ML20043H393
| ML20043H393 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/18/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043H391 | List: |
| References | |
| NUDOCS 9006250352 | |
| Download: ML20043H393 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
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I WASHINGTON. D. C. 20666
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SAFETY.EVA}UATION.BY.TWE OFFICE OF. NUCLEAR RFAC1')R. REGULATION RELATED.TO AMENDMjNT.N0 14]
T0. FACILITY OPERATING LICENSE do.-OPR f5 N_0RTHEASTNUCLEAR_ ENERGY. COMPANY.ET.S 2
l MILLSTONE. NUCLEAR p0WER STAT 10N 0 NIT..NO. 2 1
DOCKET.N0.50 336 2
l 1.0 _ INTRODUCTION By application for license amendment dated March 19, 1990, Northeast Nuclear Energy Compair (the licensee) requested changes to the Technical Specifications (iS) for Millstee Nuclear Power Station, Unit 2.
The proposed amendment would change the Technical Specification Sections 4.4.9.3.1.d, 4.7.1.1 and 4.4.2 by specifying the surveillance Inservice Testing (IST) for the power operated i
relief valves (PORV's), main steam safety valves and the pressurizer safety valves respectively in accordance with Section 4.0.5 which specifies the IST in accordance with ASME Section XI Code Edition and applicable addenda as required by 10 CFR 50.5bo(g).
2.0 EVALUATION Specifically, the proposed amendment would change the way the Technical Specifications sections for IST requirements are specified for the PORV's (Section 4.4.9.3.1.d), main steam safety valves (Section 4.7.1.1) and pres-surizersafetyvalves(Section4.4.2).
Instead of identifying the specific
'ASME Section XI Edition Addenda-and Subsection, to which these valves are to be tested, each specification would require testing in accordance with Speci-l fication 4.0.5 which specifies the ASME Section XI Code Edition and applicable l -.
addenda as required by 10 CFR 50.55a(g). The proposed change would avoid the l
need to identify these details for each Technical Specification that relates to-E ASME Section XI. The changes would be editorial in nature and would not affect the plant's current practices in compliance with the surveillance requirements.
The staff has determined the proposed changes to be acceptable, i
I 9006250352 900618 Det ADOCK 0500 6
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, 3.0 (NVjRONMENTALCONSIDERATION The amendment changes surveillance requirements. We have determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The staff has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public conrent on such finding.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessirent need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public such activities will be ccnducted in compliar.ce wit 1 the Cormission's regulations, and(3)theissuanceoftheamendmentwillrotbeinimicaltothecommon defense and security or to the health and safety of the sublic.
Dated:
June 18, 1990 Principal Contribu, tor: G. Vissing
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