ML20076K965

Public Version of Rev 5 to Emergency Plan Implementing Procedure FNP-0-EIP-26, Offsite Notification. ,Transmittal Form & Procedure Request Form

ML20076K965
Person / Time
Site:	Farley
Issue date:	06/10/1983
From:	Hudspeth J, Odom J ALABAMA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20076K961	List: ML20076K965
References
FNP--EIP-26-1, FNP-0-EIP-26-01, NUDOCS 8307180319
Download: ML20076K965 (5)

Text

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a PROCEDURE REQUEST FORM FNP-0-AP-1

1. Procedure Number FNF-o E/F.devision Number f Procedure Title M f-f cin /Jof,-ftho7~rnm i Safety Related C Non-Safety Related C New Procedure Request C Procedure Revision, New Revision Number Change of Intent at Temporary Procedure Change, Effective until next permanent change, TCN R C

C Temporary Procedure Change, Req'd. by Plant Conditions, TCN _ l.

Temporary Procedure Change, One Time Use DOCUMENT CONTRO

2. Change Summary CONTROLLED COPY DO NOT REPRODUCE 2.1 Procedure Page Numbers Affected by Change COPY NO. OM

/D 2.2 Description of Changes Tee M4Yo e l e d 2.3 Reason for Change nea WRe V es v vire me 3 -

3. Prepared By Nh/h ,, ,/4,MMunar , 6-7-PJ pgnature V

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Title Date

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4. Reviewed By Signature g

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Title

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5. Cross-Disciplinary /PORC Review Groun Signature Title Date

6. Temporary Change Approval (Signature /Date)

A Member Group Staff ww ( h / 8- 9-8J C

Eir Shift Foreman Senior Reactor Operator f/ /T////4 _ 4 CA / 64#3

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Y Plant Manager 4/ 4 h 'm-

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7. Final Approval (Signature /Date, required within 60 days of temporary approval)

1. 4 Group Supervisor fo Ma/ d / G/rola'3 C Plant Superintendent *' /

C MSAER /

.O Vice President -

Nuclear Generation /

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.c Plant Manager Jel . A W

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A I e FNP-0-AP-1

- FARLEY NUCLEAR PLA.Yr NUCLEAR SAFETY EVALUATION CECK LIST 9

(1) UNIT 3.M M

! (2) CECK LIST APPLICA3LE TO: FNF - o - 6.ffd 4 Revision TCN 6 '/9 (3) SAFETY EVALUATION - PART A 1

I The procedure, procedure change or modifcation to which this evaluation l is applicable represents:

(3.1) Yes No A change to the plant as described in the FSAR7 (3.2) Yes No /,A change to procedures as described h the FSAR7

' (3.3) Yes No / ,A test or experiment not described i:. the FSAR?

(3.4) Yes No / A change to the Technical Specifications?

If the answer to any of the above questions is "Yes," complete Item (4) and attach a 10CFR50.59 evaluation. If the answer to all of the above is "No," omit Item (4) and Item (9).

(4) SAFETT E7ALUATION - PART 3 (4.1) Yes No Will the probability of an accident previously evaluated in the FSAR be increased?

(4.2) Yes No Will the consequences of an accident previously evaluated in the FSAR be increased?

(4.3) Yes No May the possibility of an accident which is different than any already evaluated in the FSAR be created?

/ (4.4) Yes No Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?

(4.5) Yes No - Will the consequences of a malfunction of equipment important to safety different than any already evaluated in the FSAR be increased? ~

(4.6) Yes No May the possiblity of a malfunction of equipment important to safety different than any already evaluated in the FSAR be created?

(4.7) Yes No Will the margin of safety as defined in the basis to any Technical Specification be reduced?

If the answer to any of the above questions is "Yes," an unreviewed safety question is involved. Explain the basis for each answer provided in Section 4.

(5) REMARKS: (Attach additional pages if necessary)

(6)

(7)

PREPAED 3Y: dh [rkw REVIEWED 3Y:(//5///Mm dCL /fd

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DE DATE M -. M

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(3) PORC REVIEW: /) DATE /

(9) NORS REVIEV: DATE l Dis tribution

. Original: Document Control File A21 6226 Figure 3 Rev. 7 1

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• VOLUME 14 , FNP-0-EIP-26 I

specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.

e 5.11.2 Abnormal degradation discovered in fuel cladding, reactor coolant pressure' boundary, or primary containment.

5.11.3 Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR.

5.11.4 Errors discovered in the transient or j accident analyses or in the methods used

! for such analyses as described in the l safety analysis report or in the bases i for the technical specification that l have or could have permitted reactor operation in a manner less conservative than' assumed in the analyses. -

e 5.11.5 Performance of structures, systems, or t

I, components, that requires remedial

.2 V

l action or corrective measures to prevent operation in a manner less conservative than ' assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery '

during. plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or! corrective measures to prevent the existence or development of an unsafe condition.

5.12 The Director of the NRC Regional Office shall be i notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by commercial telephone, in the event that an unusual or important event occurs that causes a significant environmental impact from plant (s) operation, or that.has high public or potential public interest concerning environmental impact from plant (s) operation.

NOTE: A written followup report to the NRC is due within 10 days of the event.

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m AlabamaPower  !

the SOJ!n&m e eC:nC S/S!e71 s June 14, 1983 Director NRR Nuclear Reactor Regulations USNRC Phillips Building (

7920 Norfolk Avenue Bethesda, MD 20014 j

Dear Sir:

In accordance with Alabama Power Company Administrative Procedure FNP-0-AP-4, Control of Plant Documents and Records, attached are revisions  ;

to Emergency Plan Implementing Procedures.

Please verify that you have the procedures with the corresponding copy numbers that are on the Document Transmittal Form.

Please sign and return the forms as soon as possible to the following

- address: '

Alabama Power Company Farley Nuclear Plant Box 470  ;

Ashford, AL 36312  !

ATTN: Document Control Supervisor l If you should have any questions, please call me at (205) 899-5156 ,

Extension 422.

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byB/Hudspeth f

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Director NRR Nuclear Reactor Regulations USNRC b

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Dear Sir:

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,In'accordance with ' Alabama ' Power Company Administrative Procedure J

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f FNP-0-AP-4', control 'of Plant DoEuments and Records, atitached are revisions i to Emergency Plan Implementing Procedures. -

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.Please verify that,you have.the. procedures with the corresponding copy- '

e numbers that are on'the Document Transmittal. Form.

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,Pleasesignand'returnthejformsassoonas_possibletothefollowing, 7,

i address: ,

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Alabama Power Company.

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.,- Farley Nuclear Plant ' ,.

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Box 470 ,-

Ashford, AL 36312 ATTN: Document Control Supervisor f

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If you should have any questions, please' call me at (205) 899-5156 E Extension 422. -

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E Sincerely,

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yBfHudspeth f ,

E _ Document Control Supervisor e

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cc: Larry W. Enfinger- yf- '~~ - 4 -

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