ML20216G773
| ML20216G773 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/13/1998 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | Bowling M NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20216G780 | List: |
| References | |
| TAC-MA1084, NUDOCS 9803200086 | |
| Download: ML20216G773 (2) | |
Text
_
Mr. Martin L Bowling, Jr.
-March 13, 1998 Recovery Officer-Millstona Unit 2 Northe:st Nucle:r Energy Comp ny?
c/o Ms. Patricia A. Loftus Director-Regulatory Affairs a
P.O. Box 128 Waterford, CT 06385
SUBJECT:
REQUEST FOR RELIEF FROM ASME SECTION XI-MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 (TAC NO. MA1084)
Dear Mr. Bowling:
By letter dated March 3,1998, the Nnrtheast Nuclear Enerpy Company submitted a request for a one-time relief from the requirements of 10 CFR 50.55a(f) for performing the required inservice l
testing of certain Class 1 components in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI for Millstone Unit 3.
The staff concludes that pursuant to 10 CFR 50.55a(a)(3)(ii), the proposed alternative described in the enclosed safety evaluation is authorized in that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The alternative is authorized until the end of Refueling Outage 6.
Sincerely, Orig,inal signed by:
Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Safety Evaluation cc w/ encl: See next page DISTRIBUTION
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Mr. Martin L Bowling, Jr.
Recovery Officer-Millstone Unit 2 Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director-Regulatory Affairs P.O. Box 128 Waterford, CT 06385
SUBJECT:
REQUEST FOR RELIEF FROM ASME SECTION XI-MILLSTONE NUCLEAR 1
POWER STATION, UNIT NO. 3 (TAC NO. MA1084)
Dear Mr. Bowling:
l By letter dated March 3,1998, the Northeast Nuclear Energy Company submitted a request y a one-time relief from the requirements of 10 CFR 50.55a(f) for performing the required insarvice testing of certain Class 1 components in accordance with the American Society of Mechanical i
Engineers Boiler and Pressure Vessel Code Section XI for Millstone Unit 3.
The staff concludes that pursuant to 10 CFR 50.55a(a)(3)(ii), the proposed alternative described in the enclosed safety evaluation is authorized in that compliance with the specified requirements
{
would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The attemative is authorized until the end of Refueling Outage 6.
I Sincerely,
/
Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Safety Evaluation cc w/ encl: See next page I