ML20090E155
| ML20090E155 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/05/1984 |
| From: | Counsil W NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| F0570A, F570A, SD-57, NUDOCS 8407190322 | |
| Download: ML20090E155 (2) | |
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General Offices a Selden Street Berlin, Connecticut ne uwc'" '** ** ** **"
P.O. BOX 270
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(20H66-69M July 5,1984 Docket No. 50-423 F0570A Dr. Thomas E. Murley Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Design and Construction:
Two Potential Saf ety Issues (SD-57)
In a June 5,1984 telephone conversation between your Mr. T. Rebelowski and our Mr. R. R. Viviano, Northeast Nuclear Energy Company (NNECO), reported a potential significant deficiency in the design and construction of Millstone Unit No. 3 as required by 10 CFR 50.55(e). The potential significant deficiency involves the following two potential safety issues:
(1)
High Energy Line Breaks Outside Containment This safety issue concerns the temperature envelope requirements on the environmental qualification of equipment outside containment for high energy line breaks.
We are in the process of evaluating this potential safety concern.
A subsequent report will be provided to you by September 19, 1984.
(2)
Number of Reactor Coolant Pumps Operating in Mode 3 The second potential safety issue concerns the number of Reactor Coolant Pumps (RCP) which need to be operating in Mode 3. An inconsistency exists between the number of RCPs assumed to be operating in the Millstone Unit No. 3 FSAR Accident Analyses (two RCPs operating, one on standby) and the Westinghouse Standard Technical Specifications (one RCP operating, one on standby).
The Millstone Unit No. 3 Technical Specifications have not yet bs en submitted to the NRC. When they are submitted to the NRC in November 1984, they will reflect the number of RCPs operating in Mode 3 assumed in the safety analyses. As such, we do not consider this to be a potential significant deficiency.
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1 4> ' We trust that the above information satisfactorily responds to your concerns.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY k
Lb W. G. Counsil Senior Vice President cc:
Mr. R. C. DeYoung, Director Division of Inspection and Enforcement U. S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, MD 20014 CrA G**
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