ML19225C847
| ML19225C847 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/15/1979 |
| From: | Moody D Maine Yankee |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| WMY-79-63, NUDOCS 7908020588 | |
| Download: ML19225C847 (2) | |
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ENGINEERING OFFICE WEST 8ORO, MAtSACHUSETTS 01531 C17-3G6-9011
+* b _ s__- Q WMY 79-63 June 15, 1979 United States Nuclear Regulatory Consission Office of Inspection and Enforcement Region I
'231 Park Avenue King of Prussia, Pennsylvania 19406 Attention:
Boyce H. Grier, Director
References:
(1)
License No. DPR-36 (Docket No. 50-309)
(2)
(3)
IE Bulletin No. 79-OlA.
(4)
Le t t e r, MYAPC t o US AEC, d a ted Jun e 7, 19 73 (5)
Supplementary Repo rt on Ef f ects of a Postulated Break in a High Energy Piping System Outside the Containment, Maine Yankee Atocic Powar Sta tion, dated September,19 73.
Dear Sir:
Subject:
Environmental Qualification of Class 1E Equipment Reference (2) required action to be taken on providing written evidence of the qualification of electrical equipment required to function under postulated accident conditions at Ibine Yankee.
In compliance with are providing the follcwing responses:
this requirecent, we 1.
Insid e Reacto r Conta inmen t The environmental qualifications of electrical equip =ent located inside the reacto r containment wh'ich are required to remain operable during and/or sub sequent to a Design Basis Accident (DBA) have been reviewed for adequacy. This inf ormation is provided in YAEC Report No. 1130A -
" Summary: Environmental Qualifications of Saf ety Related Electrical Equipment Within the Reactor Containment at Maine Yankee Atcaic Power Station" which is enclosed as Attachment 1.
II.
Out sid e Re acto r Containmen t investigated for the ef fects of postulated The Maine Yankee Plant wa s high energy piping sys ten breaks outside reactor containment.
Mcdifi cations.e re cade to assure safe shutdcun capability f ollowing a postulated rupture.
The results of the analyses and a brief 430 016 7908020 6 if13
U.S. Nuclear Regulatory Cocaission June 15, 1979 Attn: Of fice of Inspection and Enforcement Page 2 description of the modificatious were reported to the AEC in Reference (4).
Reference (5) is a supplemental report presenting additional info rmation necessary to review Ref erence (4).
III.
Conclusions a)
Inside Reactor Containment The results of our investigation into the environmental qualifications of the safety-related electrical equipment identified in YAEC Repo rt llSOA in icate that adequa te environmental qualification documentation is available for all electrical equipcent.
b) Out side Re actor Containnen t Review of References (4) and (5) indicate that since the required codifications have been cade, there are no longer any e acerns about abnormal environ = ental conditions ror electrical equipment outside the reactor contain=ent.
Reference (3) requires that infor=ation be provided concerning ASCO solenoid valves used in safety-related systems at Maine Yankee. We believe that we have adequately answered these concerns in our above responses to Reference (2).
In addition, a preventive maintenance program will be conducted in accordance with the requirements of this bulletin (Ref. 3)).
We trust that this information is satisf acto ry ; however, should you have any f urther questions, please contact us.
Very truly yours, MAINE YANKEE ATCMIC POWER COMPANY I p,
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E' D.[I. Moody Manager of Operations 430 017
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