ML20117P760
| ML20117P760 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/20/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20117P759 | List: |
| References | |
| NUDOCS 9609250298 | |
| Download: ML20117P760 (4) | |
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ls UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066H001 o
.....g SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 203 TO FACILITY OPERATING LICENSE NO. DPR-65 NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY
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THE WESTERN MASSACHUSETTS ELECTRIC COMPANY MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 DOCKET NO. 50-336 l
1.0 INTRODUCTION
On September 12, 1995, the U.S. Nuclear Regulatory Commission (NRC) approved issuance of a revision to 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," which was subsequently published in the Federal Reaister on September 26, 1995, and became effective on October 26, 1995. The NRC added Option B " Performance-Based Requirements" to allow licensees to voluntarily replace the prescriptive testing requirements of 10 CFR Part 50, Appendix J, with testing requirements based on both overall leakage rate performance and the performance of individual components.
By letter dated January 16, 1996, the Northeast Nuclear Energy Company, et al.
(the licensee) submitted a request for changes to the Millstone Nuclear Pouer Station, Unit No. 2, Technical Specifications (TSs). The requested changes would change the TS Limiting Condition for Operation Section 3.6.1 and Surveillance Requirement Section 4.6.1, " Primary Containment," and the corresponding Bases, as well as, add a TS Administrative Controls Section j
6.19, " Containment Leakage Rate Testing Program."
The proposed changes would permit implementation of 10 CFR Part 50, Appendix i
J, Option B.
The licensee has established a " Containment Leakage Rate Test Program" and proposed adding this program to the TSs. The program references Regulatory Guide (RG) 1.163, " Performance-Based Containment Leak Test Program," dated September 1995, which specifies a. method acceptable to the NRC for complying with Option B.
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2.0 BACKGROUND
4 Compliance with Appendix J provides assurance that the primary containment, and those systems and components that penetrate the primary containment, do j
not exceed the allowable leakage rate values specified in the 'Ss and Bases.
l The allowable leakage rate is determined so that the leakage assumed in the safety analyses is not exceeded.
On February 4, 1992, the NRC published a notice in the Federal Reaister (57 FR 4166) discussing a planned initiative to eliminate requirements marginal to safety which impose a significant regulatory burden.
10 CFR Part 50, Appendix J, " Primary Containment Leakage Testing for Water-Cooled Power Reactor," was considered for this initiative and the staff undertook a study of possible changes to this regulation. The study examined the previous performance history of domestic containments and examined the effect on risk of a revision to the requirements of Appendix J.
The results of this study j
are reported in NUREG-1493, " Performance-Based Leak-Test Program."
Based on the results of this study, the staff developed a performance-based approach to containment leakage rate testing. On September 12, 1995, the NRC l
approved issuance of this revision to 10 CFR Part 50, Appendix J, which was d
subsequently published in the Federal Reaister on September 26, 1995, and became effective on October 26, 1995. The revision added Option B,
" Performance-Based Requirements," to Appendix J to allow licensees to voluntarily replace the prescriptive testing requirements of Appendix J with testing requirements based on both overall and individual component leakage rate performance.
RG 1.163, September 1995, " Performance-Based Containment Leak Test Program,"
was developed as a method acceptable to the NRC staff for implementing Option J.
This RG states that the Nuclear Energy Institute (NEI) document NEI 94-01, " Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," provides methods acceptable to the NRC staff for j
complying with Option B with four exceptions, which are described therein.
Option B requires that the RG or other implementation document used by a licensee to develop a performance-based leakage testing program must be included, by general reference, in the plant TSs.
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RG 1.163 specifies an extension in Type A test frequency from three approximately equally spaced tests in 10 years to at least one test in 10 years based upon two consecutive successful tests. Type B tests may be extended up to a maximum of 10 years based upon completion of two consecutive successful tests and Type C tests may be extended up to 5 years based on two consecutive successful tests.
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0 By letter dated October 20, 1995,-NEI proposed model TSs implementing Option B. 'After some discussion, the staff and NEI agreed on a set of model TSs, i
which were transmitted to NEI in a letter dated November 2, 1995.
These TSs i
are to serve as a model for licensees to develop plant specific TSs in preparing amendment. requests to implement Option B.
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In order for a licensee to determine the performance of each component, i
factors that are indicative of or affect performance, such as an administrative leakage-limit, must be established. The administrative limit is selected to be indicative of the potential onset of component degradation.
Although these limits are subject to NRC inspection to assure that they are selected in a reasonable' manner, they are not TS requirements.
Failure to j
meet an administrative limit requires the licensee to return to the minimum test interval for that component.
l Option B requires that the licensee maintain records to show that the criteria j
for Type A, B, and C tests have been met.
In addition, the licensee must i
maintain comparisons of the performance of the overall containment system and the individual components to show that the test intervals are adequate. These
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records are subject to NRC inspection.
3.0 EVALUATION k
The licensee's January 16, 1996, letter to the NRC proposed TS changes to permit the use of Option B of the revised 10 CFR Part 50, Appendix J.
i Option B permits a licensee to choose Type A; or Type B, and C; or Type A, B and C testing to be done on a performance basis.
The licensee has selected to perform Type A, B, and C testing on a performance basis. The proposed TS i
changes refer to RG 1.163, September 1995, " Performance-Based Containment Leak Test Program," which specifies a method acceptable to the NRC for complying with Option B.
This requires changes to TSs 4.6.1.1.d, 3.6.1.2.a-through
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3.6.1.2.c, 4.6.1.2.a through 4.6.1.2.h, 4.6.1.3.a through 4.6.1.3.c, 4.6.1.6.3, Bases 3/4.6.1.2, and the addition of a TS Section 6.19.
The proposed changes replace specific surveillance requirements related to primary containment leakage rate testing and the corresponding acceptance criteria and test methods with a requirement to perform the testing required by 10 CFR Part 50, Appendix J, Option B, as modified by approved exemptions, in accordance with the guidelines provided in RG 1.163, September 1995. The licensee chose to include its performance testing program in the TSs as an administrative program, which is consistent with the guidance in tne November 2, 1995, letter to NEI discussed above. The staff has reviewed the licensee's 1
proposed changes and finds them consistent with the requirements of 10 CFR i
Part 50, Appendix J, Option B, in that the changes include general reference in the TSs to RG 1.163 used by the licensee to develop the performance-based i
-leakage testing program for the Millstone Nuclear Power Station, Unit No. 2.
There are no current exemptions that would affect the adoption of Option B.
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. The staff has determined that the proposed TS changes, as detailed above, are in compliance with the requirements of 10 CFR Part 50, Appendix J, Option B, consistent with the guidance in RG 1.163 and the guidance provided in the November 2,1995, letter and, therefore are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment.
The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a l
facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The amendment also relates to changes in recordkeeping,. reporting, or administrative procedures or 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 consideration, and there has been no public comment on such finding (61 FR 5816 as corrected 61 FR 7825).
Accordingly, the amendment meets the eligibility criteria for categ'orical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared iri connection with the issuance of the amendment.
6.0 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: D. Mcdonald Date: September 20, 1996
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