ML20041A638

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Forwards Application for Amend to License DPR-53,to Allow Operation of Sixth Cycle
ML20041A638
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 02/17/1982
From: Lundvall A
BALTIMORE GAS & ELECTRIC CO.
To: Clark R
Office of Nuclear Reactor Regulation
Shared Package
ML20041A639 List:
References
NUDOCS 8202220370
Download: ML20041A638 (2)


Text

, r EALTIM O R E GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475

  • BALTIMORE, MARYLAND 21203 ARTHUR E. LUNDVALL Ja.

"["ff" February 17,1982 q

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission

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Washington, D.' C. 20555 _. *.T p- ' W.

ATTENTION: Mr. R. A. Clark, Chief C t 3ghl9g7 f

  1. 4 Operating Reactors Branch #3 g  % f? I g "C C Division of Licensing 4M ~

SUBJECT:

Calvert Cliffs Nuclear Power P ~

Unit No.1, Docket No. 50-317 Amendment to Operating License DPR-53 Sixth Cycle License Application Gentlemen:

Baltimore Gas and Electric Company hereby requests an Amendment to Operating License DPR-53 to allow operation for a sixth cycle. The Enclosure to this letter presents discussions in support of the conclusion that the Safety Analyses discussed therein envelop and ensure conservative operation at a RATED THERMAL POWER of 2700 MWth.

Technical Specification Changes and Justification The proposed changes to the Standard Technical Specifications (STS) required by this Amendment are described in Chapter 9.0 of the Enclosure to this letter and justified by discussions in Sections 1.0 through 8.0 of the Enclosure.

Safety Analysis and Review This proposed amendment and these proposed STS changes constitute an

[ unreviewed safety question since the consequences of Design Bases Events l previously evaluated are slightly worse and because we propose some slightly less conservative bases for the Technical Specifications. However, the Enclosure presents analyses which demonstrate that acceptable limits on DNBR, fuel centerline temperature to melt, Reactor Coolant System upset pressure, and 10 CFR 100 site boundary dose rate guidelines would not be exceeded during a Design 7

Bases Event. i s

Our present intention is to begin the Unit I refueling outage on April 17, 1982, and to complete the outage and begin the approach to criticality on June 30, 1982, with return to power operation immediately thereafter.

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! 8202220370 820217 l PDR ADOCK 05000317 P PDR

Office of Nuclear Reactor Regulation February 17,1982 Page two The Plant Operations and Safety Re.new Committee (POSRC) and Offsite.

Safety and Review Committee (OSSRC) have reviewed this proposed Amendment and these proposed changes to the Standard Technical Specifications and have concluded that although they constitute an unreviewed safety question they do not present an undue risk to the health and safety of the public.

Very truly yours, BALTIMORE GAS AND ELECTRIC COMPANY

. ,if *-

A. E. Lundvall, Jr. f Vice President - Supply W3L/AEL/djw Enclosure (40 copies)

STATE OF MARYLAND, CITY OF BALTIMORE, TO WIT:

A. E. Lundvall, Jr., being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a Corporation of the State of Maryland; that he executed the foregoing Amendment for the purposes therein set forth; that the statements made in said Amendment are true and correct to the best of l his knowledge, information, and belief; and that he was authorized to execute the l

Amendment on behalf of said Corporation.

WITNESS my Hand and Notarial Seal.

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' * ' N6tary Public Copies To: 3. A. Biddison, Esquire (w/o encl)

G. F. Trowbridge, Esquire (w/o encl)

Mr. D. H. Jaffe - NRC Mr. P. W. Kruse - CE (w/o encl) k