ML20071F438
| ML20071F438 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 06/30/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071F436 | List: |
| References | |
| NUDOCS 9407080221 | |
| Download: ML20071F438 (3) | |
Text
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j UNITED STATES NUCLEAR REGULATORY COMMISSION 4 '
W A SC N G T O N. D C. ;'05 54-0001 SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 62 TO FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO 62 TO FAClllTY OPERATING LICENSE NO. NPF-66, AMENDMENT NO. 52 TO FACILITY OPERATING LICENSE N0. NPF-72, AND AMENDMENT NO. 52 TO FAClllTY OPERATING LICENSE NO. NPF-77 COMMONWEALTH EDISON COMPANY BYRON STATION. UNIT NOS. 1 AND 2, BRAIDWOOD STATION. UNIT NOS. 1 AND 2 DOCKET NOS STN 50-454. STN 50-455. STN 50-456 AND STN 50-457
1.0 INTRODUCTION
By submittal dated March 7,1994, as superseded by a submittal dated March 24, 1994, the Commonwealth Edison Company (Ceco or the licensee) submitted a request for an amendment to the operating licenses of Byron Nuclear Station, Units 1 and 2, and Braidwood Nuclear Station, Units 1 and 2.
The proposed amendments would revise Byron and Braidwood Technical Specification (TS) 4.6.1.2 by deleting the schedular requirements for Type A containment integrated leakage rate (ILRT) tests to be performed at 40 i 10 month intervals.
The changed TS would instead reference Type A testing in accordance with Appendix J to 10 CFR 50.
The proposed amendments would also include a minor editorial change.
2.0 BACKGROUND
The TS for Byrr-and Braidwood currently require that a set of three Type A ILRTs be perf' ad specifically at 40 i 10 month intervals during each 10-year service per us, with the third test of each set to be performed during the shutdown for the 10-year plant inservice inspection. Appendix J to 10 CFR 50 requires that a set of three Type A tests be conducted at approximately equal intervals during the 10-year service period, and also requires that the performance of the third test coincioe with the shutdown for the 10-year plant inservice inspection.
While the testing frequency requirements in the Byron and Braidwood TSs essentially duplicate those in Appendix J to 10 CFR 50, the TS specifically require that testing be done at 40 i 10 month intervals. The licensee sta+as that for Byron, Units 1 and 2, the current 18 month fuel cycle would make it difficult to conduct the third test within the required 40 i 10 month interval and still have it coincide with the 10-year inservice inpsection outages.
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. 2-Ceco further states that the time intervals for testing are currently met by Braidwood, Units 1 and 2, but requests changes to maintain consistency with the Byron TS and to eliminate any future need for a TS change as a result of revisions to Appendix J.
Therefore, the licenses proposes to revise the TS by deleting the detailed surveillance schedule for Type A tests and instead reference the performance of Type A testing in accordance with Appendix J to 10 CFR 50.
3.0 TECHNICAL SPECIFICATION CHANGES TS Surveilance Requirement 4.6.1.2.a would be revised by removing the requirement that Type A tests be conducted at 40 i 10 month intervals with the third test being conducted during the shutdown for the 10-year inservice inspection.
The revised Surveillance Requirement would read as follows:
" Type A (0verall Integrated Containment Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by app oved exemptions."
In addition iS Surveillance Requirement 4.6.1.2.b would be modified by deleting the reference to the testing schedule referenced in the unrevised version of Surveillance Requirement 4.6.1.2.a.
This change is editorial in nature.
4.0 EVALUATION Satisfactory leakage results are a requirement for the establishment of containment operability.
Neither the general frequency nor the required number of Type A tests would be changed ty the proposed revisions.
Also, the maximum allowable leakage rate at the calculated peak containment pressure would not be changed.
Only the detailed 40 10 month test interval would be changed to provide more fl.exibility.
Tyse A, B, and C tests would continue to be performed in accordance with Appendix J to 10 CFR 50.
Type A test acceptance criteria weald not be changed and combined leakage of penetrations subject to Type B ar.a Type C tests would be maintained within the required limits.
Also, the proposed changes do not impact the design basis of the containment and would not change the response of containment during a design basis accident.
Finally, the testing method, acceptance criteria, and the Bases to the TS are not changed by the proposed revisions to the TS.
Therefore, based on all of the above, the staff finds the proposed changes to be acceptable.
An administrative -hange to TS Section 3.6.1.2a(2) for Braidwood, Unit 1, was made to include the limiting value for the integrated leakage rate for Braidwood, Unit 2.
Tha Unit 2 value (0.07% by weight of air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) had been included in the Unit 2 TS at the time of licensing.
Because Braidwood has common TSs, the values for both units should be shown in Section 3. 6.. l. 2 a ( 2 ).
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5.0 STATE CONSULTATION
in accordance with thi :ommission's regulations, the Illinois State official was notified of the proposed issuance of the amendments.
The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
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 (59 FR 22002). 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 anvironmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
7.0 CONCLUSION
The ComT.ission has concluded, based on the considerations discussed above s 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) tne 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:
H. Dawson if Date:
June 30, 1994
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