Letter Sequence Supplement |
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MONTHYEARML20094N9281995-11-20020 November 1995 Forwards 91C2687.A46, USNRC USI A-46 Resolution Seismic Evaluation Rept Monticello Nuclear Generating Plant, in Response to Suppl 1 to GL 87-02 Project stage: Other ML20100J1101996-02-19019 February 1996 Supplemental Response to Suppl 1 to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue USI A-46 Project stage: Supplement ML20134C3391997-01-29029 January 1997 Forwards RAI Re 951120 Summary Rept,In Response to USI A-46 Project stage: RAI ML20138G0431997-04-29029 April 1997 Forwards Response to 970129 RAI Re Resolution of Unresolved Safety Issue A-46.Samples of Anchorage Calculations Done W/Anchor Program,Also Encl Project stage: Other ML20138F6751997-04-29029 April 1997 Provides Update on Status of Response to GL 87-02,Suppl 1 Project stage: Other ML0312007011997-10-0808 October 1997 Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions Project stage: Request ML20217G7321997-10-0808 October 1997 Forwards RAI Re Licensee 970426 Submittal Re USI A-46 Seismic Evaluation Rept Project stage: RAI ML20199C8981997-11-12012 November 1997 Forwards Rev to Staff Request for Addl Info Related to Unresolved Safety Issues A-46 Seismic Evaluation Rept.Rev Adds Three Addl Questions & Extends Response Date to 980115 from 971219 Project stage: RAI ML20197H3531997-12-17017 December 1997 Informs of Plans to Respond to Majority of 971112 RAI Questions by 980115 Re USI A-46.Addl Time Is Requested to Respond to Questions 6,7 & 8.NSP Would Like to Withhold Response Until Industry Position Is Determined Project stage: Other ML20199G9801998-01-15015 January 1998 Provides Response to Question 6 in 971008 & 1112 RAIs on Resolution of USI A-46,seismic Evaluation Rept.Responses to Questions 7 & 8 Will Be Submitted by 980215 Project stage: Other ML20203C2431998-02-11011 February 1998 Provides Response to Questions 7 & 8 in 971008 & 1112 RAIs on Resolution of USI A-46,seismic Evaluation Rept Project stage: Other ML20197A9001998-02-27027 February 1998 Forwards RAI Re USI A-46, Seismic Evaluation Rept. Response Requested by 980508 Project stage: RAI ML20247M1721998-05-15015 May 1998 Provides Response to Request for Addl Info on Resolution of Unresolved Safety Issue A-46.Submittal Contains No New NRC Commitments & Does Not Modify Any Prior Commitments Project stage: Request 1997-12-17
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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 ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted 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 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 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 ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls 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 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 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 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 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 ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font 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 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 ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl 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 ML20206G2181999-05-0505 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Dtd 960110,for Plant 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 ML20206G7741999-05-0303 May 1999 Forwards Insp Rept 50-263/99-02 on 990223-0408.One Violation Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20205N0821999-04-12012 April 1999 Forwards SE of NSP Response to NRC GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Licensee Adequately Addressed Actions Requested in GL ML20205N4811999-04-0909 April 1999 Forwards Licensing Requalification Insp Rept 50-263/99-10 on 990308-12.No Violations Noted.However,Inspectors Through Observation of Simulator Scenario Exams Noted Difficulties in Ability of SM to Simultaneously Implement Duties of SM ML20205N5301999-04-0909 April 1999 Discusses Arrangements Made on 990406 for Administration of Licensing Exams at Monticello Nuclear Generating Station During Wk of 990823.Requests That Exam Outlines Be Submitted by 990128 & Supporting Ref Matls by 990719 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C4851999-03-26026 March 1999 Informs That on 990203,NRC Staff Completed PPR of Nuclear Plant.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20205A5881999-03-24024 March 1999 Forwards Request for Addl Info Re Submittal Requesting Rev of pressure-temperature Limits & Surveillance Capsule Withdrawal Schedule ML20204H4711999-03-18018 March 1999 Forwards SER Concluding That Util Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello & Adequately Addressed Actions Requested in GL 96-05 ML20207H5161999-03-11011 March 1999 Forwards Insp Rept 50-263/99-01 on 990112-0222.No Violations Noted ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8091999-09-24024 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 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 ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed 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 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 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 ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello ML20203A3081999-01-28028 January 1999 Forwards TS Page 60d,as Supplement 3 to 971125 LAR Re CST Low Level Hpci/Rcic Suction Transfer.Page Includes NRC Approved Amend 103 Changes for Use by NRC in Issuing SER ML20202F7821999-01-27027 January 1999 Forwards 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(vi).Ltr Contains No New Commitments or Modifies Any Prior Commitments ML20206S0331999-01-20020 January 1999 Submits Annual Rept of Safety & Relief Valves Failure & Challenges ML20206P1221998-12-31031 December 1998 Forwards LAR for License DPR-22,revising TS pressure-temp Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4, Deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR ML20198M3271998-12-28028 December 1998 Submits Change to Commitment for Submittal of ITS Application.Util Plans to Provide ITS Conversion Package Submittal to NRC in Dec of 2000 ML20198J7511998-12-22022 December 1998 Informs of Completion of Listed Commitment Made in Re Severe Accident Mgt. Severe Accident Mgt Guidelines Have Been Assessed,Plant Procedures Have Been Modified & Training of Affected Plant Staff Has Been Completed ML20198J4311998-12-21021 December 1998 Forwards Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv. Under Separate Cover,Licensee Is Providing LAR to Revise Curves ML20198J7711998-12-14014 December 1998 Documents 981214 Discussion with NRC Staff Re Deviation from Emergency Procedure Guidelines ML20195C8781998-11-11011 November 1998 Forwards Supplement to 971125 License Amend Request Re Condensate Storage Tank Low Level Suction Transfer Setpoints for HPCI Sys & Reactor Core Isolation Cooling Sys ML20195C9631998-11-11011 November 1998 Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment ML20195E2261998-11-10010 November 1998 Submits Suppl 1 to Util Response to NRC Request for Addl Info Re 981118 Request for Deviation from Emergency Procedure Guidelines ML20155H6591998-11-0404 November 1998 Forwards Response to 980910 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20155F9091998-10-27027 October 1998 Forwards Master Table of Contents to Rev 16 of Usar.Info Was Inadvertantly Omitted at Time of 981023 Submittal 05000263/LER-1998-005, Forwards LER 98-005-00,re HPCI Being Removed from Service to Repair Steam Leak in Drain Trap Bypass.Commitments Made by Util Are Listed1998-10-21021 October 1998 Forwards LER 98-005-00,re HPCI Being Removed from Service to Repair Steam Leak in Drain Trap Bypass.Commitments Made by Util Are Listed ML20154L9321998-10-12012 October 1998 Forwards Suppl 2 to LAR & Suppl 980319,which Proposed Changes to Ts,App a of Operating License DPR-22 for Mngp.Number of Addl Typos & One Title Change on Pages Associated with Amend Request Have Been Identified 05000263/LER-1998-004, Forwards LER 98-004-00 Re Manual Scram Inserted Following Pressure Transient Closes Air Ejector Suction Isolation Valves & Trips Offgas Recombiners.Ler Contains Listed Commitment1998-10-0909 October 1998 Forwards LER 98-004-00 Re Manual Scram Inserted Following Pressure Transient Closes Air Ejector Suction Isolation Valves & Trips Offgas Recombiners.Ler Contains Listed Commitment ML20154L8671998-10-0909 October 1998 Forwards Suppl 1 to LAR for License DPR-22, Replacing Exhibits B & C of Original Submittal to Reflect Item 2 & Subsequent Changes.Request for APRM Flow Converter Calibr Interval Extension,Withdrawn ML20154J6201998-10-0505 October 1998 Forwards Rev 49 to Monticello Security Plan.Encl Withheld, Per 10CFR73.21 ML20153F5351998-09-25025 September 1998 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Improved TS ML20153F0051998-09-25025 September 1998 Forwards Suppl 1 to 971031 Application for Amend to License DPR-22,replacing Exhibit C Which Contains TS Pages Incorporating Proposed Changes Described in Original 971031 Request ML20153D8561998-09-17017 September 1998 Forwards Rev 17 to EPIP A.2-414, Large Vol Liquid Sample &/ or Dissolved Gas Sample Obtained at Post Accident Sampling Sys. Superseded Procedures Should Be Destroyed.Ltr Contains No New NRC Commitments,Nor Does It Modify Prior Commitments ML20153D1441998-09-17017 September 1998 Informs NRC That Listed Commitments 1 & 3 Were Completed by End of 1998 Refueling Outage.Commitments Involved Final Disposition of Remaining Outlier Components Re All Known Outstanding Work Associated with GL 87-02,Suppl 1,USI A-46 ML20153E0331998-09-17017 September 1998 Forwards Response to NRC 980629 RAI Re RPV Weld Chemistry Values Previously Submitted as Part of Plant Licensing Basis.Next Monticello RPV Sample Capsule Scheduled to Be Removed During 1999/2000 Refueling Outage ML20153E9011998-09-0909 September 1998 Forwards Rev 1 to MNGP Colr,Cycle 19, Incorporating Changes to power-flow Maps in Figures 6 & 7.Changes Made to Correct Errors in Stability Exclusion Region & Stability Buffer Region Shown on Rev 0 ML20151S7401998-08-28028 August 1998 Responds to NRC Re Violations Noted in Insp Rept 50-263/98-09.Corrective Actions:Procedure 4 AWI-04.04.03 Will Be Revised to Eliminate Term Urgent from Section 4.3.1.D ML20238E8201998-08-26026 August 1998 Forwards Effluent & Waste Disposal Semi-Annual Rept for Jan-June 1998 & Revised Effluent & Waste Disposal Semi- Annual for Jul-Dec 1997. Ltr Contains No New NRC Commitments,Nor Does It Modify Any Prior Commitments ML20237E9741998-08-26026 August 1998 Forwards Rev 4 to EWI-09.04.01, Inservice Testing Program. Rev of Inservice Testing Program Reflects Valves Added as Result of Component Mods Recently Performed ML20237E6821998-08-25025 August 1998 Forwards fitness-for-duty Program Performance Data for Six Months Period Ending 980630 1999-09-09
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Nonthem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 ,
Monticello. Minnesota 55362-9637 )
l February 19,1996 Generic Letter 87 02 l
US Nuclear Regulatory Commission i Attn: Document Control Desk l Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Supplemental Response to Supplement 1 to Generic Letter 87-02,
" Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors. Unresolved Safety issue USI A-46"(TAC M69460)
> On February 19,1987, the NRC issued Generic Letter 87-02, " Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety issue (USI) A-46". This Generic Letter encouraged utilities to participate in a generic program to resolve the seismic verification issues associated with USl A-46. As a result, the Seismic Quali'ication Utility Group (SQUG) developed the " Generic implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment".
On May 22,1992, the NRC Staff issued Generic Letter 87-02 Supplement 1, which constituted the NRC Staff's review of the GIP and which included Supplemental Safety Evaluation Report Number 2 (SSER-2) on tho GIP, Revisica 2, corrected on February 14,1992. By letters dated September 21,1992, and November 20,1995; Monticello responded to Generic Letter 87-02 Supplement 1.
In our November 20,1995 letter, Monticello committed to a follow-up response within 90 days providing our schedule for corrective actions to address components identified as outliers during the relay evaluation. These components were listed in Table 7-1 of our report USNRC A-46 Resolution. Seismic Evaluation Report. Monticello Nuclear Generatino Plant: the Monticello SQUG report. This letter satisfies that commitment. Attachment 1 to this letter restates the iisting of components provided in Table 7-1 of the Monticello SQUG report and provides our schedule for resolution of these outliers. .
This letter contains the following new NRC commitment:
- 1. Outlier components identified in Table 1-1 of Attachment 1 are to be evaluated and resolved in accordance with the SQUG Generic Imolementation Procedures (GIP). For Seismic Verification of Nuclear Plant Eouloment. Revision 2, Section I 5, " Outlier identification and Resolution." This action is to be completed prior to 2/16/96 NSP tt\ DATA \NRCCORR\GL9702RR. DOC
" 3602280258 960219 PDR ADOCK 05000263 p PDR
~
USNRC NORTHERN STATES POWER COMPANY February 19,1996 Page 2 the end of the 1998 refueling outage, currently scheduled to commence in January 1998.
- 2. Outlier components identified in Table 1-2 of Attachment 1 are to be replaced with relays seismically qualified for their intended use during the Monticello 1996 refueling outage, scheduled for April 1996.
- 3. Outlier components identified in Table 1-3 of Attachment 1 are to be replaced with relays seismically qualified for their intended use during the Monticello 1998 refueling outage, currently scheduled to commence in January 1998.
Please contact Marv Engen, Sr Licensing Engineer, at (612) 295-1291 if you require further information.
h Einh W ,
William J Hill l Plant Manager l Monticello Nuclear Generating Plant c: Regional Administrator- 111, NRC NRR Project Manager, NRC Sr Resident inspector, NRC State of Minnesota, Attn: Kris Sanda Attachments: Affidavit to the US Nuclear Regulatory Commission l (1) Generic Letter 87-02, Supplement 1, Relay Evaluation Outlier Resolution l l
f
UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 Supplemental Response Dated February 19,1996 to Supplement 1 to Generic Letter 87-02, Nerification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors. Unresolved Safety Issue USI A-46" frac M69460)
Northem States Power Company, a Minnesota corporation, hereby provides the information requested by Supplement 1 to Generic Letter 87-02, as committed to in our November 20, 1995, submittal.
This letter contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY By / N*
William J Hf Plant Manager Monticello Nuclear Generating Plant l
On this day of [ebhv / 99h before me a notary public in and for a said County, personally appeared Vfilliam J Hill, Plant Manager, Monticello Nuclear Generating i Plant, and being first duly swom acknowledged that he is authorized to execute this document on beha!f of Northem States Power Company, that he knows the contents thereof, and that to i the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.
. tuo M'drvin R Engen /
l Notary Public- Minnesota f '.$
Sherbume County nn/#
My Commission Expires January 31,2000 MARVIN SCHARD ENGEN ,
j h0TMtYPusuC IMedESOTA i % N: E89: Jan. 31,2000; 1
r.
Attachment 1 Generic Letter 87-02. Supplement 1. Relav Evaluation Outlier Resolution The seismic capacity review performed using the Seismic Qualification User Group (SQUG) methodology identified a number of relays for which the Generic Equipment Ruggedness Spectra (GERS) or specific vendor qualification were not available. These relays are considered outliers and will require additional evaluation. The components listed in Table 1 1 below ere to be evaluated using the methodology for resolution of outliers contained in the SQUG Generic Implementation Procedures (GIPL For Seismic yp_riNeton of Nuclear Plant Eauipment. Revision 2, Section 5, " Outlier Identification and rb eJjution." This action is to be completed prior to the end of the 1998 refueling outage, c.urrently scheduled to commence in January 1998.
Table 1-1 Relay Outliers to be Further Evaluated Relay Designation and Panel Subsystem / Component used in ECRA (C91) G-3A (EDG 11)
ECRA (C92) G-3B (EDG 12)
ESR1 (C91) G-3A (EDG 11)
ESR1 (C92) G-3B (EDG 12)
ESR2 (C91) G-3A (EDG 11)
ESR2 (C92) G-3B (EDG 12)
ESRX1 (C91) P-111 A - 11 EDG-ESW pump, V-SF 11 EDG supply fan ESRX1 (C92) P-111B - 12 EDG-ESW pump, l V-SF 12 EDG supply fan l P-111 A - 11 EDG-ESW pump, !
ESRX2 (C91)
- V-SF 11 EDG wpply fan ESRX2 (C92) P-1118 - 12 EDG-ESW pump, V-SF 12 EDG supply fan ESTR (C91) G-3A (EDG 11)
ESTR (C92) G-3B (EDG 12)
FFC (C91) G-3A (EDG 11)
FFC (C92) G-3B (EDG 12)
FFCO (C91) G-3A (EDG 11)
FFCO (C92) G-3B (EDG 12)
FPR (C91) EDG 11 FPM - motor driven fuel pump FPR (C92) EDG 12 FPM - motor driven fuel pump FSR1 (C91) G-3A (EDG 11)
FSR1 (C92) G-38 (EDG 12)
FSR2 (C91) G-3A (EDG 11)
FSR2 (C92) G-38 (EDG 12)
GV (C91) G-3A (EDG 11)
GV (C92) G-3B (EDG 12)
' Attachment 1 February 19,1996
- Page 2 Table 1-1 (continued)
Relay Designation and Panel - Subsystem / Component used in [
MSR1 (C91) G-3A (EDG 11) ,_
_MSR1 (C92) G-3B (EDG 12) _ l MSR2 (C91) G-3A (EDG 11) .
MSR2 (C92) G-38 (EDG 12)
NFLD (C93) G-3A (EDG 11)
NFLD (C94) G-38 (EDG 12)
NFLDA (C93) G-3A (EDG 11)
NFLDA (C94) G-3B (EDG 12)
OT (C93) G-3A (EDG 11) '
OT (C94) G-38 (EDG 12)
OTR (C91) G-3A (EDG 11)
OTR (C92) G-3B (EDG 12)
PFDA1 (C91) G-3A (EDG 11)
PFDA1 (C92) G-38 (EDG 12)
PFDA2 (C91) G-3A (EDG 11)
PFDA2 (C92) G-38 (EDG 12)
SFA (C93) - G-3A (EDG 11)
SFA (C94) G-3B (EDG 12)
STR1 (C91) G-3A (EDG 11),
11 EDG MVST1 - air start solenoid, 11 EDG BPM booster pump motor ,
STR1 (C92) G-3B (EDG 12),
12 EDG MVST1 - air start solenoid, 12 EDG BPM booster pump motor STR2 (C91) G-3A (EDG 11),
11 EDG MVST2 - air start solenoid, 11 EDG BPM booster pump motor STR2 (C92) G-3B (EDG 12),
12 EDG MVST2 - air start solenoid, 12 EDG BPM booster pump motor VSR1 (C91) G-3A (EDG 11)
VSR1 (C92) G-3B (EDG 12) .
VSR2 (C91) G-3A (EDG 11) l VSR2 (C92) G-3B (EDG 12)
ZSR1 (C91) G-3A (EDG 11)
ZSR1 (C92) G-38 (EDG 12)
ZSR2 (C91) G-3A (EDG 11)
ZSR2 (C92) G-3B (EDG 12) l l
~
' 9' ,.
Attachment 1 February 19,1996 Page 3 The following relays identified as outliers per the methodology contained in the SQUG GIP are to be resolved by component replacement. These relays are to be replaced with relays seismically qualified for their intended use during the Monticello 1996 refueling j outage, scheduled for April 1998.
Table 1-2 PFD1 (C92) G-3B (EDG 12)
PFD2 (C92) G-3B (EDG 12)
SFB1 (C92) G-38 (EDG 12)
SFB2 (C92) G-3B (EDG 12)
SFD1 (C92) G-3B (EDG 12)
SFD2 (C92) G-3B (EDG 12)
SSP 1 (C92) G-3B (EDG 12)
SSP 2 (C92) G-38 (EDG 12)
The following relays identified as outliers per the methodology contained in the SQUG GIP are to be resolved by component replacement. These relays are to be replaced with relays seismically qualined for their intended use during the Monticello 1998 refueling outage, currently scheduled to commence in January 1998.
Table 1-3 PFD1 (C91) G-3A (EDG 11)
PFD2 (C91) G-3A (EDG 11)
SFB1 (C91) G-3A (EDG 11)
SFB2 (C91) G-3A (EDG 11)
SFD1 (C91) G-3A (EDG 11)
SFD2 (C91) G-3A (EDG 11)
SSP 1 (C91) G-3A (EDG 11)
SSP 2 (C91) G-3A (EDG 11)