ML20206U765

Forwards Rev 4 to NSPNAD-8102-A, Reload Safety Evaluation Methods for Application to Prairie Island Units, Including Original Acceptance Criterion for Condition IV Events Per 860530 SER

ML20206U765
Person / Time
Site:	Prairie Island
Issue date:	07/01/1986
From:	Musolf D NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20206U771	List: ML20206U765 ML20206U778
References
NUDOCS 8607110130
Download: ML20206U765 (2)

Text

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/W Northem States Power Company 414 Nicollet Mall Minneapohs. Minnesota 55401 Telephone (612) 330-5500 July 1, 1986 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GERRATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Submittal of Revised NSPNAD-8102 As requested by the May 30, 1986 Safety Eva?.uation Report, we are submitting five copies of Revision 4 to NSPNAD-8102. Revision 4 includes the original acceptance criterion for the condition IV events, as requested by the Safety Evaluation Report.

The May 30, 1986 Safety Evaluation Report stated: "We will require you follow the EPRI quality assurance procedure regarding the VIPRE-01 modifications." We feel this is unnecessary since we have our own procedures, previously reviewed by the NRC, which control the modification of Nuclear Analysis Department's codes used for safety analysis, it is our understanding that your concern is configuration control of the VIPRE-01 code. If significant changes are made to VIPRE-01 which have not been approved by the NRC generically, we will submit these changes for approval and identify the code with an NSP generated name, i.e. VPR XXXXX. We believe this will address your concerns with configuration control.

The May 30, 1986 Safety Evaluation Report requested that the DNBR limit of 1.17 for the WRB-1 carrelation be added to the acceptance criteria for each accident. The document was printed without this change being made due to an administrative oversight. Appendix F does clearly identify that the 1.17 limit is to be used for the WRB-1 correlation. This will be corrected the next time a revision to the document is submitted to the NRC Staff. This was discussed with Mr R Lobel of the NRC Staff.

This report has been declassified to a non-proprietary document. We no longer feel this information provides Northern States Power or Utility

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Northem States Power Company Dir, NRR July 1, 1986 Page 2 Associates International with a competitive advantage. We have observed similar methodology in the industry since the submittal of this document, April 19,1985.

M David Musolf Manager - Nuclear Support Services DMM/TMP/tp c: Regional Administrator-III, NRC (w/o attachment)

NRR Project Manager, NRC (w/o attachment)

Resident Inspector, NRC (w/o attachment)

G Charnoff (w/o attachment)

Attachments: 5 copies of Topical Report NSPNAD-8102-A Revision 4