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	{{#Wiki_filter:o _e Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonado Dr. East Welch, Minnesota 55089 April 20, 1995 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Revised Pages for License Amendment Request Dated January 9,1995 Incorporation of F* and L* Steam Generator Tube Repair Criteria Attached are revised pages for the January 9, 1995 License Amendment Request which proposed the incorporation of F* and L* Steam Cencrator Tube Repair Criteria into the Prairie Island Technical Specifications. The attached page revisions eliminate the L* requirements from the Technical Specification pages submitted with the original license amendment request. Bases page B.4.12-2 has also been revised to incorporate information provided to the NRC Staff in our March 15, 1995 response to the March 8, 1995 NRC request for additional information. A new Bases page, B.4.12 3, is also attached. That page was required because of the addition of the new information to page B.4.12-2. The proposed revisions do not change the conclusions of the original significant hazards evaluation.		{{#Wiki_filter:o
			_ e Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonado Dr. East Welch, Minnesota 55089 April 20, 1995 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn:
			Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Revised Pages for License Amendment Request Dated January 9,1995 Incorporation of F* and L* Steam Generator Tube Repair Criteria Attached are revised pages for the January 9, 1995 License Amendment Request which proposed the incorporation of F* and L* Steam Cencrator Tube Repair Criteria into the Prairie Island Technical Specifications. The attached page revisions eliminate the L* requirements from the Technical Specification pages submitted with the original license amendment request. Bases page B.4.12-2 has also been revised to incorporate information provided to the NRC Staff in our March 15, 1995 response to the March 8, 1995 NRC request for additional information. A new Bases page, B.4.12 3, is also attached. That page was required because of the addition of the new information to page B.4.12-2.
			The proposed revisions do not change the conclusions of the original significant hazards evaluation.
	The attachment contains the revised Technical Specification pages with the original proposed changes and all revisions incorporated.		The attachment contains the revised Technical Specification pages with the original proposed changes and all revisions incorporated.
	We have made no new Nuclear Regulatory Commission commitments in this letter.		We have made no new Nuclear Regulatory Commission commitments in this letter.
	Please contact Gene Eckholt (612-388 1121, Ext. 4663) if you have any questions related to the attached pages.		Please contact Gene Eckholt (612-388 1121, Ext. 4663) if you have any questions related to the attached pages.
	f&c Yu Mike Wadley f		f&c Yu f
	Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC State of Minnesota, Attn: Kris Sanda J E Silberg Attachments: Affidavit Revised Technical Specification Pages j 2/10111 9so4240sss 950420 i PDR ADOCK 05000282 P PDR}}		Mike Wadley Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC State of Minnesota, Attn: Kris Sanda J E Silberg Attachments: Affidavit Revised Technical Specification Pages j
			2/10111 9so4240sss 950420 i
			PDR ADOCK 05000282 P
			PDR}}

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2020-04-20T01:18:11Z

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{{Adams
| number = ML20082M809
| issue date = 04/20/1995
| title = Forwards Revised TS Pages Eliminating L* SG Tube Repair Criteria Submitted w/950109 Lar.Bases Page B.4.12-2 Also Revised to Incorporate Info Provided to NRC in Util 950315 Response to NRC 950308 RAI
| author name = Wadley M
| author affiliation = NORTHERN STATES POWER CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000282, 05000306
| license number =
| contact person =
| document report number = NUDOCS 9504240383
| package number = ML20082M815
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 1
}}

=Text=
{{#Wiki_filter:o _e Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonado Dr. East Welch, Minnesota 55089 April 20, 1995 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Revised Pages for License Amendment Request Dated January 9,1995 Incorporation of F* and L* Steam Generator Tube Repair Criteria Attached are revised pages for the January 9, 1995 License Amendment Request which proposed the incorporation of F* and L* Steam Cencrator Tube Repair Criteria into the Prairie Island Technical Specifications. The attached page revisions eliminate the L* requirements from the Technical Specification pages submitted with the original license amendment request. Bases page B.4.12-2 has also been revised to incorporate information provided to the NRC Staff in our March 15, 1995 response to the March 8, 1995 NRC request for additional information. A new Bases page, B.4.12 3, is also attached. That page was required because of the addition of the new information to page B.4.12-2. The proposed revisions do not change the conclusions of the original significant hazards evaluation.
The attachment contains the revised Technical Specification pages with the original proposed changes and all revisions incorporated.
We have made no new Nuclear Regulatory Commission commitments in this letter.
Please contact Gene Eckholt (612-388 1121, Ext. 4663) if you have any questions related to the attached pages.
f&c Yu Mike Wadley f
Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC State of Minnesota, Attn: Kris Sanda J E Silberg Attachments: Affidavit Revised Technical Specification Pages j 2/10111 9so4240sss 950420 i PDR ADOCK 05000282 P PDR}}

ML20082M809 - Revision history

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