ML20148H394
| 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: |
| References | |
| NUDOCS 8011180297 | |
| Download: ML20148H394 (2) | |
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b W. Dooly, DR iT G.
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H. Shapar, OGC N. Dube, DRL (5)
L J. Buchanan; ORNL :.
g APR 141972 L CAL PDR L N ocket File 5 h..
DRL Reading gy anc a n Docket No. 50-29 R. Tedesco, T. Carter
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R. S11ger, R. Schemel C. Lo A.
Yankee Atomic Electric Company T ets ATTN:
Mr. Donald E. Vandenburgh R. Boyd 3 c',Md, EM Vice President
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R. DeYoung 3 0.0 C 3
- f 20 Turnpike Road
- 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 jg protection system, involving the reactor coolant flow and the steam pg
, generator low level safety channels. We have designated our action on
@M the proposed changes as change No. 97.
4 y L, f We have reviewed your Proposed Change No. 96 and supplemental documents that bg include the information on the design, fabrication and testing of the proposed
@p modified facility features, the safety considerations you have evaluated, the
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proposed changes to the Technical Specifications and the supporting revised Q
cections of the Safety Analysis Report. We have concluded that:
(a) the NyN oafety related characteristics of Core X are not significantly different 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 ff of the upgraded Emergency Core Cooling System has been analyzed in accordance
- 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.
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Yankee Atomic Electric Company APR 141972
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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
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Donald J. Skovholt Assistant Director hU for Reactor Operations W
Division of Reactor Licensing i
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Lnclosure:
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Attachment A - Change to the M,
Technical Specifications k.'+
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cc:
C. Duane Blinn, Esquire Day, Berry & Howard y
Counselors at Law r;
1 Constitution Plaza
.,3 Hartford, Connecticut 06103 7
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