ML20082C484
| ML20082C484 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/11/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082C483 | List: |
| References | |
| NUDOCS 9107190138 | |
| Download: ML20082C484 (2) | |
Text
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UNIT D STATES NUCLEAR REGULATORY COMMISSION y
L WASHINGTON, D.C. 20566 i
SAFETY EVAlllATION BY THE OFFICE OF' NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.158 TO FACILITY OPERATING LICENSE NO. DPR-66
_ AMENDMENT NO. 37 TO FACILITY OPERATING' LICENSE NO. NPF-73
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DUQUESNE-LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLl!MINATING COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION UNIT NOS. 1 AND 2 DOCKET NOS.-50-034 AND 50-412
1.0 INTRODUCTION
By. letter dated February 20, 1991, theDuquesne-LightCompany-(DLC)_ submitted
- a. request for changes to the Beaver Valley Power Station, Unit Nos. I and 2 Technical-Specifications-(TS). The-requested change would-modify the A'ppendix 1
'A Technical'SpecificationsLfor determining-containment leakage.
S the amendments:would modify surveillance requirement (TS 4.6.1.2) pecifically, to delete the reference to ANSI-N45.4-1972.
2Property "ANSI code" (as page type) with input value "ANSI-N45.4-1972.</br></br>2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..0- BACKGROUND-The Api.endix A-Technical Specification:4.6.1.2 requires that_the containment-L leakage rate be-determined by criteria specified in Appendix.J of 10'CFR Part 50 L
using;the methods and provisions of ANSI N45.4-1972. On November 15, 1988,.
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the Commission published in the Federal Register-(53 FR 45891) a final rule which provided for an alternative method for containment. leakage rate testing.
L This rule explicitly permits the use_of the Mass _ Point statistical data-analysis method for calculating containment leakage rates (found in ANSI /ANS
-56.8-1987 " Containment System _ Leakage Testing Requirements").
The present wording of Surveillance Requirement 4.6.1.2.only: refers to ANSI N45.4-1972 and does not allow the use of the improved alternate method, Hass Point L
--analysis,-_in' calculating containment leakage rates. 'By deleting the specific reference to-ANSI N45.4-1972 from the Surveillance Requirement 4.6.1.2, and' p
idirecting that containment leakage rates be determined in accordance with-Appendix'J.of 10 CFR Part 50, either procedure can be implemented.
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.. 3.0 EVALUATION The deletion of the reference to ANSI M45.4-1972 fron Surveillance Requirement 4.6.1.2 will not affect the ability of the Integrated Leak Rate Test to determine the actual containment leakage rate. The leakage rate will be determined in accordance with 10 CFR Part 50 Appendix J which references ANSI N45.4-1972 and the new alternate method ANSI /ANS 56.8-1987 as approved methods. This allows DLC to follow the Total Time and Point to Point analysis methods recognized by ANSI N45.4-1972 or the new improved Mass Point analysis method. This Mass Point method was incorporated in a newer ANSI standard, ANSI /ANS 56.8 - 1981 (revision 1987), " Containment System Leakage Testirg Requirement" and has been accepted by the NRC staff as an improveo alternate method of calculating containment leakage rates. The utilization of the Mass Point analysis provides at least the same degree of accuracy as the Total Time and Point to Point methods.
Therefore the determination that the actual leakage rates from containment are less than or equal to that assumed in the limiting containment DBA analysis will continue to be performed. The medified surveillance requirement will continue to ensure that the leak tightness of the containment is maintained to prevent the uncontrolled release of radioactivity to the environment. Based on the above, the staff concludes that the proposed change to the Technical Specifications is acceptable.
4.0 STATE CONSULTATION
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.
5.0 EfGIRONMEig g CONSIDERATION The amendments involve a change to a surveillance requirement. 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 hnards consideration, and there has been no public comment on such fir <.iing (50 FR 20035). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 5122(b) no environmental impact statement or environmental assesment 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: James W. Andersen Date: July 11, 1991
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