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MONTHYEARML20129E0771996-09-25025 September 1996 Requests That Northern States Revise Oqap & TS Amend Request to Address Listed Issues & That Oqap Be Resubmitted & TS Amend Request Be Supplemented Accordingly Project stage: Other ML20134D0501996-10-0909 October 1996 Forwards Errata to Re Review of Rev 20 to Operational QAP for Monticello & Prairie Island Sites.Ref to Be Changed to Oqap Should...Conform to Guidance Provided in Administrative Ltr 95-06..., Not Guidance in GL 95-06 Project stage: Approval ML20199C9271997-11-12012 November 1997 Informs That 970714 Submittal of Operational Quality Assurance Plan,Rev 20 for Plant,Units 1 & 2,has Been Approved Project stage: Other 1996-09-25
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel ML20217B1421999-09-30030 September 1999 Informs That on 990902,NRC Staff Completed mid-cicle Plant Performance Review of Monticello Nuclear Generating Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Information & to Plan for Insp Activities ML20216J2491999-09-30030 September 1999 Ack Receipt of 980804,990626 & 0720 Ltrs in Response to GL 98-01,suppl 1, Year 2000 Readiness of Computer Sys at Npps. Staff Review Has Concluded That All Requested Info Has Been Provided ML20212K9131999-09-30030 September 1999 Refers to 990920 Meeting Conducted at Monticello Nuclear Generating Station to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr ML20216J8091999-09-24024 September 1999 Informs That New Diaphragm Matl Has Corrected Sticking Problem Associated with Increased Control Rod Drive Scram Times.Augmented Testing of Valves at Monticello Has Been Discontinued ML20216G4341999-09-24024 September 1999 Forwards Exam Rept 50-263/99-301 on 990823-26.Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy.Test Was Administered to Two Applicants. Both Applicants Passed All Sections of Exam ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F0901999-09-21021 September 1999 Confirms Discussion Between M Hammer & Rd Lanksbury to Have Routine Mgt Meeting on 991005 in Lisle,Il.Purpose of Meeting to Discuss Improvement Initiatives in Areas of Operations & Equipment Reliability ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211Q6981999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Monticello Operator License Applicants During Wks of 010604 & 11.Validation of Exam Will Occur at Station During Wk of 010514 ML20211L1981999-09-0101 September 1999 Forwards Insp Rept 50-263/99-05 on 990702-0812.No Violations Noted ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211F9961999-08-26026 August 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 990101-990630, Revised Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 & Revs to ODCM for Monitcello Nuclear Generating Plant ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 ML20211C9501999-08-23023 August 1999 Forwards Rev 17 to Monticello Nuclear Generating Plant USAR, Updating Info in USAR to Reflect Implementation of Increase in Licensed Core Thermal Power from 1,670 Mwt to 1,775 Mwt.Rept of Changes,Tests & Experiments Not Included ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions ML20210T9601999-08-12012 August 1999 Provides Rept on Status of Util RPV Feedwater Nozzle Insps Performed in Response to USI A-10 Re BWR Nozzle Cracking ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel ML20217B1421999-09-30030 September 1999 Informs That on 990902,NRC Staff Completed mid-cicle Plant Performance Review of Monticello Nuclear Generating Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Information & to Plan for Insp Activities ML20212K9131999-09-30030 September 1999 Refers to 990920 Meeting Conducted at Monticello Nuclear Generating Station to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA ML20216J2491999-09-30030 September 1999 Ack Receipt of 980804,990626 & 0720 Ltrs in Response to GL 98-01,suppl 1, Year 2000 Readiness of Computer Sys at Npps. Staff Review Has Concluded That All Requested Info Has Been Provided IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr ML20216G4341999-09-24024 September 1999 Forwards Exam Rept 50-263/99-301 on 990823-26.Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy.Test Was Administered to Two Applicants. Both Applicants Passed All Sections of Exam ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F0901999-09-21021 September 1999 Confirms Discussion Between M Hammer & Rd Lanksbury to Have Routine Mgt Meeting on 991005 in Lisle,Il.Purpose of Meeting to Discuss Improvement Initiatives in Areas of Operations & Equipment Reliability ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211Q6981999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Monticello Operator License Applicants During Wks of 010604 & 11.Validation of Exam Will Occur at Station During Wk of 010514 ML20211L1981999-09-0101 September 1999 Forwards Insp Rept 50-263/99-05 on 990702-0812.No Violations Noted ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam ML20210H0861999-07-28028 July 1999 Forwards Insp Rept 50-263/99-04 on 990521-0701.No Violations Noted.Licensee Conduct at Monticello Facility Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML20209J0941999-07-15015 July 1999 Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing Actions ML20209G5621999-07-14014 July 1999 Forwards Insp Rept 50-263/99-11 on 990621-24.No Violations Noted.Objective of Insp,To Determine Whether Monticello Nuclear Generating Station Emergency Plan Adequate & If Station Personnel Properly Implemented Emergency Plan ML20209H8361999-07-0202 July 1999 Forwards Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) for Tests Administered During Week of 990517-21.Two Applicants Passed All Sections of Exam & Issued Reactor Operator Licenses to Operate Pings ML20196J5351999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950515 & NSP Responses & 980917 for Monticello Npp.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209F0391999-06-30030 June 1999 Forwards Insp Repts 50-282/99-04 & 50-306/99-04 on 990407-0531.Violation Noted.Notice of Violation or Civil Penalty Will Not Be Issued,Based on NRC Listed Decision to Exercise Discretion ML20196D5501999-06-18018 June 1999 Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls ML20196A6741999-06-17017 June 1999 Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML20207D0641999-05-26026 May 1999 Informs of Plans to Conduct Meeting on 990614 in Red Wing,Mn,To Present Planned Changes to NRC Regulatory Processes & Pilot Plant Program for Prairie Island Nuclear Generating Station ML20207B5841999-05-26026 May 1999 Forwards SER Concluding That Licensee 990412 Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Reactor Vessel Head Penetrations for part-length CRDMs Will Provide Acceptable Quality & Safety ML20207B7941999-05-25025 May 1999 Forwards Insp Repts 50-282/99-05 & 50-306/99-05 on 990426- 30.No Violations Noted.Overall Plant Radiological Controls Effective in Maintaining Reasonable Collective Dose for Work Being Conducted During Unit 1 Refueling Outage ML20207B3281999-05-24024 May 1999 Informs That in May 1999,Region III Received Rev 20 to Portions of Prairie Island Nuclear Generating Center Emergency Plan.Rev Submitted Under Provisions of 10CFR50.54(q) ML20207A1491999-05-20020 May 1999 Forwards Request for Addl Info Re Areas of Seismic,Fire,High Winds,Floods & Other External Events for IPEEE Submittals for PINGP Dtd Dec 1996,March 1998 & Dec 1998 ML20206N5601999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Monticello Npp.Organization Chart Encl ML20206S0891999-05-13013 May 1999 Informs That on 990505 NRC Staff Held Planning Meeting for Plant to Identify Insp Activities at Facility Over Next 6 to 12 Months ML20206N4581999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl ML20206G2181999-05-0505 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Dtd 960110,for Plant ML20206J2101999-05-0404 May 1999 Forwards Insp Repts 50-282/99-02 & 50-306/99-02 on 990226-0406.No Violations Noted.During Insp Period,Sf Casks 08 & 09 Successfully Loaded & Cask 08 Transported & Placed in ISFSI ML20206G4901999-05-0404 May 1999 Forwards Staff Review of Licensee 960508 Response to NRC Bulletin 96-002, Movement of Heavy Loads Over Sf,Over Fuel in Rc or Over Safety-Related Equipment, .Overall, Responses Acceptable.Tac M95610 Closed 1999-09-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 30066-0001
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'S,,,,, November 12, 1997 ggg Mr. Roger O. Anderson, Director Nuclear Energy Engineering Northern States Power Company 414 Nicollet Mall Minnsspolis, Minnesota 55401
SUBJECT:
APPROVAL OF NORTHERN STATES POWER COMPANY'S OPERATIONAL QUAllTY ASSURANCE PLAN, REVISION 20 (TAC NOS. M95130 AND M95131)
Dear Mr. Anderson:
On April 19,1996, Northem States Power Company (NSP) submitted Revision 20 of the Operational Quality Assurance Plan (OQAP) for approval by the Nuclear Regulatory Commission pursuant to 10 CFR 50.54(a). On September 25,1996, we forwarded the preliminary results of our review of Revision 20 to the OQAP. On December 19,1996, NSP submitted a revised Revision 20 of its OQAP to address the NRC staff comments.
Subsequently, on July 14,1997, NSP submitted a second revised version of Revision 20 which superseded all previous versions of the OQAP. The revised OQAP supported an application to amend the Prairie Island, Unit Nos.1 and 2, technical specifications (TS) to relocate and revise the administrative controls delineated in the TS. The amendments will be addressed by separate correspondence.
OQAP Revision 20, incorporates the following new sections: Section 7.3, " Procedures,"
Section 8.4.4, " Prairie Island Procedure Control," Section 19.12, " Prairie Island Operating Records," Section 21.0, " Prairie Island Safety Audit Committee (SAC)," and Section 22.0,
" Prairie Island Operations Committee (OC)."
Section 7.3, " Procedures," includes, verbatim, procedure related provisions included in current TS 6.5," Plant Operating Procedures," that do not have to be retained in TS to conform to Section 5.4," Procedures," of NUREG 1431, Revision 1.
Section 8.4.4, " Prairie Island Procedure Control," includes, verbatim, the control of temporary changes currently in TS 6.5.C, " Temporary Changes to Procedures."
Section 19.12, " Prairie Island Operating Records," includes, verbatim, the record retention requirements currently in TS 6.6," Plant Operating Records."
Section 21.0 defines the Prairie Island SAC function, membership, qualifications, meeting frequency, quorum, responsibilities, authority, and records provisions which agree verbatim I with the review and audit functions currently specified in TS 6.2.
Section 22.0 defines the Prairie Island Operations Committee (OC) membership, meeting frequency, quorum, responsibilities, authority, records, and procedures provisions which agree verbatim with the review and audit functions currently specified in TS 6.2.
9711200197 971112 PDR ADOCK 05000243 ,.,
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R. O. Anderson November 12, 1997 All future changes to the OQAP are to be controlled pursuant to 10 CFR 50.54(a). OQAP, Revision 20, constitutes the bases for the licensee's continued compliance with the requirements of Appendix B to 10 CFR Part 50 and Revision 20 to the OQAP, dated July 14, 1997, tutinues to comply with the criteria of Appendix B to 10 CFR Part 50 in accordance with NUREG-0800 (Standard Review Plan Sections 13.4 and 17.2). Therefore, the staff approves, OQAP, Revision 20, as submitted on July 14,1997.
Sincerely, ORIGINAL SIGNED BY
< r Beth A. Wetzel, t;enior Project Manager Project Directorate ill 1 <
Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50 282,50 306, and + -
50-263 ,
cc: See next page >
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- DISTRIBUT10N' .
Docket File
. PUBLIC '-
PD#31 Reading ,
E. Adensam B. Wetzel ,
' T. J. Kim 'i J. Peralta, HQMB i T. Tjader, OTSB OGC ACRS J. McCormick Barger, Region til DOCUMENT NAME: G:\WPDOCS\ PRAIRIE \Pl95130.QAP T3 receive e copy of thle escument, indicate in the aos: "C" e Copy methout attechment/smelosure *E's Copy with attachment / enclosure *f a No copy OFFICE PM:PD31 E ! LA:PD31 E BC:HQMB lg D;PD31 g(lg NAME LGundrum:dbM CJamerson djy SBlack R(f (, JHannon" l DATE 11/(, /97 11/ 6 /97 (/ 11/10 /97 11// 9 7 l
OPPICIAL EECORD COPY l
,_ . . , _ . _ . . . , _ . _ _ . . . __ _. _ _ ...~. _ . _ _ _ .
R. O. Anderson 2-All future changes to the OQAP are to be controlled pursuant to 10 CFR 50.54(a). OQAP, Revision 20, constitutes the bases for NSP's continued compliance with the requirements of Appendix B to 10 CFR Part 50 and Revision 20 to the OQAP, dated July 14,1997, continues to comply with the criteria of Appendix B to 10 CFR Part 50 in accordance with NUREG-0800 (Standard Review Plan Sections 13.4 and 17.2). Therefore, the staff approves OQAP, >
Revision 20, as submitted on July 14.1997.
Sincera!y, gkts Q. t .
Both A. Wetzel, Senior Project Manager Project Directorate lll 1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Re0ulation Docket Nos. 50 282,50 3M, and 50 263 cc: See next page l
l L -- - . - -
, Mr. Roger O. Anderson, Director Prairie Island Nuclear Generating ;
Northem States Power Company Plant l l
cc:
i J. E. Silberg, Esquire Site Licensing i Shaw, Pittman, Potts and Trowbridge Prairie Island Nuclear Generating 2300 N Street, N. W. Plant Washington DC 20037 Northem States Power Company 1717 Wakonado Drive East Plant Manager Welch, Minnesota 55089 Prairie Island Nuclear Generating Plant Tribal Council -
Northem States Power Company Prairie Island Indian Community 1717 Wakonado Drive East ATTN: Environmental Department Welch, Minnesota 55089 5636 Sturgeon Lake Road Welch, Minnesota 55089 Aconis A. Neb!ett Assistant Attomey General ONice of the Attomey General 455 Minnesota Street Suite G30 St. Paul, Minnesota 55101 2127 U.S. Nuclear Regulatory Commission Resident inspector's ONice 1719 Wakonade Drive East Welch, Minnesota 55089 9642 Regional Administrator, Region ill U.S. Nuclear Regulatory Commisslori 801 Warrenville Road Lisle, Illinois 60532 4351 Mr.'Jeff Cole, Auditor / Treasurer Goodhue County Courthouse Box 408 Red Wing, Minnesota 55066-0408
- Kris Sanda, Commissioner Department of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota 55101 2145 November 1996
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