ML20009H202

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Forwards Safety Evaluation & Technical Evaluation Re Licensee Response to IE Bulletin 80-06 Concerning ESF Reset Control Design Deficiency.Requests Confirmation of Valve Mods Prior to Refueling Outage
ML20009H202
Person / Time
Site: Millstone 
Issue date: 07/24/1981
From: Lainas G
Office of Nuclear Reactor Regulation
To: Jordan E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20009H203 List:
References
IEB-80-06, IEB-80-6, NUDOCS 8108070022
Download: ML20009H202 (1)


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DISTRIBUTION:

"Y Docket No. 50-245 ORB #5~RF Subject File MEMORANDUM FOR:

E. L. Jordan, Deputy Director Division of Resident and Regional Reactor Inspection. IE FROM:

Gus C. Lainas, Assistant Director for Safety Assessment Division of Licensing

SUBJECT:

MILLSTONE 1 - ESF RESET CONTROL DESIGN DEFICIENC/ -

I&E BULLETIN 80-06 Task Interface Agreement ROI-80-15 assigned the responsibility to the Office of Nuclear Reactor Regulation for reviewing the licensee's responses to Items 1 and 3 of I&E Bulletin 80-06. Our review of Northeast Nuclear Energy Company responses to the bulletin for the Millstone Unit No.1 are coeplete. The Technics 1 Evaluation Report (TER) prepared by our contractor EG8G and our Safety Evaluation Report (SER) are enclosed.' )

We have concluded that the licensee has satisfied the concerns of I&E Bulletin 80-06 having completed modifications to four iso-condenser valves that could have moved from the " EMERGENCY" mdde upon ESF reset in accordance with the n#ked up drawings of the proposed modifications that NyECO provided to EG&G/SRO. Please confirm that the valves were modified and tested as scheduled prior to returning th power following the 1980-1981 extended refueling outage.

Original signed By:

G. C.1.ainas Gus C. Lainas, Assistant Director for Safety Assessment Division of Licensing

Enclosures:

As stated cc w/ enclosures:

S. Minor D. Crutchfield H. Smith J. Shea e108070022 810724 PDR ADOCK 05000245 G

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