a nce :

Classroom X

Simulator READ TO THE EXAMINEE NRC Examiner:

Date:

Actual Performance:

X Plant I will explain the initial conditions, which step to simulate or discuss, and provide initiating -Jes.

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 was operating at 100% power for 160 days on-line when the following occurred:

=

EDG 2-1 was 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months into a maintenance outage to replace the motor driven fuel oil pump and not expected to return for another 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months .

A lightning strike in the switchyard resulted in a loss of offsite power and a reactor trip.

[ACB 2F101, 2-2 Emerg Gen Output Breaker tripped on overcurrent de-energizing the 4KV 2DF Bus.

30 minutes into the event, PSMS displayed the 5 hottest CETs at greater than 730°F and RVLIS Full Range at 30%.

No 4KV emergency power is expected for at least another 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Correctly classify an emergency event using EPP/I-1 b and determine Protective Action Recommendations in accordance with 1 /2-EPP-IP-4.1.

NONE EPP/I-1 b, Recognition And Classification of Emergency Conditions, Rev. 5 1/2-EPP-IP-4.11 Offsite Protective Actions, Rev. 18 EPP/I-1 b, Recognition And Classification of Emergency Conditions, Rev. 5 1/2-EPP-IP-4.1, Offsite Protective Actions, Rev. 18 As the Emergency Director, you are to evaluate the given plant conditions and determine the emergency classification in accordance with EPP/1-1 b, Recognition And Classification of Emergency Conditions. Report your results when finished.

YES 12 minutes 7

I C P m G-tn=nm~s~

BVPS-2 NRC ADMIN NO. 5 NUREG 1021, Revision 9

Appendix C Page 2 of 7 Form ES-C-1 2002 Audit A4 SRO PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

1 NOTE:

Provide the Candidate with the first set of Initial Conditions and a copy of the 1

EAL's.

I

.\\,

Performance Step: 1 Correctly classify the emergency event Stand a rd :

Candidate classifies the event based on Tab 3.1, Loss of AC (Power Ops) as a General Emergency using the following criteria:

AE and DF 4KV emergency buses NOT energized from Unit 1 sources for > 15 minutes, and Five hottest CETs > 719F with no RCPs running and RVLIS full range < 40%

NOTE:

CUE:

If the Candidate does NOT correctly classify the event, then stop the JPM at this point.

This JPM is conducted in two (2) parts. Once the Candidate determines the correct emergency classification, then administer the PAR section of the JPM. Each section is allotted 15 minutes to complete.

Inform the Candidate that the Initial Notification Form will NOT be completed at this time.

Comment:

NOTE:

Provide the Candidate with the second set of Initial Conditions and a copy of 1/2-EPP-IP-4.1, Offsite Protective Actions.

I BVPS-2 NRC ADMIN NO. 5 NUREG 1021, Revision 9

Page 3 of 7 PERFORMANCE INFORMATION Form ES-C-1 2002 Audit A4 SRO Appendix C Performance Step: 2 Locate Offsite Protective Action Recommendation Flowchart Standard:

Candidate refers to 1/2-EPP-IP-4.1, Attachment A, Offsite Protective Action Recommendation Flowchart.

Comment:

Performance Step: 3 Standard :

Determine offsite protective action Candidate navigates PAR flow chart as follows:

. General Emergency already declared (J)

. Met data provided in Initial Conditions (k)

. None of the following are TRUE (L):

3 35 wind speed LESS than 2 MPH (or unavailable)?

3 Is either 150 or 500 wind directions unavailable?

3 The difference between the 150 & 500 wind directions is 2 165 and 5 795 degrees? (opposite wind directions) or unavailable?

3 Release (other than a non-routine minor release below Federally approved operating limits or wholly comprised of tritium) has started or is imminent. (within one hour) 3 Release transport will span sunrise or sunset hours. - E,

9 Dose projection results available (FSAR, monitor data, etc.)?

-YES (+).

. Projected dose at EAB >1 REM TEDE or > 5 REM CDE -

. TEDE is less than 10 REM at EAB - NO (J) 9 Projected dose at 5 miles: > 1 REM TEDE or > 5 REM CDE -

Projected dose at 2 miles: > 1 REM TED or > 5 REM CDE -

YES (+)

NO (1)

YES (4)

Comment:

BVPS-2 NRC ADMIN NO. 5 NUREG 1021, Revision 9

Appendix C Page 4 of 7 Form ES-C-1 2002 Audit A4 SRO PERFORMANCE INFORMATION 4

Performance Step: 4 Determine Offsite Protective Action Recommendations Comment:

Stand a rd :

Standard:

Candidate determines that the 150 elevation downwind sectors are DEFGH.

CUE:

Inform the Candidate that the Initial Notification Form will NOT be completed at this time.

Comment:

Terminating Cue:

STOP TIME:

When the candidate completes the Protective Action Recommendation, the evaluation for this JPM is complete.

BVPS-2 NRC ADMIN NO. 5 NUREG 1021, Revision 9

Appendix C Page 5 of 7 Form ES-C-1 2002 Audit A4 SRO VERIFICATION OF COMPLETION Job Performance Measure No.:

2005 NRC SRO No. 5 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

BVPS-2 NRC ADMIN NO. 5 NUREG 1021, Revision 9

Appendix C Page 6 of 7 Form ES-C-1 JPM CUE SHEET 2002 Audit A4 SRO INITIAL CONDITIONS:

(Emergency Classification)

The Unit was operating at 100% power for 160 days on-line when the following occurred:

EDG 2-1 was 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months into a maintenance outage to replace the motor driven fuel oil pump and not expected to return for another 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months .

A lightning strike in the switchyard resulted in a loss of offsite power and a reactor trip.

[ACB ZFlO], 2-2 Emerg Gen Output Breaker tripped on overcurrent de-energizing the 4KV 2DF Bus.

30 minutes into the event, PSMS displayed the 5 hottest CETs at greater than 730°F and RVLIS Full Range at 30%.

No 4KV emergency power is expected for at least another 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

INITIATING CUE:

BVPS-2 NRC ADMIN NO. 5 As the Emergency Director, you are to evaluate the given plant conditions and determine the emergency classification in accordance with EPP/1-1 b, Recognition And Classification of Emergency Conditions. Report your results when finished.

NUREG 1021, Revision 9

Appendix C Page 7 of 7 Form ES-C-1 2002 Audit A4 SRO JPM CUE SHEET INITIAL CONDITIONS:

(Protective Action Recommendations)

A General Emergency has been declared at Unit 2 following a small break LOCA and the loss of all 4KV emergency power.

The following plant conditions exist:

. 35 wind direction is from 270 at 4 MPH.

150 wind direction is from 270 at 11 MPH.

. 500 wind direction is from 285 at 15 MPH.

. No radioactive release has occurred or is anticipated.

. Health Physics has provided the following dose projections:

At the EAB:

11 REM TEDE; 8 REM CDE At 5 miles:

0.9 REM TEDE, 2.5 REM CDE At 2 miles:

1.5 REM TEDE; 4 REM CDE INITIATING CUE:

You are the Emergency Director and the TSC/EOF have NOT yet been activated. You are to evaluate the above conditions and determine which, if any, offsite Protective Action Recommendations are necessary.

BVPS-2 NRC ADMIN NO. 5 NUREG 1021, Revision 9

FISSION PRODUCT BARRIER MATRIX (Modes 1-4) 1.1 1.2 1.3 Fuel Clad (RCS activity, corecooling, heat sink)

RCS (Integrity, SGTR, heat sink)

Containment (CNh4T Red Path, CNMT bypass) 1 SYSTEM DEGRADATION 2.1 Loss of Instrumentation 2.5 RCS Unident Leakage 2.9 Turbine Failure 2.2 Loss of FunctiodComms 2.6 RCS Ident. Leakage 2.10 Stm/Feed Line Break 2.3 Failure of Rx Prot.-ATWS 2.7 Technical Specification S/D 2.4 Fuel Clad Degradation 2.8 Safety Limit Exceeded 2

HAZARDS and ED JUDGEMENT 4.1 Fire 4.3 Flammable Gas 4.5 Control Room Evacuation 4.2 Explosion 4.4 Toxic Gas 4.6 Security Table 4-1 Table 4-2 4.7 ED Judgement Figure 4-A Figure 4-BEigure 4-C Table 4-3/Table 4 4

~~

DESTRUCTIVE PHENOMENA 5.1 Earthquake 5.2 TornadoMigh Winds Table 5-1 5.3 Aircraft CrashProjectile 5.4 River Level High 5.5 River Level Low Figure 5-A 5.6 Watercraft Crash (RWISWS Loss)

SHUTDOWN SYSTEM DEGRADATION 6.1 Loss of Shutdown Systems 6.3 Loss of AC (Shutdown) (Modes 5 & 6) 6.2 RCS Inventory-Shutdown 6.4 Loss of DC (Shutdown) (Modes 5 & 6) 6.5 Fuel Handling (All Modes) 6.6 Inadvertent Criticality RADIOLOGICAL 7.1 Gaseous Effluent 7.2 Liquid Effluent Table 7-1 7.3 Radiation Levels 7.4 Fuel Handling (All Modes)

Table 7-2 7

Mot -

1 2

3 4

1 2

3 4

1 2

3 4

1 2

3 4

Criterion / Indicator Prolonged loss of offsite and onsite AC power

[I and 21

1.

AE & DF 4KV emergency buses NOT energized from Unit 2 sources for 215 minutes

2.

[aor bor c]

a.

Ops personnel report CSF status tree RED PATH or ORANGE PATH terminus exists for core cooling Restoration of either AE a DF 4KV emergency bus is NOT likely from any source within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of loss

c.

Three max core exit thermocouples

>I200 F three max core exit thermocouples 2729 F with no RCPs runnine and RVLIS full ranee <40%

b.

Loss of offsite and onsite AC power for >15 minutes

1.

AE & DF 4KV emergency buses NOT energized from Unit 2 sources for >I5 minutes AC power to emergency buses reduced to a single source of power such that any additional failure will result in the d e energization of both buses

[I and 21

1.

Either AE DF 4KV emergency bus is de-energized for >15 minutes

2.

The energized AE or DF 4KV emergency bus has only one source of power

[a or b]

a.

Emergency diesel generator

b.

2A or 2D 4KV normal bus Loss of offsite power supply for >15 minutes

[I and 21 Offsite power supply to AE and DF 4KV buses unavailable for 21 5 minutes.

Each diesel generator is supplying power to its respective emergency bus I.

2.

m Mode 5

6 De-fuel 5

6 De-fuel Criterion / Indicator Refer to Tab 6

Shutdown System Degradation Refer IO Tab 6

Shutdown System Degradation

UNPLANNED loss of offsite and onsite AC power for >15 minutes

1.

AE DF 4KV emergency buses NOT energized from Unit 2 sources for 215 minutes Also Reyer to Tab 6 Shutdown System Degradation UNPLANNED loss of offsite power supply for >15 minutes [I and 21 I.

Offsite power supply to AE and DF 4KV buses unavailable for 21 5 minutes.

Either diesel generator is supplying power to its respective emergency bus

2.

1 2

3 4

1 2

3 4

L EPPA-1 b Jriteri 1 Fissi I Ir -

Pra on idicator

(

Refer to Tab on duct Barrier Matrix and Tab 23 Loss of Function, and Tab 6.1 Loss of Shutdown Systems Loss -

of -

all -

vi ita1 DC Dwer -

. for -

minutes

1.

Voltage 410.4 VDC on DC buses 2-1 and 2-2 2-3 & 2-4 for >I 5 minutes Also Refer to Tab I Fission Product Barrier Matrix, Tab 2.2 Loss of Function, and Tab 2.1 Loss of Instrumentation and Tab 6.1 Loss of Shutdown Systems Refer to Tab I Fission Product Barrier Matrix, Tab 2.2 Loss of Function, and Tab 2.1 Loss of Instrumentation and Tab 6.1 Loss of Shutdown Systems SD loss for >IS minutes

[I or 21 of -

one trai -

in -

of DC power

1. Voltage < I 10.4 VDC on DC Buses 2-1 &

2-3 for >I 5 minutes

2. Voltage I 5 minutes Refer to Tab 6.4 Loss of DC (Shutdown)/or modes 5, 6. and dejiteled Revision 5

EPPDmplementing Procedures OFFSITE PROTECTIVE ACTIONS Continue assessments Expand the affected area if subsequent assessments, including the results of field measurements, indicates the need fl n new Upgraded PAR is identified. an Inifinl Notification Form SHALL be completed and DECLARATION 1I2-EPPIIP 4.1 Attachment A (Page 1 of 2)
A5.715GP f----
4 OFFSITE PROTECTIVE ACTIOE r,
~
I Projected dose at EAB YES \\
Dose projection results available (FSAR, monitor data, etc.)?
--7(
YES
>I REM TEDE or Obtain the following information:
1 )
35' wind speed MPH
2) 150' wind direction demees
3) 500' wind direction deerees IS AT LEAST ONE OF THE FOLLOWlNG TRUE?
Is either the 150' 500' wind directions unavailable?
35' wind speed LESS than 2 MPH (or unavailable)"
The difference between the 150' and 500' wind directions is 2 165 and 2 195 degrees? (opposite wind directions) or unavailable?
Release (other than a non-routine minor release below Federally approved operating limits or wholly comprised of tritium) has started Release transport will span sunrise or sunset hours.&
NWS forecast indicates a weather front (Wind speed increased by more than 20%, or, wind direction changes by more than one sector, or, stability class changes one or more classes towards stable (e.g., ABC to D, E to FG, etc.) will pass thru EPZ during release transDort.
is imminent. (within one hour)
TSC/EOF OSLY:
rrpproprinte ofsite agencies notified within I5 minutes (this does not chnnge the emergency clnssijicntion stntus).
I Recommend EVACUATE 0-5 miles, 360 degrees AND SHELTER the remainder of the I O mile EPZ AND advise the general public to administer KI in accordance with the State Plan.
(Minimum Recommendation)
I
' K / J \\
DOWNWIND WEDGE DETERMINATION 1 ) Obtain 150' and 500' Wind Direction 2 ) Using each wind direction, determine 3 ) Combine Sectors for PAR Sectors per the Chart below
\\Viiid Downwind Sector From Wedge Sectors
.A 350- 1 1 GHJKL 3
12-34 C
35-56 D
57-79 E
80 -101 F
102 -124 G
125 -146 H
147 -169 J
170-191 K
I92 -214 L
215 -236 M
237 -259 N
260 -281 P
282 -304 Q
305 -326 R
327 -349 HJKLM JKLMK KLMNP LMSPQ MNPQR NPQRA PQRAB QRABC RABCD ABCDE BCDEF CDEFC DEFGH EFGHJ FCHJK I
I I I
I I
I I
I I I I I I
I I
I I
I I I I
I I
13 Rev. 18
EPPDmplemen ting Procedures OFFSITE PROTECTIVE ACTIONS Projected release duration is less than one hour Release has started, TED Is less than YES is expected to Start YES (i,e.: LOCA with at least IOREM at EAB. +
within one hour.
+
one full train of sprays.)
"ECOMMENDATION FLOWCHART I I I
I 1
I I
Recommend SHELTER for the 0-10 mile EPZ.
YES

?

+
1/2-EPP/IP 4.1 Attachment A (Page 2of2)
A5.715GP Projected dose at 5 miles:
0-10 miles, 360 degrees.
I 1
YES
>I REM TEDE I
Or I
I I I i
-?
I I
I I I I I
I I
I I
. -~
I I I 1
I 2 miles, 360 degrees and AND SHELTER the remainder of the IO mile EPZ AND advise the general public to administer KI in accordance with the State Plan I
5 mile downwind wedge
. _~ I I
I I
I I 0-2 miles. 360 degrees, AVD SHELTER the remainder of the 10 mile EPZ.
accordance \\\\it11 the State Plan advise the general publ~c to administrr Kl in 14 Rev. 18

ML050900374

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