ML20117N969

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Safety Evaluation Supporting Amends 214 & 219 to Licenses DPR-44 & DPR-56,respectively
ML20117N969
Person / Time
Site: Peach Bottom  
Issue date: 06/18/1996
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20117N967 List:
References
NUDOCS 9606250111
Download: ML20117N969 (4)


Text

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j NUCLEAR REGULATORY COMMISSION I e WASHINGTON, D.C. 20bM001 jf1FETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0S.214 AND 219 TO FACILITY OPERATING LICENSE NOS. DPR-44 and DPR-56 PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION. UNIT NOS. 2 AND 3 DOCKET NOS. 50-277 AND 50-278

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 i

based on both overall leakage rate performance and the performance of individual components.

By application dated February 15, 1996, PECO Energy Company, (PEC0, the licensee) requested changes to the Technical Specification (TS) for Peach Bottom Atomic Power Station, Units 2 and 3, (PBAPS).

The proposed changes would permit implementation of 10 CFR Part 50, Appendix J, Option B.

The licensee has established a " Containment Leakage Rate Testing Program" and proposed adding this' program to the TS.

The program references Regulatory Guide 1.163, September 1995, " Performance-Based Containment Leak-Test Program" which specifies a method acceptable to the NRC for complying with Option B.

Proposed TS page 5.0-17a of the February 15, 1996 application was renumbered as page 5.0-18 before issuing this amendment and existing TS pages 5.0-18 through 5.0-25 are being reissued as pages 5.0-19 through 5.0-26.

2.0 BACKGROUND

Compliance with 10 CFR Part 50, Appendix J, provides assurance that the primary containment, including those systems and components which penetrate tie primary containment, do not exceed the allowable leakage rate specified in the TS and bases.

The allowable leakage rate is determined so that the leakage assumed in the safety analyses is not exceeded.

9606250111 960618 PDR ADOCK 05000277 P

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i e On February 4,1992, the NRC published a notice in the Federal Reaister (57 FR 4166) discussing a planned initiative to begin eliminating requirements marginal to safety which impose a significant regulatory burden. Appendix J of 10 CFR Part 50, " Primary Containment Leakage Testing for Water-cooled Power Reactors" was considered for this initiative and the staff undertook a study of possible changes to this regulation. 1he study examined the previous performance history of domestic containments and examined the effect on risk 3

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 1

appreved issuance of this revision to 10 CFR Part 50, Appendix J, which was 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 i

testing requirements based on both overall and individual component leakage i

rate performance.

Regulatory Guide 1.163, September 1995, " Performance-Based Containment Leak-Test Program", was developed as a method acceptable to the NRC staff for implementing Option B.

This regulatory guide states that the Nuclear Energy Institute (NEI) guidance 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 complying with Option B with four exceptions which are described therein.

j Option B requires that the regulatory guide or other implementation document used by a licensee to develop a performance-based leakage rate testing program

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must be included, by general reference, in the plant TS. The licensee has 1

referenced Regulatory Guide 1.163 in the PBAPS TS.

Regulatory Guide 1.163 specifies an extension in Type A test frequency to at least one test in 10 years based upon two consecutive successful tests.

Type B tests may_be extended up to a maximum interval 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.

By letter dated October 20, 1995, NEI proposed TS to implement Option B.

After some discussion, the staff and NEI agreed on final TS which were transmitted to NEI in a letter from C. Grimes, NRC, to D. Modeen, NEI, dated November 2, 1995. These TS are to serve as a model for licensees to develop plant specific TS in preparing amendment requests to implement Option B.

For a licensee to determine the performance of each component, 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 i

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l-l-limits are subject to NRC inspection to assure that they are selected in a reasonable manner, they are not TS requirements. Failure to meet an administrative limit requires the licensee to return to the minimum value of l

the test interval.

Option B requires that the licensee maintain records to show that the criteria for Type A, B and C tests have beca met.

In addition, the licensee must

-maintain comparisons of the performance of the'overall containment system and the individual components to show that the test intervals are adequate. These records are subject to NRC inspection.

3.0 EVALUATION The licensee's February 15,1996,. letter to the NRC proposes to establish a

" Containment Leakage Rate Testing Program" and proposes to add this program to the TS. The program references Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program" which specifies a method acceptable to the NRC for complying with Option B.

This requires a change to:

(1) Existing TS 1.1 " Definitions" - deletion of the definition of L, (2) Existing TS 3.6.1.1, " Primary Containment,"

TS 3.6.1.2, " Primary Containment Air Lock,"

TS'3.6.1.3, "PCIVs,"

- deletion of specific acceptance criteria and surveillance frequency and insertion of reference to " Primary Containment Leakage Rate Testing Program" (3) Existing TS 5.5, Programs and Manuals" - addition of new TS 5.5.12, defining the " Primary Containment Leakage Rate Testing Program" Corresponding bases were also modified.

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 elected to perform Type A, B and C testing on a performance basis.

i The TS changes proposed by the licensee are in compliance _with the requirements of 10 CFR Part S0, Appendix J, Option B and consistent with the guidance of Regulatory Guide 1.163, September 1995, and the' generic-TS of the November 2,1995, letter and are, therefore, acceptable to the staff.

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4.0 STATE CONSULTATION

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In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.

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5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change the surveillance requirements.

The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (61 FR 13531). Accordingly, the amendments meet 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 amendments.

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 amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

J. Shea Date: June 18, 1996 i

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