ML20137N561
| ML20137N561 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/13/1985 |
| From: | Mroczka E, Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-PT21-86-054-000 F0892A, PT21-86-054-000, SD-82, NUDOCS 8512040139 | |
| Download: ML20137N561 (2) | |
Text
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(203) 665-5000 November 13,1985 Docket No. 50-423 F0892A Dr. Thomas E. Murley Regional Administrator U.S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406
References:
(1)
- 3. F. Opeka letter to T. E. Murley, F0779A, dated June 6, 1985.
(2)
- 3. F. Opeka letter to T. E. Murley, F0788A, dated August 29, 1985.
(3) 3.
F.
Opeka letter to T.
E.
Murley, F0844A, dated September 30,1985.
/
(4)
- 3. F. Opeka letter to T. E. Murley, dated October 30,1985.
Dear Dr. Murley:
Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Accordance with 10CFR50.55(e):
Core Exit Thermocouples (SD-82)
In a May 9,1985 telephone conversation between your Mr. T. Rebelowski and our Mr. R. K. McCarthy, Northeast Nuclear Energy Company reported a potential significant deficiency in the construction of Millstone Unit No. 3 in accordance with 10CFR50.55(e). The potential significant deficiency involved the core exit thermocouple systems provided by Westinghouse.
As noted in Reference (1), while performing equipment qualification testing of the core exit thermocouples, Westinghouse noted that the total system error exceeded the errors assumed in the Westinghouse Emergency Response Guidelines. These guidelines were used to develop the Emergency Operating Procedures (EOPs).
References (2),(3) and (4) provided status concerning our efforts to resolve this issue. As noted in Reference (4), an evaluation has been performed to address the impact of increased core exit temperature errors in the EOPs. Westinghouse has determined that the Millstone Unit No. 3. specific errors for core exit temperature are 200F, normal environment and 490F, adverse environment.
8512040139 851113 a n PDR ADOCK 05000423 8 V S
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f.e..- - Based upon these values, Westinghouse has calculated new EOP setpoints to be used in the Millstone Unit 3 EOPs. No changes other than the setpoints, are required to address the increased core exit temperature error.
Based on the Millstone Unit No. 3 Plant Specific _ Setpoints for Emergency Operating Procedures, Revision 1, (which is based on Revision I of the Westinghouse Emergency Response Guidelines) we consider this not to be a significant deficiency for Millstone Unit No. 3.
As such, we consider this to be our final report for SD-82.
This final report is being provided on November 13, rather than November 12, as discussed with your Resident Inspector, Mr. F. Casella.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY J F. Opew J. F. Opeka Senior Vice President By: E. J.jfAroczka (/
Vice Pro 4ident cc:
Mr. 3. M. Taylor, Director Division of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l
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