ML20004F600
From kanterella
| ML20004F600 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/22/1981 |
| From: | Gilberts D NORTHERN STATES POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-26, NUDOCS 8106190190 | |
| Download: ML20004F600 (2) | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3801999-10-21021 October 1999
[Table view]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 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 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 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 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 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 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 ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE 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 IR 05000263/19990031999-06-18018 June 1999 Forwards Insp Rept 50-263/99-03 on 990409-0520.Four Violations Noted & Being Treated as non-cited Violations, Consistent with App C of Enforcement Policy 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 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 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 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 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 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 1999-09-09 Category:INCOMING CORRESPONDENCE MONTHYEARML20216J8091999-09-24024 September 1999
[Table view]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 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 ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions 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 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 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 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 ML20155A2661998-10-23023 October 1998 Forwards Rev 16 to USAR for Monticello Nuclear Generating Plant. Summary of Changes,Tests & Experiments Made Under Provisions of 10CFR50.59(b)(2) Also Encl.Rev Updates Info in USAR for Period Up to 980801 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 ML20154D7921998-10-0101 October 1998 Forwards Response to NRC RAI Re Licensee 971118 Request for Deviation from Emergency Procedures Guidelines.Proprietary Flow Charts,Including Rev 5 to C.5-110 RPV Control & Rev 6 to C.5-110 RPV Control, Encl.Proprietary Info Withheld ML20154D8031998-09-25025 September 1998 Submits Annual Rept of Any Change or Error Identified in ECCS Analytical Models or Application 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 ML20153F5351998-09-25025 September 1998 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Improved TS 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 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 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 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 1999-09-09 Category:UTILITY TO NRC MONTHYEARML20059H5411990-09-0606 September 1990
[Table view]Requests Amend to Certification of Financial Assurance for Decommissioning Plant,Per 10CFR50.75(c).Findings of Fact, Conclusions of Law & Order Encl ML20059E8801990-09-0606 September 1990 Forwards Rev 32 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059D5071990-08-29029 August 1990 Forwards Effluent & Waste Disposal Semiannual Rept for Jan- June 1990, Amended Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1989 & Rev 7 to ODCM ML20058M7811990-08-0606 August 1990 Forwards Rev 31 to Security Plan.Rev Withheld Per 10CFR73.21 ML20055J0671990-07-16016 July 1990 Submits Results of Sample Split Performed at Facility During May 1990 ML20043D5651990-06-0505 June 1990 Forwards Rev 30 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20042E8671990-04-27027 April 1990 Forwards Radiation Environ Monitoring Program 1989. ML20033G4551990-04-0202 April 1990 Forwards Definition of Drywell Boundaries for Security Plan. Encl Withheld (Ref 10CFR73.21) ML20012E0091990-03-21021 March 1990 Forwards Completed Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey ML20033H1221990-03-0606 March 1990 Forwards Summary of Levels of Nuclear Property Insurance Maintained by Util for Plants,Per 10CFR50.54(w) ML20012A1801990-02-28028 February 1990 Forwards Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1989 & Amend to Rept for Jan-June 1989,including Second Quarter Analyses Results of Sr-89 & Sr-90 ML20006F5691990-02-16016 February 1990 Forwards Annual Rept of Occupational Exposure & Annual Rept of Safety Valve & Relief Valve Failures & Challenges ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011D9651989-12-27027 December 1989 Forwards Safeguards Responses to Violations Noted in Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $3,750 Re Insp Rept 50-263/89-24.Encl Withheld (Ref 10CFR73) ML19353B1351989-12-0101 December 1989 Forwards Executed Amend 11 to Indemnity Agreement B-42, Reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements. ML19325F0861989-11-0707 November 1989 Forwards Rev 29 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML19324B8011989-11-0606 November 1989 Forwards Rev to Safeguards Contingency Plan & Implementing Procedures,Per Generic Ltr 89-07 Re Safeguards Planning for Surface Vehicle Bombs.Rev Withheld (Ref 10CFR50.54(f) ML20246L5021989-08-31031 August 1989 Responds to Generic Ltr 89-12, Operator Licensing Exams ML19332B5721989-08-28028 August 1989 Forwards Effluent & Waste Disposal Semiannual Rept,Period: Jan-June 1989. Amend to Effluent & Waste Disposal Semiannual Rept (for Second Half Yr of 1988) Also Encl ML20247Q2631989-08-0404 August 1989 Forwards Response to NRC Re Violations Noted in Insp Rept 50-263/89-16.Response Withheld ML20245L6541989-06-26026 June 1989 Responds to NRC Re Violations Noted in Insp of License DPR-22 Re RCIC Inoperability.Corrective Actions:Test Procedure 7140 Revised to Perform Sys Operability Test After Completion of Level Switch Test ML20247F9581989-05-25025 May 1989 Forwards Rev 28 to Security Plan.Rev Withheld ML20245E5951989-04-27027 April 1989 Forwards Safeguards Event Log for First Quarter 1989.Log Withheld ML20247K4251989-04-14014 April 1989 Responds to NRC Re Violations Noted in Insp Rept 50-263/89-04.Corrective Actions:Initial & Continuing Training Programs for Radiation Protection Personnel Will Be Reviewed & Upgraded Re Administrative Requirements ML20245B8531989-04-12012 April 1989 Forwards Annual Rept to Nrc,Radiation Environ Monitoring Program for 1988 ML20248C5261989-04-0303 April 1989 Requests NRC Review & Approval of Encl Proposed Change in Facility Security Plan Permitting short-term Alterations in Security Force Manning.Change Withheld ML20247G4841989-03-29029 March 1989 Forwards Rev 27 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20235Y4111989-02-28028 February 1989 Forwards Effluent & Waste Disposal Semiannual Rept, Jul-Dec 1988 & Amend to Disposal Semiannual Rept for Jan-June 1988.Analyses for Sr-89 & Sr-90 Not Completed in Time & Will Be Included W/Next Semiannual Rept ML20196C9471988-11-30030 November 1988 Notifies Commission of Change in Completion Schedule for Improvements in Instrument Valve Identification Procedures Described in Util ML20153D8001988-08-26026 August 1988 Forwards Response to Re Violations Noted in Insp of License DPR-22.Response Withheld (Ref 10CFR73) ML20207F6091988-08-12012 August 1988 Forwards Rev 3 to Facility Safeguards Contingency Plan.Rev Withheld ML20207F6571988-08-12012 August 1988 Forwards Rev 25 to Plant Security Plan.Rev Withheld (Ref 10CFR73) ML20151F4341988-04-12012 April 1988 Forwards Rev 24 to Security Plan,Per 10CFR50.54(p).Rev Withheld (Ref 10CFR73) ML20151F4391988-04-12012 April 1988 Forwards Rev 8 to Security Force Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld (Ref 10CFR73) ML20151F4331988-04-12012 April 1988 Forwards Rev 2 to Safeguards Contingency Plan.Changes Do Not Decrease Effectiveness of Safeguards Contingency Plan & May Be Implemented W/O Prior NRC Review & Approval.Rev Withheld (Ref 10CFR73) ML20150E2541988-03-21021 March 1988 Informs of Rev to Commitment Made Re Licensed Operator Training & Requalification Programs.Util Will Conduct Future Operator Training Using Program Accredited by INPO in Dec 1987.Program Available for NRC Review ML20148A5001988-03-0808 March 1988 Forwards Payment of Civil Penalty in Amount of $50,000, Per NRC 880219 Order ML20147G2621988-02-25025 February 1988 Forwards Endorsements 87,86,73,72 & 91 to Nelia Policies NF-174,NF-174,NF-197 & NF-197,Endorsements 8 to Nelia Certificates N-17,N-63 & N-37 & Endorsements 72,71 & 62 to Maelu Policies MF-51,MF-51 & MF-68,respectively ML20234C3151987-12-29029 December 1987 Forwards Rev 23 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20236V3611987-11-30030 November 1987 Forwards Rev 22 to Security Plan.Rev Consists of Miscellaneous Changes Required to Implement Changes to 10CFR73.Rev Withheld (Ref 10CFR73.21) ML20235K5531987-09-29029 September 1987 Forwards Response to NRC 870805 Request for Addl Info Re Submittal of NSPNAD-8608 & NSPNAD-8609 Concerning Reactor Physics Methods Qualification & Reload Safety Evaluation Methods for Facility ML1129712091987-08-28028 August 1987 Forwards Supplemental Info for 870727 Application for Amend to License DPR-22,including Proprietary NEDE-24050-2, Suppl 2 to LOCA Analysis Rept for Monticello Nuclear Generating Plant. ML20215E3491987-06-0101 June 1987 Responds to Generic Ltr 87-06 Re Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves. Info Provided Includes Listing of Pressure Isolation Valves & Description of Testing Done to Verify Integrity ML20206C9321987-03-16016 March 1987 Forwards Endorsements 7 to Maelu Certificates M-37,M-36 & M-17 & Nelia Certificates N-37,N-36 & N-17,Endorsement 59 to Maelu Policy MF-68,Endorsements 69 to Nelia Policy NF-197 & Maelu Policy MF-51 & Endorsement 83 to Nelia Policy NF-174 ML20207R0331987-02-11011 February 1987 Clarifies Items Identified in Insp Rept 50-263/86-08,per 870105 Telcon.Changes Re Svc Water Sys Pump Motors,Hpci & RCIC Flow,Shorting Switches & App R Requirements for Cabling Listed ML20210B3211987-01-0707 January 1987 Responds to NRC Re Violations Noted in Insp Rept 50-263/86-04.Corrective Actions:Standby Liquid Control Sys Modified to Eliminate Fuse Coordination Problem.Sys Tested W/Shorted Condition to Verify Proper Fuse Coordination ML20214R3701986-11-24024 November 1986 Forwards Rev 20 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20214C3621986-11-12012 November 1986 Forwards Affidavit Re Enforcement Action 86-164,per 10CFR2.202(d) & 861020 Order to Show Cause ML20214C8261986-11-12012 November 1986 Responds to IE Bulletin 86-003, Potential Failure of Multiple ECCS Pumps Due to Single Failure.... Plant Does Not Have Single Failure Vulnerability in Min Flow Recirculation Lines of Any ECCS Pump ML20213G1371986-11-10010 November 1986 Suppls Response to IE Bulletin 80-08 Re Exam of Containment Liner Penetration Welds & Discusses Listed Followup Actions to Resolve Open Status Identified in NUREG/CR-3053.Exam Unnecessary Due to Low Stresses in Weld 1990-09-06 |
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Northem States Power Company 9
J 414 Nicollet Man D.E. Gilberts l Minneapoks. Minnesota 55401 s.n or vie. Pr ie.m !
Telephone (612) 330-6071 Power supply 1 May 22, 1981 7 9 0 %
9> f dl 4 Mr. James G. Keppler c' N
nCULb((*d t L Director, Region III h. ..,13 IO3I h 'I Office of Inspection and Enforcement U. S. Nuclear Regulatory Ccamission g u.s. re,, g 799 Roosevelt Road i fj\,
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Og _
f Glen Ellyn, IL 60137
Dear Mr. Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Responge to IE Bulletin No. 79-26, Rev. 1 The destructive examination of Monticello's most highly exposed control blade 'nas been completed, with the following results, in response to IE Bulletin No. 79-26, Revisien 1, Item 4.
A. The tubes examined were tubes numbers 1, 2, 3, 4, 5, 7, 10, 12, 20 and 21 from wing 1 of control blade MT77R. (Tube 1 is the outermost tube).
B. All of the tubes were visually examined, and the tcp approximately one-half of each tube was also eddy-current tested. Through-wall defects were found in tube 1 at the following approximate dis:.ances from the tube top: 4, 4 , 5 , 9k,11,11 3/4,13k,16, 20, 26, 29 3/4, and 30 inches. No through-wall defects were found in any other tube.
C. The calculated B-10 depletion (percent) for each tube examined versus elevation is:
Tub e Upper 3' Upper Mid 3' Lower Mid 3' Lower 3' 1 47 37 33 7 2 45 35 32 6 3 43 34 30 6 4 41 32 29 6 5 39 30 27 5 7 36 28 25 5
\/ %$
10 33 26 23 5
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12 32 25 22 4 20 25 20 18 3 i
21 24 19 17 3 !
- 810 a 10o 80 0
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+
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- e .
Mr. James G. Keppler Page 2 May 22,1981 l D. The only significant loss of B gC was found to be in tube 1. The loss front extended from the top end plug down about 33 inches.
E. The =mv4=um local depletion for tubes having no cracks was found to be 6* .98 percent B-10 depletion, near the top of tube 3.
. F. The maximum local depletion for tubes having no loss o' boron was found to be 67.98 percent B-10 depletion, near the top of e <te 3. (This is the same as item I because the only tube with a crac 2 also showed a loss of boron.)
If additional information is required, please communicate directly with plant management.
Yours truly, D. E. Gilberts Senior Vice President Power Supply cc: '[r. C. H. Brown Mr. G. Charnoff Director, Office of Inspection and Enforcement Division of Reacter Operations Inspection U. S. Nuclear Regulatory Commission Washington, D. C. 20555 DEG:nk i
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