ML19210E266: Difference between revisions

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{{#Wiki_filter:MSP NORTHERN             STATES             POWER             COMPANY M I N N E A PO LI S. M I N N E S OTA 55401 November 27, 1979 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282           License No. DPR-22 50-306                         DPR-60 Possible Rod Drop Accident Analysis Non-Conservatism A possible non-conservatism in the rod drop accident analysis for certain Westinghouse designed nuclear plants was discussed at a meeting of Westinghouse, utility licensee, and NRC representatives on November 19, 1979. An interim procedural solution was adopted at this meeting.
{{#Wiki_filter:MSP NORTHERN STATES POWER COMPANY M I N N E A PO LI S. M I N N E S OTA 55401 November 27, 1979 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-22 50-306 DPR-60 Possible Rod Drop Accident Analysis Non-Conservatism A possible non-conservatism in the rod drop accident analysis for certain Westinghouse designed nuclear plants was discussed at a
meeting of Westinghouse, utility licensee, and NRC representatives on November 19, 1979. An interim procedural solution was adopted at this meeting.
On November 20, 1979, the NRC Project Manager for Prairie Island re-quested verbal and written confirmation of implementation of the prescribed procedure. This letter is to confirm that the interim procedure for Prairie Island has been prepared, reviewed, approved and placed in effect. The procedure will remain in ef fect until further notice.
On November 20, 1979, the NRC Project Manager for Prairie Island re-quested verbal and written confirmation of implementation of the prescribed procedure. This letter is to confirm that the interim procedure for Prairie Island has been prepared, reviewed, approved and placed in effect. The procedure will remain in ef fect until further notice.
L 0 Mayer, PE Manager of Nuclear Support Services LOM/ak cc: J G Keppler G Charnoff 1468 320 2OI 7912010}}
L 0 Mayer, PE Manager of Nuclear Support Services LOM/ak cc: J G Keppler G Charnoff 1468 320 2OI 7912010}}

Latest revision as of 20:50, 4 January 2025

Confirms Implementation of Interim Procedural Solution Adopted at 791119 Meeting W/Nrc,Westinghouse & Util Re Possible Rod Drop Accident Analysis for Certain Westinghouse Designed Plants
ML19210E266
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 11/27/1979
From: Mayer L
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 7912040201
Download: ML19210E266 (1)


Text

MSP NORTHERN STATES POWER COMPANY M I N N E A PO LI S. M I N N E S OTA 55401 November 27, 1979 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-22 50-306 DPR-60 Possible Rod Drop Accident Analysis Non-Conservatism A possible non-conservatism in the rod drop accident analysis for certain Westinghouse designed nuclear plants was discussed at a

meeting of Westinghouse, utility licensee, and NRC representatives on November 19, 1979. An interim procedural solution was adopted at this meeting.

On November 20, 1979, the NRC Project Manager for Prairie Island re-quested verbal and written confirmation of implementation of the prescribed procedure. This letter is to confirm that the interim procedure for Prairie Island has been prepared, reviewed, approved and placed in effect. The procedure will remain in ef fect until further notice.

L 0 Mayer, PE Manager of Nuclear Support Services LOM/ak cc: J G Keppler G Charnoff 1468 320 2OI 7912010