ML20148H394

Responds to Util 710806 Proposed Change 97,720204,0310,20 & 30 Suppls & 720115 Revised Loss of Coolant Analysis.Change 97 Authorized Per 10CFR50.59.Tech Specs Changes Encl

ML20148H394
Person / Time
Site:	Yankee Rowe
Issue date:	04/14/1972
From:	Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
To:	Vandenburgh D YANKEE ATOMIC ELECTRIC CO.
Shared Package
ML20148H398	List: ML20148H394
References
NUDOCS 8011180297
Download: ML20148H394 (2)

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L J. Buchanan; ORNL :. g APR 141972 L CAL PDR L N  ;

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DRL Reading gy anc a n Docket No. 50-29 R. Tedesco, T. Carter ] '( ~

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Yankee Atomic Electric Company T ets ATTN: Mr. Donald E. Vandenburgh R. Boyd 3 c',Md , EM Vice President /

20 Turnpike Road R. DeYoung 3 0.0 C 3

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p. Sk vholt Vestboro, Massachusetts 01581 Change No. 97 ,

Gentlemen: License No. LPR-3 g ;

This refers to your Proposed Change No. 96 dated August 6,1971, including j four supplements dated February 4, March 10, 20 and 30,1972, and your * '

" Revised Loss of Coolant Analysis" dated January 15, 1972. These documents have been submitted in support of your request for certain changes to the  ;

Technical Specifications appended to License No. DPR-3 for the Yankee .p reactor to allows (1) loading and operation of the reactor with zirealoy $!.

clad fuel in the Core X configuration at power levels that are authorized Q presently, (2) modifications to the Emergency Core Cooling System to g upgrade its performance capabilities, and (3) modifications to the reactor protection system, involving the reactor coolant flow and the steam jg pg

, generator low level safety channels. We have designated our action on the proposed changes as change No. 97. @M 4 y We have reviewed your Proposed Change No. 96 and supplemental documents that L, f bg include the information on the design, fabrication and testing of the proposed @p modified facility features, the safety considerations you have evaluated, the  ?

proposed changes to the Technical Specifications and the supporting revised Q cections of the Safety Analysis Report. We have concluded that: (a) the oafety related characteristics of Core X are not significantly different NyN from those of previous cores, (b) the proposed modifications to the Emergency Core Cooling System provide a significant improvement in the capability to  %

pI cool the core in the ever.t of a loos-of-coolant accident, (c) the performance of the upgraded Emergency Core Cooling System has been analyzed in accordance ff

• l with the prescribed evaluation models and meets the criteria for Emergency ,

Core Cooling System performance in the Commission's " Interim Policy Statement",

dated June 29, 1971, and (d) the proposed modifications to the reactor ;y protection system safety channels will enhance the safety of reacter operation. d og JHlS DOCUTI C0"TES Y

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Yankee Atomic Electric Company APR 141972 .

In our evaluation of Proposed Change No. 96, we also have taken into account your planned actions fcr improving the Emergency Core Cooling System initiation instrumentation by providing diversity of initiation '

signals, and for the installation of means for mixing, sampling and control of hydrogen gas that may acaumulate inside the, vapor container in the event of a loss-of-coolant ac ident. These installations will be completed at the end of the outage for refueling with Core XI.  ;

1 Based on our review of the information presented in Proposed Change No.

96 and supplements, we have concluded that there are no hazards consid- 7 erations not described or implicit in the Safety Analysis Report.. fThere is reasonable assurance that the health and safety of the public will not g be endangered by the proposed facility modifications, refueling with Core X and operation of the reactor up to presently authorized power levels.

- s Accordingly, pursuant to Section 50.59 of 10 e7R Part 50, Change No. 97 is "i hereby authorized as proposed. The Technical Specifications in Appendix A to License No. DPR-3 are changed as set forth in Attachment A to this letter. <

Sincerely, j l@

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Donald J. Skovholt #

Assistant Director hU for Reactor Operations W Division of Reactor Licensing i 4 .: ,

Lnclosure: Mf i Attachment A - Change to the M, Technical Specifications k.'+

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cc: C. Duane Blinn, Esquire Day, Berry & Howard Counselors at Law y

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