ML20099K111

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Forwards GE Proprietary Classification Sys,Thermal Hydraulic Analysis & Power Level Profile,Loca Analysis Per 10CFR50,App K,Proposed Tech Specs Revs & Failure Study on ECCS Manually Controlled Electrically Operated Valves.W/O Encls
ML20099K111
Person / Time
Site: Pilgrim, 05000000
Issue date: 07/09/1975
From: Galligan T
BOSTON EDISON CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20099K024 List:
References
FOIA-84-105 NUDOCS 8411290314
Download: ML20099K111 (4)
v • d • e


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10 CFR 50 APPENDIX K RFANALYSIS AND. PROPOS5 ,-

t TECHNICAL SPECIFICATIONS FOR PILGRIM NUCLFAR POWER STATION. UNIT 1 -

Dear Sir:

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In an order dated December 27, 1974, the NRC modified the operating license for j'

6 Pilgrim Nuclear Power Station, Unit #1, and required reanalysis of the effective-I ness of the Pilgrim Emergency Core Cooling Systems (ECCS) following a Loss of T. '

Coolant Accident (LOCA) in accordance with Section 50.46 and Appendix K of 10 CFR Part 50. The order further required that the reevaluation be performed in accordance with an acceptable evaluation model conforming to the provisions of

$10 CFR 50.46 and be submitted within six months of the date of publication of-the Order in the Federal Register (January 9, 1975). -

This reevaluation has been perforced by the General Electric Company utilizing an acceptable evaluation model consisting of the vendor evaluation model pre-

sented in draft topical report NED-20566 which has been modified in accordance with the changer described in the staff Safety Evaluation Report of the Pilgrim

) Nuclear Power Station, dated December 27, 1974, and is' hereby submitted pursuant \-

[, to your order of December 27, 1974. The ECCS reevaluation and proposed Technical 3

Specification revisions are similar to those transmitted to the NRC (AEC) by

Boston Edison Company on August 19, 1974. The ECCS reevaluation is contained in a- '

Attachment C to this letter and appropriate proposed Technical Specification re-g visions are contained in Attachment D.

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In a subsequent letter dated January 23, 1975, you requested Boston Edison to submit the analyses supporting proposed GETAB - based Technical Specifications

! on a schedule consistent with that for submittal of the ECCS reanalyses. These-Ii analyses are included in Attachment B to this submittal. .

In addition, your April 24, 1975 letter requested that Boston Edison review the"

)2 't ECCS reanalysis to verify that the effects of a single failure or operator error that causes any manually-controlled, electrically-operated valve to move to a ~

position that could adversely affect the ECCS was considered. -

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a t The ningle failure study contained in Attachment E to this letter indicates that 7 the single failures assumed in the ECCS reevaluation are more severe than postulated single failures of manually controlled electrically operated ECCS ).

valves.. Consequently, the ECCS reevaluation has appropriately assumed the- .;'

limiting single failure.

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1 In a letter. dated May 29,'1975, you requested Boston Edison to indicate hor '

j t.w the new calculational ~ method developed by General Electric for .determinind - -

4 void coefficients would be accounted for in the GETAB/GEXL submittal. Bes';on ,

l *, Edison notified you in a June 9,1975-letter that General Electric had advised g sic us that the new void coefficients had been utili ed in the calculation of the i$, Minimum Critical Power Ratio (MCPR) limits associated with the GETAB/GEXL pro-j- posed Technical Specifications contained in Attachment D to this letter. "

In a subsequent letter dated June 16, 1975, you ideatified certain information

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4 1 required by the Staff to complete its review of the ECCS reanalysis ~. Of thel

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six items ident'ified in Attachment 1 to your letter it appears that items num-

) bered 1 (Break Spectrum and Partial Loop Operation, 3 (Single Failure Analysis), ,i and 4 (Submerged Valves) are applicable to Pilgrim 1. The break spectrum and . O' .

]- Partial Icop Operation Item is addressed $n Attachment C to this letter. Analysis '

for Partial Loop Operation is presently being conducted and will be submitted when completed and reviewed. . The Single Failure Analysis, as noted above, is addressed

  • in Attachment E to this letter. The item identified as Submerged Valves ia cur-rently under review. A transmittal addressing this subject is currently scheduled fl 7

for submittal on or before August 9,1975.

4 We have been informed by the General Electric Company that dimensioned figures C-Sa, C-5b, -C-6a, C-7a, C-7b, C-7c, C-8a, C-9a, C-9b , ana- C-9e of Attachment C to this letter are considered propriet'ary by General Electric in .

acccrdance,with the procedures and standards set forth in Attachment A to this y '- letter, and that this information should be withheld from public disclosure in accordance with the provisions of 10CFR2.790. The analytical methods and the data which would be compromised by public disclosure of these figure's were developed at considerable expense to the General Electric Cc=pany and tt a re-lease of the information would allcw competitors to confirm similar desias

, without incurring similar expense.

The Boston Edison Company has proprietary agreements with the General Electric Company and has handled this information in accordance with those agreements and Attachment'A. ,

Accordingly, the ECCS reanalyses Boston Edison has. submitted in accordance with ,

I the NRC order of December .27,1974 contain non-proprietary, non dimensioned j . versions of the appropriate proprietary curves to allow continuity during review of the non-proprietary submittal. The proprietary curves are being transmitted

.under separate cover. ,

1 -t 1 The proposed Technical Specifications contained in Attachment D to this letter - *

have been given pre 14=4 navy reviev and approval by the Operaticus Review Com- f'

~.1 mittee and review by the Nuclear 5 sfety Review and Audit Committee. However, j due to the schedule for submittal of this material required by the NRC order u of December 27, 1974 and the recent completion of portions of the calculations

', required =td develop these proposed Technical Specification revisions, our review '

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July 9, 1975

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of this tnterial vill necec:arily centinue following its edbrittal en July 9, y

  • 1975. Errata, if any, vill be identified as necessary following this addi-f

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tional review.

Te the best cf our knowledge the'inforcation centained herain and attached f~ hereto fulfills, encept as noted.in cur respence to the Sub=crged Vc.lve and

.1 Partie.1 Loop Operation portions of your June 18, 1975 letter, the recuirenents

[ cf your Dece: er 27, 1974 order for Modification of Licence and all subsequent J ccrrespcndence fren the IEC tc 3cston Edison concerning ECCS reanalysis and

't CP/n3/GEXLTechnicalSpecifications. Accordingly, 3ccten Edison Ccapany hereby requests that the Technical Specification reviciens prepoted in Attach =ent L to

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s this letter be issued.

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t a the interin' period until the proposed Technical Specificatiens are iscued,

, Pilgri: 1 vill be operated under the cost restrictivo linit of the specifica-tion containci in Attachment D to this latter, the current Techniet.1 Specifi-E cation:, and Of.e limits imposM by the IGC Order of Decc=ber 27, 1974.

a Plearc adviso us if you have a ther question reccrding this submitts.l.

Very truly yours.

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. President Cc..r.arxealth ci Massachusetts )

County of Suffolk )

Teen p2rsonclly appeared before ac Thomas J. Galli;;an, Jr. , who, b ing duly cora, did state that he is President of Boston Edison Ocs; cny, the applic .c.t barain, and that he is duly' authorized ta execute and file the proposed

, 7echri al' Specification revisions described herein in the name and on bahalf of B:ston Edison Cocpany and that the stata=ents in said proposed revistor.:-

cra true to the best of his knowledge and belief.

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1-July 9, 1975-

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Divicion of Reactor Licensing

. Attachments l A. GE Proprietary Classification System i B. Thermal Hydraulic Analysis (GETAB) and Power Level Profile for Pilgrim Nuclear Power Station, Unit 1, Cycle 2 i C. Pilgrim Nuclear. Power Station Loss of Coolant Accident Analyses in ,

! Conformance with Section 50.46 and Appendix K to 10CFR50 -

D. Proposed Technical Specification Revisions

- E. Single failure study on Emergency Core Cooling System Manually Controlled

. Electrically Operated Valves ~

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cc: Messrs. J. E. Larson '!

i.! - . E. F. Kearney .

J. A. Smith W. M. Sides D. G. Stoodley

, Boston Edison Company Reading Room bec: Messrs. A. F. Corry W. F. Roche J. E. Howard i J. A. Seery e

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