ML20137Z394
| ML20137Z394 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/04/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137Z373 | List: |
| References | |
| NUDOCS 8603130031 | |
| Download: ML20137Z394 (3) | |
Text
jo UNITED STATES g
8 NUCLEAR RECULATORY COMMISSION o
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING Al1ENDMENT NO.13 TO OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO.
50-483
1.0 INTRODUCTION
By letter dated November 15, 1985, Union Electric Company (the licensee) requested revision to Technical Specifications 4.6.1.1.C. 3.6.1.2.a.
3.6.1.2.b. 4.6.1.2.a. 4.6.1.2.d. 3.6.1.3.b 4.6.1.3.b and 4.6.1.7 to indicate that containment leak rate testing (Type A, B, C tests per 10 CFR 50, Appendix J) is to be perfonned at the calculated peak contain-ment internal pressure (Pa) of 48.1 psig This value for Pa is a result of containment pressure / temperature lal ses in the Callaway FSAR (refer to Section 6.2.1.4.3.3 and Table 6.2.1-2.
2.0 EVALUATION The safety analyses contained in the Callaway FSAR were carried out utilizing a peak calculated containment pressure of 48.1 psig which was the result of the accident analyses presented in FSAR Section 6.2.1.4.3.3 and Table 6.2.1-2.
The value of Pa that was specified in the Callaway Technical Specifi-cations (NUREG-1085, Revision 1) was 48.0 psig which is slightly lower than the analyzed value of 48.1 psig.
The proposed technical specification changes from 48.0 to 48.1 psig would affect the following technical specifications:
1.
4.6.1.1.c 2.
3.6.1.2.a 3.
3.6.1.2.b 4
4.6.1.2.a 5.
4.6.1.2.d 6.
3.6.1.3.b 7.
4.6.1.3.b 8.
4.6.1.7.2 The staff's review of the above proposed changes indicates that the slight change of calculated peak containment pressure is technically inconsequential and has little effect on the past and future containment leak rate test results, and is, therefore, acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in surveillance requirements.
The staff has determined that the amendment involves no significant change in the types or significant increase in the amounts of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has pre-viously issued a proposed finding that this amendment involves no signif-icant hazards consideration and there has been no public coment on such categorical exclusion set forth in 10 CFR 51.22(c)gibility criteria for finding. Accordingly, this amendment meet the eli (9).
Pursuant to 10 CFR 51.22(b), no environmental impa::t statement or environ-mental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The Comission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register (51 FR 3719) on January 29, 1986, and consulted with the state of Missouri. No public coments were received, and the state of Missouri did not have any coments.
We have concluded, based on the considerations discussed above, that:
will not be endangered by operation in the proposed manner, and (2) public (1) there is reasonable assurance that the health and safety of the such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public, principal Contributors:
Y. S. Huang, PAEB P. O'Connor, PWR#4 Da ted: Kirch 4,1986
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MDuncan TAlexion P0'Connor OELD LHannon 4
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