ML20141K922: Difference between revisions

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| number = ML20141K922
| number = ML20141K922
| issue date = 05/26/1971
| issue date = 05/26/1971
| title = Forwards Util 710520 Ltr Clarifying Misunderstanding Concerning Reliability of Plant Onsite Emergency Diesel Generators
| title = Forwards Util Clarifying Misunderstanding Concerning Reliability of Plant Onsite Emergency Diesel Generators
| author name = Morris P
| author name = Morris P
| author affiliation = US ATOMIC ENERGY COMMISSION (AEC)
| author affiliation = US ATOMIC ENERGY COMMISSION (AEC)
Line 12: Line 12:
| case reference number = FOIA-91-282
| case reference number = FOIA-91-282
| document report number = NUDOCS 9203260113
| document report number = NUDOCS 9203260113
| title reference date = 05-20-1971
| package number = ML20091A092
| package number = ML20091A092
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE

Latest revision as of 10:06, 12 December 2021

Forwards Util Clarifying Misunderstanding Concerning Reliability of Plant Onsite Emergency Diesel Generators
ML20141K922
Person / Time
Site: Oyster Creek
Issue date: 05/26/1971
From: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
To: Bush S
Advisory Committee on Reactor Safeguards
Shared Package
ML20091A092 List: ... further results
References
FOIA-91-282 NUDOCS 9203260113
Download: ML20141K922 (3)


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  • ' UNITED STATES ATOMIC ENERGY. COMMISSION ,

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wAsmuoTon, o c rosas g De x p RECEIVED i r May 26, 1971 e " t'el 27 /M 9 3B l Docket No. 50-219 l

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i Dr. Spencer'H Bush Chairman, Advisory Committee 4- on Reactor Safeguards- l U. S.- Atomic Energy Commission

! Washington, D. C.- 20545 l-

Dear Dr. Bush. ,

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Three (3) copies of the following are transmitted ,

for information the Committee: i l

j l- Letter from Jersey Central Power 6 Light Company dated May 20, 1971, clarifying a misunderstanding concerning the reliability of.the Oyster Creek i on-site emergency diesel generators. l I

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g Sincerely, ,

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.L Peter A. Morris, Director Division of Reactor-Licensing.

Enclosures:

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Project: Oyster Creek Status: Provisional Operating License issued Operation at increased power level requested Backtroend: December 12, 1968 - ACRS operating license report April 9, 1969 - POL issued -

May 3, 1969 - Initial criticality December 22, 1969 - Completed 100 hr full power (1600 Mwt) demonstration May 5, 1970 - Amendment No. 55 requesting authorization to operate at 1690 th.>t June 2,1970 - Amend.rient No. 57 correcting and I supplementing Amendment No. 55 July 30, 1970 - Amendrant 1:o . 58, startup test results September 17, 1970 - Am.2ndment 1;o. 63, additional j

information in support of Amendment No. 55 i September 30, 1970 - DRL report on the proposed power increase to 1690 thit October 14, 1970 - Subcommittee meeting October 15, 1970 - ACRS meeting November 10, 1970 - Supplemeatal DRL report l November 11, 1970 - Subcommittee meeting j November 12-14, 1970 - ACRS meeting j

i November 17, 1970 - ACRS Report favorable to " mini

, stretch" to 1690 Met -

December 10, 1970 - Reactor operates at 1690 Mwt l December 30, 1970 - Amendment No. 65 requesting i

authorization to operate at 1930 th7t

' January 26, 1471 - Supplement No. I to Amendment No. 65 11ay 21,1971 - DRL report on the proposed power increase to 1930 Mwt May 2 6,1971 - Subcowaittee meeting June 10, 1971 - Supplc.nent No. I to DRL report June 10-12, 1971 - ACRS meeting '

Jersey Central Power and Light Company has requested a power Icvel increase for the Oyster Creek Nuclear Generating Station to 1930 Mwt which in the maximum capacity of the main turbine and about 70 Mw above the origint.1 " stretch" capacity.

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2 DRL has completed its review of the proposed power increase and is now cat is fied that operation at 1930 Mwt will not produce an undue risk to the health and safety of the public. DRL believes that l the I'CCS is adequate to cope with an LOCA at power levels up to 1930 M't.

Operation at 1930 thit 1spredicated on the availability of five relief valves. The fif th relief valve will not be available antil the Fall of 1971. Until such time as the fifth relief valve is installed the licensee proposes to limit power to 1865 Mwt.

l The Coraittee advised the licensee that i t would at terrpt to write a letter favorable to the power increase. Draft No. 1 of a letter is l I available for consideration at the June 16-17, 1971 Special ACRS mee t i n;; .

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