ML20070G819
| 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
i
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:
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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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 -
Additional Information for Braidwood 1 LTOPS j
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 68-147 504
!30 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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