ML20100K132

Forwards Application for Amend to Licenses DPR-42 & DPR-60, Incorporating Operability & Testing Requirements Associated W/Shunt Trip Attachment Mod Required by Generic Ltr 83-28. Fee Paid

ML20100K132
Person / Time
Site:	Prairie Island
Issue date:	04/05/1985
From:	Musolf D NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20100K135	List: ML20100K132 ML20100K153 ML20100K186
References
GL-83-28, NUDOCS 8504120205
Download: ML20100K132 (2)

Text

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Northem States Power Company 414 Nicollet Mall Minneapohs. Minnesota 554 . i Telephone (612) 330-5500 April 5,1985 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request dated April 5,1985 Shunt Trio Attachment Chansre Attached are three originals and 37 confermed copies of a request for change to Technical Specifications, Appendix A, of Operating Licenses DPR-42 and DPR-60. In accordance with 10 CFR Part 170, a check in the amount of

$150.00 is enclosed.

In response to Generic Letter 83-28, " Required Actions Based on Generic Implications of Salera ATWS Events", modifications are being made at Prairie Island to provide automatic reactor trip system actuation of the reactor trip breaker shunt trip attachments. The NRC Generic Safety Evaluation report for the Westinghouse Shunt Trip Modification, dated August 10, 1983, requested Technical Specification changes that provide for periodic testing of the shunt trip attachments and manual reactor trip circuits. In response to that request, this submittal proposes changes to Sections 3.5 and 4.1 of the Prairie Island Technical Specifications.

Preliminary technical specifications, incorporating the shunt trip and manual reactor trip . requirements requested by the August 10, 1983 Generic Safety Evaluation Report, were provided to the Commission in our December 10, 1984 letter. Those proposed technical specifications were reviewed by the Commission, and with some additions and minor wording changes, were found to be acceptable by the Commission in the Reactor Trip Breaker Automatic Shunt Trio Safety Evaluation Report, dated February 21, 1985. The proposed changes are the same as those found acceptable in the February 21, 1985 SER, with the exception of administrative changes required to fit the revisions into the existing Technical Specification text.

Exhibit A describes the proposed changes, reason for the changes and significant hazards evaluation. - Exhibit B contains the revised Technical Specification pages. .

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Dir. NRR Northem States Power Company April 5,1985 Page 2 The February 21, 1985 NRC Safety Evaluation Report also requested that NSP provide confirmation of the successful completion of seismic qualification of the shunt trip attachment. The Westinghouse Owners Group shunt trip attachment seismic qualification test program has been successfully completed.

The results of the test program are provided in Westinghouse Report WCAP-8687, Supp. 2-E62B, Revision 0, " Equipment Qualification Test Report - DB-50 Shunt Trip Attachment and Auto Panels (Environmental and Seismic Testing)",

December 1984. A copy of this report is available onsite for audit.

Please contact us if you have any questions concerning this License Amendment Request.

DO h.A,.

David Musolf Manager - Nuclear Sup t Services DMM/EFE c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC MPCA Attn: F W Ferman G Charnoff Attachment

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