ML19345C764: Difference between revisions

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NSP NORTHERN               STATES           POWER         COMPANY MIN N E APO L8 8. MIN N E SOTA 55409 December 2, 1980 Director of Nuclear Reactor Regulation U S Nup} ear Regulatory Commission gWashington, Dc3 20555 6         t.T       !
NSP NORTHERN STATES POWER COMPANY MIN N E APO L8 8. MIN N E SOTA 55409 December 2, 1980 Director of Nuclear Reactor Regulation U S Nup} ear Regulatory Commission gWashington, Dc3 20555 6
        #G         _        l' PRAIRIE ISLAND NUCLEAR GENERATING PLANT
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#G l' PRAIRIE ISLAND NUCLEAR GENERATING PLANT
                              ? Docket No. 50-282         License No. DPR-42
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50-306                     DPR-60
? Docket No. 50-282 License No. DPR-42
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[l         o Revision No. I to E         License Amendment Request dated May 6, 1980 m         f'         SI Actuation and Power Distribution Limits C
50-306 DPR-60
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Revision No. I to E
License Amendment Request dated May 6, 1980 m
f' SI Actuation and Power Distribution Limits C
Attached are three originals and 37 conformed copies of a revision to a previously submitted request for a change of Technical Specifications, Appendix A, of Operating Licneses DPR-42 and 60.
Attached are three originals and 37 conformed copies of a revision to a previously submitted request for a change of Technical Specifications, Appendix A, of Operating Licneses DPR-42 and 60.
This submittal proposes a revision to the changes in Section 3.10 of the Prairie Island Technical Specifications as a result of discussions with the NRC staf f.     Pages TS 3.10-1, 2, and 3 should le removed f rom the May 6, 1980 License Amendment Request and the attached pages in Exhibit B should be substituted.
This submittal proposes a revision to the changes in Section 3.10 of the Prairie Island Technical Specifications as a result of discussions with the NRC staf f.
Exhibit A describes the proposed changes, reasons for change, and safety evaluation. Exh ibit B contains the revised Appendix A pages.
Pages TS 3.10-1, 2, and 3 should le removed f rom the May 6, 1980 License Amendment Request and the attached pages in Exhibit B should be substituted.
                . O.
Exhibit A describes the proposed changes, reasons for change, and safety evaluation.
Exh ibit B contains the revised Appendix A pages.
. O.
L 0 Mayer, PE Manager of Nuclear Support Services LOM/TMP/jh cc: J G Keppler G Charnoff NRC Resident Inspector MPCA Attn: J W Ferman At tachment s 8012080 3/9}}
L 0 Mayer, PE Manager of Nuclear Support Services LOM/TMP/jh cc: J G Keppler G Charnoff NRC Resident Inspector MPCA Attn: J W Ferman At tachment s 8012080 3/9}}

Latest revision as of 09:57, 24 December 2024

Forwards Revision 1 to 800506 Application for Amend to Licenses DPR-42 & DPR-60,changing Tech Specs,Section 3.10 Re Safety Injection Actuation Power Distribution Limits
ML19345C764
Person / Time
Site: Prairie Island  
Issue date: 12/02/1980
From: Mayer L
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML19345C765 List:
References
NUDOCS 8012080319
Download: ML19345C764 (1)


Text

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0 0

NSP NORTHERN STATES POWER COMPANY MIN N E APO L8 8. MIN N E SOTA 55409 December 2, 1980 Director of Nuclear Reactor Regulation U S Nup} ear Regulatory Commission gWashington, Dc3 20555 6

t.T

  1. G l' PRAIRIE ISLAND NUCLEAR GENERATING PLANT
p. '

i

? Docket No. 50-282 License No. DPR-42

'2 0 '

50-306 DPR-60

,[:,

in

[l o

Revision No. I to E

License Amendment Request dated May 6, 1980 m

f' SI Actuation and Power Distribution Limits C

Attached are three originals and 37 conformed copies of a revision to a previously submitted request for a change of Technical Specifications, Appendix A, of Operating Licneses DPR-42 and 60.

This submittal proposes a revision to the changes in Section 3.10 of the Prairie Island Technical Specifications as a result of discussions with the NRC staf f.

Pages TS 3.10-1, 2, and 3 should le removed f rom the May 6, 1980 License Amendment Request and the attached pages in Exhibit B should be substituted.

Exhibit A describes the proposed changes, reasons for change, and safety evaluation.

Exh ibit B contains the revised Appendix A pages.

. O.

L 0 Mayer, PE Manager of Nuclear Support Services LOM/TMP/jh cc: J G Keppler G Charnoff NRC Resident Inspector MPCA Attn: J W Ferman At tachment s 8012080 3/9