ML20082S793

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Forwards Rev 54 to 1BWOA PRI-10, Loss of Residual Heat Cooling,Unit 1 & Rev 55 to 1BWOA PRI-10, Loss of Residual Heat Cooling,Unit 1 Per 910716 Request for Addl Info Re 891201 RHR Event
ML20082S793
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 09/10/1991
From: Checca A
COMMONWEALTH EDISON CO.
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20082S798 List:
References
NUDOCS 9109170297
Download: ML20082S793 (2)


Text

. - - _ _ _ _ _ _ _ _ _ - _

/ N- Commonwealth Edison

~/ ) ' .1400 Opus Place v

} Down:ts Grove, Illinois 60515 -

,- %j September 10,1991

+--

.0 Dr. Thomas E. Mudey, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk

Subject:

Submittal of additionalinformation concerning the event involving the Residual Heat Removal System on December 1,1989 Refsrence: July 16,1991 R.M. Pulsifer letter to T.J. Kovach

Dear Dr. Murley:

. The ebove reference requested additional information concerning the event of

' December 1,1989, involving the Residual Heat Removal (RHR) System. The purpose of -

th*s letter is to provide that information.

The attachment contains Commonwealth Edison's respotise to your questions.

If you have any further questions concerning this subject please contact A, Checca at (708) 515-7279.

Sincerely,

):Lc 9 'l W lcl A.R. Checca Nuclear Licensing Administrator At'achment cc: R. M. Pulsifer, Project Manager, NRR A. B. Davis, Re ion lil, Administrator g{

S. G. DuPont, esiden.t inspector, Braidwood ,og f (j I I

'2o917o297 siogio

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l ATTACHMENT A l

1 Request: Loss of RHR procedures (current and at the time of the event), l l

Response: Proceduro 1 BwOA PR!-10," Loss of RH Cooling Unit 1" REV. 54 was in ,

use at the time of the event and Rev. 55 of this procedure is currently '

being used. Copics of these procedures are enclosed.

Rey >est: Procedures for loss of reactor Coolant System (RCS) inventory during cold shutdown.

Response: Procedure 1 BwCA PRI 10," Loss of HH Cooling Unit 1," would also cover this evolution.

Request: Status of steam generators (SG) as a altemative means of providing decay heat removal (SG integrity, feedwater source, relief path).

4 Response: All four SG were available with water levels of between 63 and 69 percent,- No feedwater pumps (normal or auxiliary) were running during the event. A relief path was available through the SG power operated relief valves (PORVs),

l 5

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