ML20129C549
| ML20129C549 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/26/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20129C545 | List: |
| References | |
| GL-83-28, NUDOCS 8507160240 | |
| Download: ML20129C549 (2) | |
Text
fucoqk UNITED STATES
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 75 AND 68 TO FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-282 AND 50-306 Introduction By letter dated April 5,1985, Northern States Power Company (NSP), the licensee, requested amendments to Facility Operating License Nos. DPR-42 and DPR-60 for the Prairk Island Nuclear Generating Plant Unit Nos. I and 2 (PINGP). The amendments would change the technical specifications by including the operability and the surveillance requirements associated with the automatic actuation of the shunt trip attachments and the manual reactor trip circuit. Specifically, additional requirements would be placed in sections 3.5 and 4.1 of the Prairie Island Technical Specifications. These additional requirements would restrict plant operation resulting from the malfunctions of these electrical components and would provide periodic testing.to assure adeq' ate operability of the reactor u
scram mechanism when called for to perform the intended safety function.
Evaluation In our Generic Letter 83-28 (item 4.3) dated July 8, 1983, actions were identi-fied requiring all reactor licensees and applicants to respond to the generic implications of the Salem ATWS events. An NRC generic safety evaluation issued by letter dated August 10, 1983, requested model technical specification changes that provide operability and periodic testing require-ments for the automatic actuation of the shunt trip and the manual reactor trip circuits. By letters dated July 6, 1984 and December 10, 1984, the licensee responded to our requests by submitting model technical specifications that would be applicable to the Prairie Island Nuclear Generating Plant Unit Nos.
I and 2.
By letter dated February 21, 1985, the NRC issued a safety evaluation dealing with the design modifications and the model technical specifications for the automatic actuation of the shunt trip and the manual reactor trip circuit.
Our evaluation concludes that the proposed modifications are acceptable contin-gent upon confirming the seismic qualifications of the modified design and that the model technical specifications as modified and appearing in our safety evaluation are also found acceptable. As discussed in our February 21, 1985 safety evaluation, changes to the model technical specifications were discussed with and agreed to by the licensee. The proposed changes associated with this 0507160240 850626 ADOCK0500g2 DR
4 amendment request (by letter dated April 5,1985) are essentially the same as those previously approved by our safety evaluation issued on February 21, 1985 except for minor administrative changes. We have reviewed these minor administra-tive changes and agree with the licensee that they are necessary in order to fit the changes into the existing text of the specifications and in no way do they change the previously approved requirements appearing in the model technical specifications. On this basis, the proposed technical specifications related to the automatic actuation of the shunt trip and the manual reactor trip circuit are found acceptable.
ENVIRONMENTAL CONSIDERATION These amendments involve a change in the 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 amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may.be Teleased offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(9).
Pursuant to 10 CFR 551.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
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 i
be conducted in compliance with the Commission's regulations, and the issuance of the amendments will not be inimical to the common defense and security or to the health 6nd safety of the public.
Date: June 26, 1985 l
Principal Contributor:
D. C. Di Ianni l
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