ML20235B770
| ML20235B770 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/09/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235B769 | List: |
| References | |
| NUDOCS 8709240223 | |
| Download: ML20235B770 (2) | |
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UNITED sT ATES
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WASHING T ON. D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
. SUPPORTING' AMENDMENT N0.110 TO FACILITY OPERATING LICENSE NO. OPR-46 NEBRASKA-PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
1.0 INTRODUCTION
By letters-dated July 9, 1987 and August 28, 1987 (Change No. 42) the Nebraska Public Power District (the-licensee) requested an amendment to Facility Operating License No. DPR-46 for the Cooper Nuclear Station (CNS).
The proposed amendment would change the Appendix A Technical Specifications to include local leak rate test acceptance criteria for airlock doors.
- 2. 0 DISCUSSION AND EVALUATION l
The 10 CFR 50 Appendix J Section III.D.2.b(iv) requires that "the-acceptance criteria for air lock testing shall be stated :in the Technical Specifications." The CNS Technical Specifications presently lack such I
a statement of the test acceptance criteria.
The licensee has requested l
that Section 4.7.A.2.F of the Technical Specifications be revised to include the.following woros:
"The maximum allowable leakage at a test pressure of 58 psig is I
I 12.0 scfh.
Leakage measured at test pressure.less than 58 psig is
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adjusted to the equivalent value at 58 psig."
The allowable leakage rate is based on the staff's position that airlock door leakage' not exceed 0.05 La at Pa.
Measurement of leakage l
at less than Pa with adjustment of results to Pa, is consistent with a staff recommendation contained in a Safety Evaluation issued with a l
test interval Exemption on September 3, 1982 and is conservative.
The proposed amendment is therefore acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
S This amendment changes a. requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The 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.this amendment involves no significant hazards-consideration and there has been no public comment on such finding.
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l Accordingly, this amendment meets the eligibility criteria for.categor-ical exclusion set.forth in.10 CFR 51.22(c)(9) and pursuant to 10 CFR:
51,22(b) no environmental.. impact' statement or assessment' need be..
prepared in connection with,the issuance'of this. amendment, j
1 4,O CONCLUSION-1 We have concluded, based-on the co'nsiderations' discussed above,- that:
(1) there is reasonaole assurance that the health'and safety of:the public will not be endangered by operation in the proposed manner,. and (2) such activities'will be conducted in. compliance with the Com-mission's. regulations and the_ issuance of the amendment will not be t
' inimical to the common defense'and security or. to the health and safety of'the public.
l Principal Contributor:
W. Long Dated: September 9,1987 i
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