ML20213F625

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Safety Evaluation Supporting Amend 103 to License DPR-46
ML20213F625
Person / Time
Site: Cooper Entergy icon.png
Issue date: 11/10/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20213F624 List:
References
TAC-62768, NUDOCS 8611140352
Download: ML20213F625 (2)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.103 TO FACILITY OPERATING LICENSE NO. DPR-46_

NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET N0. 50-298

1.0 INTRODUCTION

By letter dated September 5,1986, the Nebraska Public Power District (the licensee) requested an amendment to Facility Operating License No. DPR-46 for the Cooper Nuclear Station. The proposed amendment would change the Technical Specifications to reflect the removal of the reactor vessel head spray piping.

2.0 EVALUATION The amendment removes that portion of the reactor vessel head spray piping from the outboard containment isolation valve to the flange on the vessel head, and the spray nozzle within the vessel. The head spray piping is a subsystem of the residual heat removal (RHR) system.

It may be placed in operation during a normal shutdown and cooldown. When the reactor is cooling down, part of the flow from the RHR system may be diverted to the head spray nozzle to condense steam in the reactor upper head. This action will facilitate flooding of the vessel. This operational mode is not used, as operational experience has shown that the head spray is unnecessary. The head spray has no safety function and is not used in any accident sequence. No credit is given for use of the head spray to safely shut down the plant during an accident. Head spray operability is not a Technical Specifications requirement for any mode of operation.

The proposed changes to the Technical Specifications would (1) delete the operability and surveillance requirements for containment isolation valves RHR-MOV-32 and RHR-MOV-33, (2) delete the aforementioned valves from Table 3.7.1 which identifies the primary containment isolation valves, (3) delete the aforementioned valves from Table 3.7.4 which identifies the testable containment penetrations associated with the isolation valves, and (4) delete the head spray function from the listing of containment isolation groups in Table 3.2.A.

The head spray line containment penetration would remain installed as a spare and would continue to be subjected to periodic local leak rate testing as required by 10 CFR 50, Appendix J.

The staff has reviewed the proposed modification and associated Technical Specifications changes and concludes that they are acceptable.

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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 the amendment involves no significant hazards consideration and there has been no public comment on such finding.

Accordingly, the amendment meets 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 amendment.

4.0 CONCLUSION

We have 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, and (2) such activities will be conducted in compliance with the Com-mission's regulations and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

W. Long Dated: November 10, 1986 I