ML20083A418
| ML20083A418 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/03/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083A413 | List: |
| References | |
| NUDOCS 9505100244 | |
| Download: ML20083A418 (3) | |
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A UNITED STATES j-j NUCLEAR REGULATORY COMMISSION s
WASHINGTON, D.C. 2006H001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.187 TO FACILITY OPERATING LICENSE NO. DPR-65 NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 DOCKET NO. 50-336
1.0 INTRODUCTION
By letter dated October 18, 1994, as supplemented February f t,1995, the Northeast Nuclear Energy Company (the licensee) submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 2 Technical Specifications (TSs). The proposed amendment would require three Type A overall Integrated Containment Leakage Tests be conducted at approximately equal intervals during shutdowns during each 10-year service period.
For the third Type A test for the second 10-year period, it would be conducted during the thirteenth refueling outage extending the second 10-year service period to the end of the thirteenth refueling outage. The amendment would also change the Containment Leakage Bases by reflecting the conditions of a proposed exemption to 10 CFR 50, Appendix J, that would remove the requirement that the third Type A test for each 10-year period be conducted when the plant is shutdown for the 10-year plant inservice inspection. The February 21, 1995, letter withdrew the action related to conducting the third Type A test for the second 10-year period during the thirteenth refueling outage and the reference to a proposed exemption to 10 CFR 50, Appendix J, that would remove the requirement that the third Type A test for each 10-year period be conducted when the plant is shutdown for tha 10-year plant inservice inspection. The referenced proposed exemption wi s i f +.hdrawn by another letter dated February 21, 1995.
2.0 EVALUATION The second 10-year inservice inspection period is between June 1985 and June 1995. The 10-year inservice inspection will be performed in March 1995 during shutdown for the twelth refueling outage as required by the current TS.
Allowing the tests to be conducted at approximate equal intervals during the next 10-year inspection period would place the next test to be conducted at an 9505100244 950503 PDR ADOCK C5000336 P
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interval of 2-3 months greater than equal intervals as the proposed amendment
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would specify. This is considered not significant considering the following:
Type A tests are performed to ensure that the total leakage from containment does not exceed the maximum allowable primary containment leakage rate at the design pressure. This assures compliance with the dose limits of 10 CFR Part 4
100.
' The proposed change to Surveillance Requirement 4.6.1.2.a of the Millstone Unit No. 2 TSs will increase the flexibility for scheduling the Type A tests.
It does not modify the maximum allowable leakage rate at the design containment pressure, does not impact the design basis of the containment, and does not make any physical or operational changes to existing plant structures, systems, or components.
Further, the proposed change is consistent with the requirement in 10 CFR Part 50, Appendix J.
Historically, Type A tests have a relatively low failure rate where Type B and C testing (local leakage rate tests) could not detect the leakage path. Most Type A test failures are attributed to failures of Type B or C components (containment penetrations and isolation valves). Type B and C components are tested per Surveillance Requirement 4.6.1.2.d of the Millstone Unit No. 2 TSs.
These tests are required to be conducted at intervals no greater than 24 months. These local leakage rate tests provide assurance that containment i
integrity is maintained. The Type B and C tests will continue to be pe-formed i
in accordance with the requirements of Surveillance Requirement 4.6.1.14.
i The previous Type A, B, and C tests demonstrate that Millstone Unit No. 2 has maintained control of containment integrity by maintaining a conservative l
margin between the acceptance criterion and the "As-Found" and "As-Left" l
1eakage results.
Based on this,'the Millstone Unit No. 2 containment is i
considered to be in sound condition.
Based on the above, the staff has determined the proposed changes to the TSs
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to be acceptable.
3.0 STATE CONSULTATION
i In accordance with the Commission's regulations, the Conneett.ut State i
official was notified of the proposed issuance of the amenomtnt. The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
L The amendment changes surveillance requirements. The NRC staff has determined r
that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released l
offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a i
proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (60 FR j
16191). Accordingly, the amendment meets the eligibility criteria for i
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. categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: G. Vissing Date: May 3, 1995 i
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