ML20070G819

Forwards Addl Info Requested Re 940330 Application for Amend to Licenses NPF-72 & NPF-77,revising Heatup & Cooldown Curves

ML20070G819
Person / Time
Site:	Braidwood
Issue date:	07/11/1994
From:	Saccomando D COMMONWEALTH EDISON CO.
To:	Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9407200307
Download: ML20070G819 (3)

Text

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f'1 ) Commonwealth Edison 1400 Opus Place Downers Grove, Illinois 60515 July 11,1994 l

l L Mr. William Russell, Director

! Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

• Attn: Document Control Desk f

Subject:

Braidwood Station Units 1 and 2 Additional Information Relating to the Request to Amend Technical Specification l Sections 3.4.9.1 and 3.4.9.3 NPF-72/77: NRC Docket Nos. 50-456/457 l

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References:

1) D. Saccomando letter to W. Russell dated l March 30,1994, transmitting request to amend Technical

[ Specification Sections 3.4.9.1 and 3.4.9.3 '

2) Teleconference conducted July 7,1993, between the Commonwealth Edison Company and the Nuclear Regulatory j Commission concerning the proposed Technical Specification '

Amendment to the Heat Up/ Cool Down Curves

Dear Mr. Russell:

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Reference 1 transmitted the Commonwealth Edison Company (Comed) request to amend Section 3.4.9.1 and 3.4.9.3 of the Technical Specification for Braidwood Units 1 and 2.

i Per your request during the Reference 2 teleconference, you will find in the

. attachment additional information that may be useful when reviewing this amendment request. This attachment specifically addresses the margins included in the development of the Low Temperature Overpressure Protection Setpoints.

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i Mr. Ruasell -

2- July 11,1994 If you have any questions concerning this correspondence please contact this office.

Sincerely, ,

Denise M. ccoman o -

uclear Licensing Administrator Attachment

, cc: R. Assa, Braidwood Project Manager-NRR S. Dupont, Senior Resident Inspector-Braidwood B. Clayton, Branch Chief-Region III Office of Nuclear Facility Safety-IDNS S

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.f Response to NRC Request for - l Additional Information for Braidwood 1 LTOPS j LTOP PORV .

MI or HI . App G - _

App G .

. Temp. ( F) Setpoint (psig) Overshoot (psig) Limiting Limit (psig) Martrin (psig) 70 490 30 MI - 521 1 97- 490 30 MI 545 :25 127 494' 30. MI 592 68-

!30 147 504 MI 637 103

.177 525- 30 hil 734 179 J

227 610 -35 HI . 1026* 381 (155)**-

277- 670 54 HI 1621* 897 (76)**

327 725. 74 HI ~*

(1)**

377 700 98 HI * -

.- (2)** '

• . A constant PORV piping structural integrity criteria of 800 psig is.conservatvely imposed for setpoint development when the-Appendix G limit exceeds 800 psig.

• • Margin to PORV piping structural limit in parenthesis.

Pressure channel measurement uncertainty (not accounted for in setpoint development): 60 psig u

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