Letter Sequence Other |
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Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: BSEP-96-0428, Provides Comments on Resolution of Spent Fuel Storage Pool Safety Issues, HL-5262, Forwards Comments to 960917 NRC Ltr Re Resolution of Spent Fuel Pool Safety Issues, ML17158B810, ML17187A502, ML17292A353, ML17312A997, ML20116E584, ML20116F061, ML20129D921, ML20129D965, ML20129F423, ML20132G883, ML20134C905, ML20134M234, ML20134M563
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MONTHYEARML17292A3531996-06-28028 June 1996 Requests Confirmation of Commitment Re Modifying Plant Refueling Procedures to Document Fuel Movement Delay Time Assumptions in Spent Fuel Pool Analysis Project stage: Other ML17187A5021996-06-28028 June 1996 Discusses Survey Conducted on 960514 of Sf Practices,Sfcs Design & Current Licensing Basis for Plant Units 2 & 3. Confirmation Ltr Requested within 30 Days of Receipt of Dtd Ltr Re Projected Completion Dates for Each Stated Action Project stage: Other ML20116F0611996-07-25025 July 1996 Responds to , Spent Fuel Survey Commitments for Byron Station,Units 1 & 2, Informing NRC That Clarification of Description of Refueling Activities Including Full Core Temporary Offload Will Be Provided by Dec 1996 Project stage: Other ML20116E5841996-08-0101 August 1996 Responds to Re Spent Fuel Survey Commitments for Waterford Steam Electric Station,Unit 3 Project stage: Other ML18012A3591996-09-17017 September 1996 Discusses & Forwards Rept of Staff Review of Sfsp Safety Issues.Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection.Review of Rept Requested for Plant Applicability Project stage: Approval ML16343A4441996-09-19019 September 1996 Forwards & Discusses Rept of Review of Sfsp Safety Issues. Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection. Review of Rept Requested for Applicability to Facility Project stage: Approval ML18152A0651996-09-19019 September 1996 Forwards & Discusses Rept of Review of Sfsp Safety Issues. Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection. Design Features Affecting SFP Reliability Also Discussed Project stage: Approval ML15238A3011996-09-20020 September 1996 Forwards & Discusses Rept of Review of Sfsp Safety Issues. Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection. Design Features That Affect SFP Reliability Also Discussed Project stage: Approval ML20129D2741996-09-20020 September 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues.Staff Intends to Conduct plant-specific Regulatory Analyses to Evaluate Potential Safety Enhancement Backfits,Per 10CFR50.109(a)(3) Project stage: Approval ML20129D3351996-09-24024 September 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues.Staff Intends to Conduct plant-specific Regulatory Analyses to Evaluate Potential Safety Enhancement Backfits,Per 10CFR50.109(a)(3) Project stage: Approval ML20129D3051996-09-24024 September 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues.Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20129F6741996-09-24024 September 1996 Informs That Staff Has Completed Detailed Review of Sfsp Safety Issues & Forwards Results for Review Project stage: Approval ML20129F4231996-09-25025 September 1996 Forwards 960726 Memo to Commission from J Taylor Re Resolution of Spent Fuel Storage Pool Action Plan Issues. Concludes That Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Other ML20129D9761996-09-26026 September 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues.Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML17333A5781996-09-26026 September 1996 Discusses Resolution of Spent Fuel Storage Pool Safety Issue & Issuance of Final Staff Rept & Notification of Staff Plans to Perform plant-specific,safety Enhancement Backfit Analysis Project stage: Approval ML17292A5181996-09-26026 September 1996 Informs That Staff Has Completed Detailed Review of Spsp Safety Issues & Forwards Results for Review Project stage: Approval ML17187A5981996-09-26026 September 1996 Discusses Completion of Detailed Review of Spent Fuel Storage Pool Safety Issues.Staff Concludes That Existing Structures,Systems & Components Related to Storage of Irradiated Fuel Provide Adequate Protection Project stage: Approval ML18065A9281996-09-26026 September 1996 Forwards & Discusses Rept of Review of Sfsp Safety Issues. Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection. Review of Rept Requested for Applicability to Plant Project stage: Approval ML20129E1121996-09-26026 September 1996 Discusses Detailed Review of Spent Fuel Storage Pool Safety Issues.Results of Review Encl Project stage: Approval ML20129D9651996-09-26026 September 1996 Forwards Rept Re Resolution of Spent Fuel Storage Pool Safety Issues.Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Other ML20129D9211996-09-26026 September 1996 Forwards NRC Rept on Resolution of Spent Fuel Storage Pool Safety Issues.Concludes That Exisiting Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Other ML18102A4261996-09-27027 September 1996 Discusses Completed Detailed Review of Spent Fuel Storage Pool Safety Issues.Comments on Accuracy of Staff Understanding of Plant Design,Safety Significant of Design Features,Cost of Potential Mods Be Submitted by 961115 Project stage: Approval ML20129E5361996-09-27027 September 1996 Forwards Results of Detailed Review of Spent Fuel Storage Pool Safety Issues.Rept Should Be Reviewed for Applicability to Facility & Actions Considered Re Design of Spent Fuel Pool Decay Heat Removal Sys.No Response Required Project stage: Approval ML17158B8101996-09-27027 September 1996 Forwards Results of Detailed Review Re Spent Fuel Storage Pool Safety Issues.Rept Should Be Reviewed for Applicability to Facility & Actions Considered Re Design of Spent Fuel Pool Decay Heat Removal Sys.No Response Required Project stage: Other ML20128H4541996-10-0101 October 1996 Discusses Completion of Detailed Review of Sfsp Safety Issues.Staff Concludes That Existing Structures,Sys & Components Related to Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20128Q3811996-10-0303 October 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues Documented in Encl Rept to Commission. Structure,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20128N1961996-10-0404 October 1996 Requests Review of Resolution of Spent Fuel Storage Pool Safety Issues:Issuance of Final Rept,Vermont Yankee Power Station.Rept to Commission Encl Project stage: Approval ML20134C9051996-10-0808 October 1996 Forwards Final Rept Re Spent Fuel Storage Pool Safety Issues Project stage: Other ML17312A9971996-10-0909 October 1996 Forwards Memo to Commission Re Resolution of SFP Safety Issues,For Info Project stage: Other ML20128M7171996-10-0909 October 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues Documented in Encl Rept to Commission. Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML14178A9671996-10-10010 October 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues Documented in Encl Rept to Commission. Structure,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20129C0531996-10-17017 October 1996 Discusses Review of Rept of Sfsp Safety Issues,Concluding That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection.Staff to Conduct plant-specific Safety Enchancement Backfit Analyses Project stage: Approval ML20129D1911996-10-22022 October 1996 Discusses Completion of Detailed Review of Sfsp Safety Issues.Staff Concludes That Existing Structures,Sys & Components Related to Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20129H3761996-10-30030 October 1996 Forwards Results of Staff Review of Spent Fuel Storage Issues.Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety. W/O Rept to Commission Project stage: Approval ML20134J7151996-11-13013 November 1996 Forwards Results of Staff Review of Resolution of Spent Fuel Storage Pool Safety Issues Project stage: Approval ML20134M2341996-11-13013 November 1996 Responds to NRC Re Resolution of Spent Fuel Pool Safety Issues & Issuance of Final Staff Rept & Notification of Plans to Perform plant-specific,safety-enhancement Backfit Analyses Project stage: Other ML20134M5631996-11-14014 November 1996 Provides Comments on Rept on Spent Fuel Storage Pool Issues & Accompanying NRC Project stage: Other HL-5262, Forwards Comments to 960917 NRC Ltr Re Resolution of Spent Fuel Pool Safety Issues1996-11-14014 November 1996 Forwards Comments to 960917 NRC Ltr Re Resolution of Spent Fuel Pool Safety Issues Project stage: Other BSEP-96-0428, Provides Comments on Resolution of Spent Fuel Storage Pool Safety Issues1996-11-15015 November 1996 Provides Comments on Resolution of Spent Fuel Storage Pool Safety Issues Project stage: Other ML20132G8831996-12-20020 December 1996 Submits Comments on NRC Rept Re Resolution of Spent Fuel Storage Pool Safety Issues:Issuance of Final Staff Rept & Notification of Staff Plans to Perform Plant-Specific,Safety Enhancement Backfit Analyses,Dbnps Project stage: Other 1996-11-15
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Text
Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch. Minnesota 55089 t
November 14,1996 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR " dRATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Comments on Final Staff Report - Plan for Resolving Spent Fuel Storage Pool Action Plan Issues - (TAC No. M88094)
The purpose of this letter is to provide comments on the staff report on Spent Fuel Storage Pool issues and the accompanying NRC letter (dated September 26,1996) that was sent to NSP.
The accompanying letter states:
The staff noted that the SFP's at Prairie Island are not capable of being cooled by a system powered from an onsite source without special reconfiguration of the electrical distribution system.
The following describes our current configuration:
The SFP cooling system's power is normally supplied by 480V Bus 1GA1 fed by 480V Bus 190 (via 4160V Bus 13) and 1GA2 fed by 480V Bus 290 (via 4160 Bus 24).
s in the event of a loss of offsite power, the ability exists to align either Diesel Generator D3 to Bus 190 and/or Diesel Generator D4 ot Bus 290, which would provide redundant backup SFP cooling capability. Diesel Generators D3 and D4 are both non-safeguards diesel generators. This change in power supply lineup f' [f
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USNRC NORTHERN STATES POWER COMPANY November 14,1996 Page 2 can be accomplished utilizing approved Prairie Island operating procedures, "C20.16 AOP1 Powering of Spent Fuel Pool Cooling and Battery Room Cooling from D3 Following a Loss of Offsite Power," and "C20.16 AOP2 Powering of Spent Fuel Pool Cooling and Battery Room Cooling from D4 Following a Loss of Offsite Power."
Additionally, a modification is in process to change the power supplies for the SFP cooling system to safeguards sources backed by safeguards diesel generators. This modification is planned to be operational within the next five months. At that time, there should be no Prairie Island SFP design concerns to be considered for regulatory analysis.
4 Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any questions regarding our understanding of this issue.
In this letter we have made no new Nuclear Regulatory Commission commitments.
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i Michael D Wadley Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator-Region Ill, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg SFPCMh7S DOC