ML20059L694
| ML20059L694 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/10/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059L690 | List: |
| References | |
| NUDOCS 9311170294 | |
| Download: ML20059L694 (3) | |
Text
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UNITED STATES D
NUCLEAR REGULATORY COMMISSION Qv
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WASHINGTON. D.C. 20555-0001
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I SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i
RELATED TO AMENDMENT NO. 68 TO FACILITY OPERATING LICENSE NO. DPR-21 i
NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NVCLEAR POWER STATION. UNIT 1
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DOCKET NO. 50-245 i
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1.0 INTRODUCTION
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By letter dated September 1,1993, the Northeast Nuclear Energy Company (NNECO) submitted a request for changes to the Millstone Nuclear Power j
Station, Unit 1 Technical Specifications (TS). The requested changes would revise the surveillance requirements for locel leak rate testing which are included in TS Section 4.7.A, to remove the 5% L limit. Removing the limit will allow Millstone Unit I to address individual, penetration leakage while maintaining the overall leakage rate for Type B and -l tests below the Appendix J acceptance criterion of 0.60 L,.
In addition, the amendment: (1) makes editorial changes and deletes the exclusion of main steam isolation valves from Section 4.7.A.3.e.(1), and (2) revises the applicable Bases section.
l 2.0 EVALUATION l
The Millstone Unit 1 TS currently contain a requirement that any one penetration (except main steam isolation valves) not exceed a leakage of 5%
L,, (18.8 SCFH). L is the allowable operational leak rate and is derived from the maximum al, Towable test leak rate, L l
Surveillance Requirement 4.7.A.3.e.(1)(a) an$. Millstene Unit 1 TS 10 CFR Part 50, Appendix J establish an acceptance limit for all the leakage through these penetrations and valves of less than 0.60L. Appendix J does not establish acceptance limits for individual penetrations. The proposed change will revise the surveillance requirements for local leak rate testing which are included in TS Section 4.7.A, Containment Systems, to remove the 5% L,, limit.
Allowable leakage is established to ensure that radiation doses to the general public, in the event of an accident, stay within the limits of 10 CFR Part i
100. To ensure that requirement is met, an acceptable overall leakage value, L, was established based upon accident pressure, containment volume, fission product inventory and conservatism. The total contribution to leakage from penetrations is 60 percent or 0.60 L,.
This contribution is independent of the number of penetrations, their location, or their individual contribution to leakage and is established as the acceptance criterion in 10 CFR Part 50, Appendix J.
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I In the letter dated September 1, 1993, NNECO stated that eliminating the TS l
requirement that each penetration not exceed 5% L could preclude costly shutdownsorstartupdelayswhichmaybeinitiateEinordertodomaintenance which does not affect plant performance nor provide any substantial benefit to public health and safety.
In addition, NNECO stated that eliminating the overly restrictive criterion on leakage could reduce operational radiation doses by preventing unwarranted maintenance.
Removing the 5% L limit for p
individual penetrations will not affect the allowable leakage limit for Millstone Unit I and, therefore, won't decrease the safety of the general l
public. The NRC staff finds that removing the " administrative limit" will have no effect on the.equirement governing the combined Type B and C leakage acceptable.,) defined in 10 CFR Part 50, Appendix J and, therefore, is rates (0.60L As part of its September 1, 1993, letter, NNEC0 proposed to remove the currently allowed exclusion of main steam isolation valves from the combined leakage of 0.60L (that exclusion is not recognized in Appendix J). This change brings TS,4.7.A.3.e.(1) in line with Appendix J and, therefore, is acceptable.
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TS 4.7.A.3.e.(1)(a) contains several symbols which are inconsistent with 10
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CFR Part 50, Appendix J and ANSI 45.4 and 56.8.
As part of this proposed revision to the TS, NNECO made editorial changes to bring the TS into agreement with the terminology of Appendix J.
The NRC staff finds these 7
changes acceptable.
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i Based on the above, the NRC staff finds that the changes to the Millstone 1 TS are in line with the nomenclature and acceptance criteria established by 10 l
CFR Part 50, Appendix J and, therefore, are acceptable.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State I
l official was notified of the proposed issuance of the amendment. The State
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official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes surveillance requirements. The NRC staff has 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 Commission has previously issued a proposed finding that the amendment involves no significant hazards 1
consideration, and there has been no public comment on such finding (58 FR 50968). Accordingly, the imendment 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 assessment need be prepared in connection with the issuance of the amendment.
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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 ccmpliance 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:
J. Andersen Date:
November 10, 1993 l
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