ML20236Q117
| ML20236Q117 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/14/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| 3706K, NUDOCS 8711190192 | |
| Download: ML20236Q117 (3) | |
Text
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fN (Commonwealth Edison In
. M
) One Fir:! N ?._ional Plaza, Chicago, Illinois -
(j} ' Chicago, Illinois 60690 - 0767 C
Address R;. ply to: Post Offica Box 767. -
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1 October 14, 1987 Mr. Thomas E. Murley, Director Office.of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission idashington, DC 20555 Attn: Document Control Desk
Subject:
Braidwood Station Unit 1
'10 CFR 50.59 Annual Report NRC Docket No. 50-456
Dear Mr. Murley:
Pursuant to 10 CFR 50.59(b)(2), attached you will find the required annual report for Braidwood Station (Facility Operating License No.
NPP-72). This submittal is. based upon the fuel load license (NPF-59) issuance date of October 17, 1986.
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The report consists of descriptions and safety evaluations for changes to the' facility as described in the safety analysis report. The report only contains changes made to the facility; no tests or experiments governed by paragraph (a) of 10 CFR 50.59 were executed.
please direct any questionc regarding this matter to this office.
Very truly yours, C. j%(
m A S. C. Hunsader Nuclear Licensing Administrator Cs l
Attachment I
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S. Sands NRC Region III Braidwood Resident Inspector
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Braidwood Nuclear Power Station Annual 10 CFR 50.59 Report 1987-
.o-Conunonwealth Edison Company NRC Docket No. 50-456 License No. NPF-72 l
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Modification: M20-0-87-015
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Description:==
This modification provided an additional high radiation isolation interlock for the Control Room HVAC (VC) system to meet the single failure criteria per an existing FSAR commitment.
Safety Evaluation Summary:
1.
The probability of an occurance or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not increased because an additional reiay is provided to enable the redundant detector to function independently in the damper control circuits. Their independent operation allows the damper circuit to isolate the control room on high radiation in the event of a single failure with the radiation control circuit. The function of the circuit is not changed.
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not expected because the system's function is not changed.
3.
The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the operation of the system is not changed.
3706K