ML20236K688
| ML20236K688 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/01/1998 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | Bowling M, Loftus P NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20236K692 | List: |
| References | |
| TAC-M96200, NUDOCS 9807100044 | |
| Download: ML20236K688 (3) | |
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WASHINGTON, D.C. 20656-0001 4p*****/
July 1, 1998 1
Mr. Martin L. Bowling, Jr.
l Recovery Officer -Technical Services Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director - Regulatory Affairs P. O. Box 128 i
Waterford, CT 06385
SUBJECT:
EVALUATION OF RELIEF REQUESTS, RR-89-19 AND RR-89-20, FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), SECTION XI REQUIREMENTS RELATING TO SNUBBERS AND RELIEF VALVES FOR MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 (TAC NO. M96200)
Dear Mr. Bowling:
i By letter dated July 2,1996, Northeast Nuclear Energy Company (NNECO) submitted its Third I
10-Year Interval inservice inspection (ISI) Program Plan, Revision 2, and associated requests for i
relief (RRs) and proposed alternatives (pas) for Millstone Nuclear Power Plant, Unit No. 2.
Additional information was provided by NNECO in its letters dated March 20,1997, August 28, I
1997, and October 31,1997.
l l
Included in the submittal were RR-89-19 and RR-89-20, which are related to the inservice testing
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(IST) program and have been evaluated independent from the other RRs and pas included in the submittal for the third 10-year interval ISI program. RR-89-19 and RR-89-20 requested relief from the visual examinations and functional testing requirements for snubbers and the requirement to develop a replacement plan when removing pressure relief valves for testing, respectively.
l Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a requires that certain ASME Code Class 1,2, and 3 components shall meet the requirements of Section XI of the ASME
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Boiler and Pressure Vessel Code (ASME Code) and applicable addenda, except where relief has been requested and granted or proposed altematives have been authorized by the Commission
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pursuant to 10 CFR 50.55a(f)(6)(i) and (g)(6)(i) when it has been demonstrated inat the Code requirements are impractical.
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l Section 50.55a(a)(3) states that a:tematives to the requirements of paragraphs (f) and (g) may be used, when authorized by the NRC, if (i) the proposed attematives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
I The NRC staff has reviewed the information provided by NNECO in support of RR-89-19 and RR-89-20. Based on its review of the information provided using the preceding criteria, as detailed in the staff's Safety Evaluation (SE) (er, closed), the NRC staff has determined that:
(1) The proposed attemative provided in RR-89-19 to use the Millstone Unit No. 2, TSs in lieu of the ASME Code,Section XI, Paragraph IWF-5000 requirements for snubber examination and testing prov! des an acceptable level of quality and safety and that r,ompliance with the applicable portions of the Code requirements will result in a hardship without a compensating increase in nmr JA
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9007100044 980701 PDR ADOCK 05000336 P
l-M. L Bowling !
to the ASME Code,Section XI, IWA-7000 requirements for developing a replacement plan when
. removing pressure relief valves for testing, provides an acceptable level of quality and safety and is, therefore, authorized pursuant to 10 CFR 50.55a(a)(3)(i). The use of this Code Case is Mhorized for the third 10-year IST interval or until it is included in a future revision of Regulatory l
Guide (RG) 1.147. At that time, NNECO is to follow all provisions in the Code Case, with limitations issued in the RG, if any, should NNECO continue to use the Code Case.
l This completes all NRC staff actions related to the referenced TAC number.
Sincerely, Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation Docket No. 50-336 i
Enclosure:
As stated cc w/ encl: See next page l
l l
l I
l M. L. Bow (ing July 1, 1998 l
to the ASME Code,Section XI, iWA-7000 requirements for developing a replacement plan when removing pressure rslief valves for testing, provides an acceptable level of quality and safety and is, therefore, authorized pursuant to 10 CFR 50.55a(a)(3)(i). The use of this Code Case is authorized for the third 10-year IST interval or until it is included in a future revision of Regulatory Guide (RG) 1.147. At that time, NNECO is to follow ali provisions in the Code Case, with limitations issued in the RG, if any, should NNECO continue to use the Code Case.
This completes all NRC staff actions related to the referenced TAC number.
Sincerely, Original signed ly:
Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
As stated cc w/ encl: Sae next page Dj3JRIBUTION:
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