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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20211J1611999-08-17017 August 1999 Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210Q1941999-08-11011 August 1999 Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210N5881999-08-0606 August 1999 Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements ML20210N5471999-08-0505 August 1999 Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License ML20210N5491999-08-0505 August 1999 Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application ML20210N1291999-08-0505 August 1999 Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr ML20210N9291999-08-0404 August 1999 Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1) ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20211B5381999-07-30030 July 1999 Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC ML20210J0741999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks ML20211C3251999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20210E4941999-07-23023 July 1999 Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan ML20210D0911999-07-22022 July 1999 Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc ML20210C5011999-07-21021 July 1999 Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested ML20210A5021999-07-20020 July 1999 Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment ML20211N9101999-07-20020 July 1999 Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) ML20210C8461999-07-19019 July 1999 Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested ML20209J5171999-07-16016 July 1999 Forwards Comments from Accuracy Review of License Renewal Application SER ML20210B7651999-07-15015 July 1999 Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl ML20209G2081999-07-13013 July 1999 Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted ML20210A6311999-07-0606 July 1999 Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20209C1391999-07-0202 July 1999 Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future ML20210D1531999-06-30030 June 1999 Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations ML20209B5781999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20210D1741999-06-24024 June 1999 Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info ML20211H8431999-06-23023 June 1999 Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl ML20196C6831999-06-21021 June 1999 Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701 ML20196C4291999-06-21021 June 1999 Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes ML20195J8271999-06-16016 June 1999 Ack Receipt of to Jackson,Chairman of NRC Re Environ Impacts of Increased Patuxtent River Complex Flight Operations on Ccnpp.Clarification & Correction of Listed Statement Found on Page Two,Provided 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl ML20210N5881999-08-0606 August 1999 Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements ML20210N5491999-08-0505 August 1999 Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application ML20210N5471999-08-0505 August 1999 Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License ML20210N9291999-08-0404 August 1999 Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1) ML20210E4941999-07-23023 July 1999 Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan ML20210C5011999-07-21021 July 1999 Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested ML20211N9101999-07-20020 July 1999 Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) ML20210C8461999-07-19019 July 1999 Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested ML20209J5171999-07-16016 July 1999 Forwards Comments from Accuracy Review of License Renewal Application SER ML20209C1391999-07-0202 July 1999 Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future ML20210D1531999-06-30030 June 1999 Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations ML20209B5781999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20210D1741999-06-24024 June 1999 Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info ML20196C4291999-06-21021 June 1999 Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes ML20195J6591999-06-16016 June 1999 Submits Proposed Alternative to Requirements of 10CFR50.55a(g)(4) (Automatic Compliance with Latest Approved Edition of ASME Code Every 120 Months).Proposal Will Apply Third ten-year ISI Interval,Scheduled to Begin 990701 ML20207F0201999-06-0101 June 1999 Forwards Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2, for NRC Review.Plan Satisfies Commitment Contained in Licensee to NRC 05000317/LER-1999-002, Requests That Cover Page for LER 99-002,dtd 990525,be Corrected to Indicate Rept Is Submitted Per Requirements of 10CFR20.2201(b)1999-05-28028 May 1999 Requests That Cover Page for LER 99-002,dtd 990525,be Corrected to Indicate Rept Is Submitted Per Requirements of 10CFR20.2201(b) ML20195B3751999-05-25025 May 1999 Forwards ECCS Codes & Methods Rept, as Required by 10CFR50.46(a)(3)(ii) ML20195B2521999-05-25025 May 1999 Submits Response to RAI Re LAR for Tube Repair Using Leak Limiting Alloy 800 Sleeves for Ccnpp,Units 1 & 2.Test Repts Encl ML20195B2271999-05-24024 May 1999 Forwards Certified Copy of Nuclear Liability Policy NF-216, Endorsement 128 ML20206U3051999-05-19019 May 1999 Submits Written Rept as Required follow-up to Verbal Rept Given to NRC Regional Administrator on 990419 of SG Tube Insps Conducted,Cause of Tube Degradation & Corrective Measures Taken as Result of Insp Findings ML20206U8281999-05-18018 May 1999 Forwards Missing Pages C-30,C-31,C-114 & C-115 from 990319 Response to NRC RAI, Wind Tunnel Modeling of Calvert Cliffs NPP Cpp Project 94-1040. Complete Copy of 1985 Rept, Wind Flows & Dispersion Conditions of Calvert Cliffs, Encl ML20212G9751999-05-12012 May 1999 Forwards Draft write-up Re OI 16 for F Grubelich to Consider ML20206K6921999-05-10010 May 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsements,In Compliance with 10CFR140.15(e).Without Encl ML20206K1711999-05-0707 May 1999 Informs That on 990430 Util Filed Encl Articles of Share Exchange with Maryland Dept of Assessments & Taxation to Form Holding Company,Constellation Energy Group,Inc (Ceg). CEG Is Parent Company of Bg&E ML20206C7521999-04-29029 April 1999 Provides Rept of Number of Tubes Plugged in Calvert Cliffs Unit 2 SGs During Recently Completed Isi,As Required by Calvert Cliffs Unit 1,TS 5.6.9.a ML20212G9891999-04-28028 April 1999 Forwards Current Draft Response to Ci 3.3.2.2-1 to Be Used as Example for OI Vs License Condition Vs Commitment Situation ML20206C7271999-04-28028 April 1999 Forwards Occupational Radiation Exposure Repts for 1998, as Required by Units 1 & 2 Tech Specs 5.6.1 & 6.1 of Isfsi. Repts Contain Tabulation of Number of Station,Util & Other Personnel Receiving Exposures Greater than 100 Mrem ML20206C7211999-04-27027 April 1999 Forwards Addl Info Which Is Being Made Available in Encl Licensed Operators Fitness for Duty Questionnaire.Encl Specifics of Personal Info Are Withheld,Per 10CFR2.790 ML20212G9851999-04-26026 April 1999 Provides Proposed Response to OI 4.1.3-1 for B Elliott to Consider ML20206U6691999-04-26026 April 1999 Advises That Documents Re Operation of Calvert Cliffs Nuclear Power Plant Should Be Addressed to Listed Natl Marine Fisheries Svc Office ML20205F8851999-04-0202 April 1999 Provides First Annual Amend to Bg&E License Renewal Application for Ccnpp,Units 1 & 2,as Required by 10CFR54 ML20205J0691999-04-0202 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20205G2971999-04-0101 April 1999 Requests That NRC Complete Review of Rev 0 to CENPD-396-P, Common Qualified Platform TR & Rev 0 to CE-CES-195-P, Software Program Manual for 'Common Q' Sys, by 990930 ML20205D7471999-03-30030 March 1999 Forwards Biennial Rept on Status of Decommissioning Funding, IAW 10CFR50.75(f)(1) ML20207G4391999-03-30030 March 1999 Responds to from Cl Miller,Requesting Assistance of FEMA in Addressing Concerns Received by NRC Involving Offsite Emergency Preparedness at Plant NPP ML20205C4091999-03-26026 March 1999 Submits Info Related to Scope,Risk Mgt & Summary of Risk for Performing Preventive Maintenance on P-13000-2 Unit Transformer Re License Amend 205 1999-09-28
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7471990-09-18018 September 1990 Discusses Response to Generic Ltr 88-17, Loss of Dhr. Development of Appropriate Tech Spec Changes for Reducing Cooling Flow Rate in Process.Changes Will Provide Increased Margin to Vortexing Conditions ML20059K1951990-09-18018 September 1990 Clarifies Auxiliary Feedwater Sys Commitments Concerning Ability of Sys to Prevent Total Loss of Feedwater Following Various Pipe Breaks & Component Failures ML20059H2811990-09-0707 September 1990 Forwards Rev 4 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program. Rev Creates Std Format for Action Plans Which States Scope, Deliverables & Overall Objectives of Action Plan ML20059F4761990-09-0707 September 1990 Forwards Rev 5 to Security Training & Qualification Plan.Rev Withheld ML20059H4241990-09-0707 September 1990 Forwards Performance Improvement Plan Implementation Program Schedule Status as of 900905 05000317/LER-1989-023, Advises That Licensee Plans to Complete Detailed Design for Automatic Isolation Sys Upgrade by 910401,per NRC Request for Schedule for Enhancement Implementation as Discussed in LER 89-23 Re Postulated Pipe Rupture1990-08-24024 August 1990 Advises That Licensee Plans to Complete Detailed Design for Automatic Isolation Sys Upgrade by 910401,per NRC Request for Schedule for Enhancement Implementation as Discussed in LER 89-23 Re Postulated Pipe Rupture ML20059B7481990-08-21021 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 ML20058Q2211990-08-14014 August 1990 Forwards Performance Improvement Plan Implementation Program Schedule Status as of 900807.Synopsis of Activities Since Last Update & Updated List of Key Action Plan Info Also Encl ML20058L8811990-08-0101 August 1990 Withdraws License Amend Request Changing Tech Spec Pages 3/4 25a & 25b, RCS Pressure-Temp Limitations. Change Would Have Revised Min Reactor Vessel Flange bolt-up Temp from 70 F to 90 F ML20058L7271990-08-0101 August 1990 Forwards Plant Performance Improvement Plan Implementation Program Schedule Status as of 900724 ML20058L2151990-07-27027 July 1990 Responds to NRC Re Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80.Corrective Action: Evaluation of Battery Charger Determined That Provisions Adequately Verify Requirements of Tech Spec 4.8.2.3.2 ML20055H9241990-07-26026 July 1990 Forwards Decommissioning Plan for Calvert Cliffs Isfsi ML20055G9981990-07-20020 July 1990 Responds to NRC Re Generic Implications & Resolution of Control Element Assembly Failure at Plant on 900607.New Control Element Assemblies Ordered.Addl Response Will Be Submitted at Least 60 Days Prior to Restart ML20044B0401990-07-13013 July 1990 Forwards Rev 3 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program. Brief Summary of Changes Listed ML20055E0801990-07-0303 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-317/90-08 & 50-318/90-08.Corrective Actions:Instruction CCI-309B Re Control of Locked Valve Revised to Clarify Required Documentation and Verification of Locked Valves ML19298E2271990-06-29029 June 1990 Confirms That Work Intended to Resolve Unresolved Items & Incorporate Improvement Suggestions Completed,Per Insp Repts 50-317/90-04 & 50-318/90-04 ML20055D0311990-06-25025 June 1990 Submits Corrections to Commitments Re Hydrogen Analyzer Sys. Under Worst Case Condition,Hydrogen Recombiners Would Be Started Prior to Hydrogen Concentration Inside Containment Reaching 3.0% Hydrogen ML20043G1771990-06-12012 June 1990 Forwards Monthly Operating Repts for May 1990 for Calvert Cliffs Nuclear Power Plant Units 1 & 2 & Revised Operating Rept for Apr 1990 for Calvert Cliffs Unit 1 ML20043G5931990-06-0808 June 1990 Requests one-time Exemption from Requirement of 10CFR50.71(e) to Allow 3-month Extension to Schedule for Submitting 1990 Rev to Updated Fsar,Per NRC 1989 QA Audit & Insp Repts 50-317/89-27 & 50-318/89-28 Noting Weaknesses ML20043F7101990-06-0606 June 1990 Suppls 900330 Response to Station Blackout Rule (10CFR50.63).Two Addl Class 1E Diesel Generators Added to Reduce Required Coping Duration.Required Coping Duration Is 4 H for One Unit ML20043D7281990-06-0404 June 1990 Responds to NRC 900404 Ltr Re Weaknessess Noted in Maint Team Insp Repts 50-317/90-80 & 50-318/90-80.Efforts to Clean,Insulate & Paint Plant Areas to Improve Cleanliness Being Undertaken ML20043C9051990-05-31031 May 1990 Notifies of Relocation of Ofcs,Effective 900604.New Addresses & Telephone Numbers Listed ML20043C5971990-05-29029 May 1990 Forwards Startup Review Board Self-Assessment Rept:Apr 1990 Unit 1 Startup. Based on Assessment,Mgt Efforts Taken Through Performance Improvement Plan Appears Substantially on Track ML20043B9341990-05-25025 May 1990 Advises of Licensee Progress to Date Re Unresolved Item Noted in Inps Repts 50-317/90-04 & 50-318/90-04 & Identify Slippage Past 900601 Target Date.Completion Date Extended to 900701 ML20043B4691990-05-21021 May 1990 Reaffirms Licensee Intention to Submit Rept Re Deletion of Tech Spec 3/4.6.1.8, Containment Sys - Containment Vent Sys, Upon Receiving Notification That Vent Valves 1(2)-MOV-6900 & 1(2)-MOV-6901 Established ML20043A3381990-05-15015 May 1990 Responds to NRC 900409 Ltr Re Violations Noted in Insp Repts 50-317/90-01 & 50-318/90-01.Corrective Actions:Detailed & Specific Directions for Radiography Will Be Incorporated in Radiography Procedures within NDE Program ML20043A3321990-05-14014 May 1990 Responds to SALP Rept Dtd 900404 Covering Util Performance During 1989.Feedback Mechanisms Established to Improve Training & 10CFR50.59 Screening Procedure & Training Revised ML20042G3751990-05-10010 May 1990 Forwards Changes 1-3 to Rev 0 to Program Plan for Second Insp Interval for Calvert Cliffs Nuclear Plant,Units 1 & 2. Plan Revised to Include Volumetric & Surface Exams of Class 2 Piping Welds in Containment Spray & Shutdown Cooling Sys ML20042G6141990-05-0505 May 1990 Requests Regional Temporary Waiver of Compliance to Provide Relief from Provision of Limiting Condition for Operation of Tech Spec 3.4.10.1, Structural Integrity of ASME Code Class 1,2 & 3 Sys. ML20042G4581990-05-0404 May 1990 Responds to Request for Addl Info Concerning Tech Spec Amend Re Emergency Diesel Generators.Preventive Maint Procedures Prepared on 900411 & Final Approval Will Be Completed After Issuance of Amend ML20042F5771990-05-0404 May 1990 Responds to NRC 900404 Ltr Re Violations Noted in Insp Repts 50-317/90-80 & 50-318/90-80.Corrective Actions:Surveillance Test Procedure M-538-1 Revised to Include Verification of Alarm Function & Alarm Testing Reviewed ML20042F0101990-04-30030 April 1990 Forwards Update of Tables 1C,2A,2B,3A & Page 7 of Semiannual Effluent Release Rept for Second Half of 1989 & Table 3A for Second Half of 1988 & First Half of 1989.Update Includes Strontium Results for Fourth Quarter for Gaseous Releases ML20042E8271990-04-30030 April 1990 Forwards Rev 2 to Calvert Cliffs Performance Improvement Plan Implementation Program. Accountability Improvements, Engineering Planning & Sys Circles Action Plans Completed. New Sections to Rev Listed ML20042F0391990-04-19019 April 1990 Submits Initial Response to SALP Rept Dtd 900404.Licensee Devoted Substantial Senior Mgt Attention & Resources to Improving Facility Performance & Committed to Continue Efforts to Attain High Stds of Safety & Quality ML20012F5511990-04-0606 April 1990 Responds to NRC 900306 Ltr Re Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Corrective Actions:Operating Procedures Changed to Prohibit Testing of ECCS When in Solid Water Condition ML20012F2991990-04-0404 April 1990 Revises Scheduled Completion Date for Implementation of Computerized Trending of Surveillance Test Data,In Response to Special Team Insp Repts 50-317/89-200 & 50-318/89-200 from 900601 to 901228 ML20042D8101990-03-30030 March 1990 Forwards Supplemental Info,Clarifying Util 890414 Response to Station Blackout Rule Noting That Util Followed NUMAR-87-00 Methodology ML20012F0211990-03-29029 March 1990 Responds to NRC 900227 Ltr Re Violations Noted in Insp Rept 50-317/89-25.Corrective Actions:Plugging Error Identified & Correct Tube Plugged & Corrective Action Procedures Revised ML20012D3111990-03-19019 March 1990 Provides Followup Response to Violation Noted in Insp Repts 50-317/89-24 & 50-318/89-24.Corrective Actions:Radiation Safety Technicians Responsible for Safety Procedures Trained in Jan 1990 & Radwaste Scaling Factors Approved on 900201 ML20012D1871990-03-16016 March 1990 Discusses Readiness for Restart of Facility ML20012B9121990-03-0909 March 1990 Withdraws 891113 Request for Relief from ASME Code Section XI Requirements ML20012B9221990-03-0909 March 1990 Responds to NRC 900207 Ltr Re Violations Noted in Insp Repts 50-317/89-27 & 50-318/89-28.Corrective Actions:Demineralized Water & Chemicals Added to Steam Generators to Restore Chemical Concentrations to Required Specs ML20012B6111990-03-0707 March 1990 Responds to NRC 900229 Ltr Re Violations Noted in Readiness Assessment Team Insp Rept 50-317/89-81.Corrective Actions: Memo Issued re-emphasizing Importance of Mgt Controls & General Supervisor Counselled ML20012D7271990-03-0505 March 1990 Responds to Violations Noted in Insp Repts 50-317/90-03 & 50-318/90-03 on 900108-12.Corrective Actions:Medical Svcs Tested All Members of Nuclear Security Force for Glaucoma & field-of-vision Requirements ML20011F4251990-03-0101 March 1990 Forwards Page 4-9 of Rev 25 to Security Plan,Originally Submitted on 900228.Encl Withheld (Ref 10CFR73.21) ML20011F4491990-02-28028 February 1990 Forwards 1989 Steam Generator Insp Results Rept.Rept Includes Number & Extent of Tubes Examined,Imperfections Noted & Identity of Tubes Plugged.No Steam Generator Tube Exams Conducted on Unit 1 During 1989 ML20012A1481990-02-28028 February 1990 Forwards Rev 25 to Security Plan & Details of Changes Made by Rev.Encls Withheld (Ref 10CFR73.21) ML20012A1531990-02-28028 February 1990 Forwards Rev 11 to Safeguards Contingency Plan & Details of Changes Made by Rev.Encls Withheld (Ref 10CFR73.21) ML20011F4141990-02-27027 February 1990 Forwards Rev 2 to, Evacuation Time Estimates within Plume Exposure Pathway EPZ for Calvert Cliffs Nuclear Power Plant. Evacuation Time Estimates Updated to Reflect Population & Road Network Changes Since 1981 ML20012A2331990-02-26026 February 1990 Advises That Erosion/Corrosion Program Controlling Implementing Procedure 5.05, Secondary Sys Piping Erosion/ Corrosion Insp Program, Fully Implemented on 891229 1990-09-07
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S ALTIMORE OAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE. MARYLAND 21203 JostPH A.TitmNAN WCt Pat $ tete,f NvC4 TAR (1,t hSt January 28, 1988 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 IE Bulletin 85-03, 'Atotor-Operated Valve Common hiode railures During Plant Transients Doe to Imoroner Switch Settines
REFERENCES:
(a) Letter from htr. J. A. Tiernan (BG&E) to Dr. T. E. Aturley (NRC),
dated hlay 15, 1986, same subject (b) Letter from htr. J. A. Tiernan (BG&E) to NRC Document Control Desk, dated September 1, 1987 Response to Request for Additional Information on IE Bulletin 85-03 Gentlemen:
This refers to IE Bulletin 85-03, item f, which requested a written report on completion of the subject program. Enclosure (1) prosides: (1) a s erification of completion of the sequested program; (2) a summary of the findings as to valse operability prior to any adjustments as a result of the subject bulletin; and (3) a summary of data in accordance with the suggested format. In conjunction with Reference (a), this letter prosides the information required by IE Bulletin 85 03.
Should you hase any further questions regarding this reply, we will be pleased to discuss them with you.
Very truly yours, 7.
{& ~
JAT/SRC/dtm [6l/
Enclosure '/
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Document Control Desk January 28,198F Page 2 cc: D. A. Brune, Esquire J. E, Silber g, Esquire R. A.Capra,NRC S. A.McNeil.NRC W. T. Russell, NRC D. C Trimble NRC R. J. Kiessel. NRC l
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ENCI.OSUR E (1)
FINAI, REPLY TO IE IlULI.ETIN 85-03 This letter provides the final information necessary to verify completion of all actions required by IE ilulletin 85 03. No hiotor-operated valses (htOVs) were found inoperable. Attachment A summarizes the data requested. The following notes apply to this data.
I. Test differential pressures (d/p) were the maximum obtainable in the test configuration (simulated accident condition). Full liigh Pressure Safety injection (llPSI) pump flow was directed into the Reactor Coolant System which was vented to the atmosphere, in fisc cases, the llPSI system was not capable of producing maximum design d/p (1310 psid sersus the 1313 psid required). For these cases the difference is considered insignificant.
- 2. The torque switch settings are explained in our response to Action item c. That is, the differences between test settings and final settings are discussed. No changes w ere required as a result of testing performed.
- 3. The Open To Close (*C') test d/p readings were taken with full flow and with valses fully open. Upon subsequent closing, the d/p's were measured and the maximum values were noted.
l The following discussion addresses each action item of IE Ilulletin 85-03 and our response. Additional information can be found in Reference (b) to the coser letter.
Asthn item x This item is complete. The results of this item were reported in Reference (a) and supplemented by Reference (c).
Acikn Item b:
A maintenance procedure exists at Cals ert Cliffs to control the set up, adjustment and testing of hlOV controls. This procedure includes torque switch, torque bypass switch and limit switch instructions. (Attachment !! provides the htOV Control Program at Cals ert Cliffs.) hiotor oserloads were established and controlled by electrical drawings. The initial switch settings and methods of control were established by the Architect / Engineer. This information w as prosided to Cah ert Cliffs in electrical drawings, control schemes and htOV Data Sheets. Ilecause of the procedures and documents as silable, the effort required for Action item b vonsisted primarily of serifying the sahdity cf historical switch settings listed in the htOV Data Sheets. This w as accomplished in house as follows: The required torque for each htOV w as determined using a method published by Limitorque in their htOY Selection Guides. Then we obtained from 1.imitorque correlations specific to the spring packs in>talled in our flulletin StOVs. These correlations related torque switch scale disisions (w hich are actui.ly a measure of spring pack deflection) to applied torque. Thus the required torque from l
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ENCI.OSUR E (1)
FINAL REPLY TO IE IlULLETIN 85-03 the calculation could be translated to a corresponding torque switch setting. A review of overloads had been conducted previously as recommended by IE Circular 81-13.
The calculational methodology was developed and the torque switch settings were derived in accordance with IE Bulletin 85-03. These newly derived settings were found to closely agree with the historical htOV Data Sheets' settings. No vai es were determined to be inoperable as a result of the calculations.
As11en item e-The htOVs subject to the requirements of the bulletin were tested at maximum d/p and full flow. These vah es were tested with 'as-found" switch settings. Additionally, the Unit One htOVs were tested at the reduced soltage of 432 solts (minimum 480-solt bus voltage allowed by Technical Specifications). All htOVs operated properly in both the open and shut directions. There were no obsersed problems.
No changes to the switch settings were required as a result of the testing, llowes er, as shown on Attachment A, some torque switch settings were changed. These were done to increase the conservatism in the settings. Some additional torque switch setting changes are planned just prior to the nest masimum d/p test. These changes will be made to standardire settings on similar htOVs in order to assist in long-term vah e i
performance trending.
Action Item d:
l As statd previously, the calculational method for determining torque switch settings j has been developed and procedures are in place to maintain torque switch, torque b> pass
, switch and limit switch settings, Some procedural enhancements were required to meet the intent of the bulletin, The control of torque switch settings for those htOVs subject to the requirements of the bulletin has been formalired. New procedures were I developed to perform masimum d/p testing of IE Dulletin 85 03 htOVs on a refueling inters al bails. We hase also developed post maintenance testing guidelines for the bulletin htOVs.
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ATTACIDtENT A ;
VAI11C VAIA*E OIUWIOR If/F PASIS A P TIFTA P T/S 0 *IIsr T/S FIIIAL W1PJD U T l ',k S B U Ent GR IE g g 9 C 9 9 9 g I!171616 V GL P 34657 2 1500 -0025 1700 38.6:1 IJV 1295 1295 1340 1090 1.0 2.25 1.5 1.5
- 1117/617 V GL P 34657 2 1500 -0025 1700 38.6:1 IlV 1295 1295 1320 1110 2.25 1.75 1.5 1.5
- I!17/626 V CL P 34657 2 1500 -0025 1700 38.6:1 IJV 1295 1295 1340 1060 2.0 2.25 1.5 1.5
- Ifty/627 V GL P 34657 2 1500 -0025 1700 38.6:1 I2V 1295 1295 1320 1070 1.5 1.75 1.5 1.75 11171636 V GL P 34657 2 1500 -0025 1700 38.6:1 IJV 1295 1295 1330 1080 2.5 2.5 1.5 1.5
- 1177/637 V GL P 34657 2 1500 -0025 1700 38.6:1 IlV 1295 2295 1310 1100 1.5 1.5 1.5 1.5 If17/646 V CL P 34657 2 1500 -0025 1700 38.6:1 Ilv 1294 1294 1330 1040 1.75 2.75 1.5 1.5
- If11/647 V CL P 34657 2 1500 -0025 1700 38.6:1 IJV 1294 1294 1310 1040 2.5 1.5 1.5 1.5
- I!11/653 V CA P 34658 4 900 -0025 1700 36.2:1 IDIV 1313 1313 1310 390 1.0 1.0 1.5 1.5 1117/654 V CA P 34653 6 900 -040 1700 35.4:1 TIV 1313 1313 1330 360 2.25 2.5 3.0 3.0
]!17/655 V CA P 34653 4 900 -0025 1700 36.2:1 IDIV 1313 1313 1310 350 1.0 1.0 1.5 1.5
]!)J/656 V CA P 34653 6 1500 -160 3405 35.4:1 TIV 1313 1313 1310 350 2.25 2.25 2.25 2.25 2117/616 V GL P 34657 2 1500 -0025 1700 38.6:1 IJV 1295 1295 1325 940 1.5 1.5 1.5 1.5 2117J617 V GL P 34657 2 1500 -0025 1700 38.6:1 LIV 1295 1295 1320 950 1.5 1.5 1.5 1.5 2ftJJ626 V GL P 34657 2 1500 -0025 1700 38.6:1 LIV 1295 1295 1325 1060 1.5 1.5 1.5 1.5 2fff/627 V GL P 34657 2 1500 -0025 1700 28.6:1 LIV 1295 1295 1320 1070 1.5 1.5 1.5 1.5 2737/636 V GL P 34657 2 1500 -0025 1700 38.6:1 LIV 1295 1295 1325 980 1.5 1.25 1.5 1.25 2!171637 V GL P 34657 2 1500 -0025 1700 38.6:1 LIV 1295 1295 1310 1090 1.5 1.5 1.5 1.5 21111646 V GL P 34657 2 1500 -0025 1700 38.6:1 LIV 1294 1294 1320 1205 1.0 2.0 1.5 1.5 2!1T/647 V CL P 34657 2 1500 -0025 1700 38.6: 1 IlV 1294 1294 l'10 1180 1.0 2.0 1.5 1.5 2fff/653 V CA P 34658 4 900 -0025 1700 36.2:1 IDIV 1313 1313 1325 350 1.5 1.5 1.5 1.5 2ftJ/654 V CA P 34653 6 900 -040 1700 35.4:1 TIV 1313 1313 1340 350 2.25 2.25 3.0 3.0 2!)JJ655 V CA P 34653 4 900 -0025 1700 36.2:1 IDIV 1313 1313 1310 310 1.5 1.5 1.5 1.5 221J/656 V cA P 34653 6 1500 -160 1720 35.4:1 T1v 1313 1313 1310 305 2.25 2.25 2.25 2.25 VALVE VALVE _0111%70R J7.T JTUTAP T/S_EIIIAL
!! = IVJUFACIURIR !! = JVJUFI.CIURIR 17.T = IXBIGi VAI1/E FUf3CTIQI O = CImED *I0 OPDT T/S = 'IOPQUE SUTICI V = VEIIJI IJL NtB LIIII*IUpr.3TE IJV = imp ISOIATIQi VALVE C = OPDI 'ID CImE O = 01111 T = TIIE 12m - IDIV = imp Da#GIRF1Ji ALL PRESSUIC III ISIG. C = CIME CL = GIDIE RIt! = 117IOR ISOIATIGI VALVE VAIA'E CimIIC ITESURES * = T/S 'ID IE CA = CATE Qt = GF1J1 PATIO TIV = 'Il%III ISOLATIGI VALVE IJE WrI11 FILM. AI1RUIID JUST S = SIZE III IIK3ff5 ALL VALVES IJE III 'IIIE IIIGI IRIOR *ID IID~r R = IFIf 7Jr/ PATI!C 11I Im. IMJIE SAFEI*I IJUECTIGI SYSTD1 APW ICL = ff]OEL 4
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A1TACllMENT Il CALVERTCLIFFS IE 11ULLETIN 85 03 MOTOR-OPERATED VALVE PROG RAM I. Method of MOV Control With a few exceptions, the normal industry practice is to seat the salve on action of the torque switch and to back seat the valve on action of the electrical limit switch. The rationale for this practice is to ensure tight l seating of the valve and a positive stop of the cperator on the back seat since i the back seat is the weakest mechanical part of the salve. This requires precise I torque switch and torque bypass switch setting determination and control. The consequences of inadequate torque switch and bypass switch settings are great.
Industry experience indicates that the itading causes of vahe fa.ilure er inoperability is the mis-adjustment or failure of the torque switch or its components. The torque switch is a spring centeled and balanced G vice. its ability to stay balanced and in adjustment is suspect. It is not a direct acting device, but depends upon the proper actions and calkration of the spring pack l The spring pack depends upon the proper grease and gap in the spring pack cavity and the suppression of hydraulic lock-up in the cevity. If the torque switch or i any of its components fail or are out of adjustment, or are installed I incorrectly, the resulting failure mode could be bent or broken s alve stems, burned out motors, valve seat damage, failures to operate, etc.
The Cahert Cliffs method of control substantially reduces these concerns because the torque switch is relegated to essentially a backup role for both opening and closing. The electrical limit switches are used as the primary control device for closing as well as opening. The limit switch is a less complex and a more positive acting device as it is directly geared to motor-operated drhe gests.
It does not depend on a spring pack. With vahe seating controlled by a limit switch, there is less wear on valv: and motor operated components because less force is being absorbed by the salve seat, valve stem, and operator gears. Also, because the sabe is not being ' torqued
- shut, less force is required to reopen the vahe.
The ditads antage of limit switch seating is that seat tightness may not be as uniform as with torque switch control. A ho, 'coastdown" of operator con.ponents must be allowed for. On closin g, the 'coastdow n' accomplishes the final seating after the limit switch stops the motor. On opening, 'coas tdo wn' has to be compensated for to present excesshe back seating. These disadsantages are os ercome by proper post adjustment operational checks. If a limit switch fails to operate (opening or clos.'g), then the torque switch will act to present vahe/ operator damage, The torque switch is also acthe during operation between i the open and close limits because of two train geared limit switches (i.e., limit I switch and torque L> pass switch operation occur simultaneously). This provides protection against binding and/or motor damage during trasel between the open and close limits.
At Cah ert Cliffs, litnit switch control has prosen to be a s alid method of control which has resulted in a good MOV operational history.
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ATTACitMENT B CALVERTCLIFF5 IE BULLETIN 85-03 MOTOR-OPERATED VALVE PROG RAM
- 11. Procedures for MOVs The Calvert Cliffs program consists of maintenance procedures, functional test procedures, preventive maintenance procedures, and operational procedures as follows:
- Maintenance Procedures: detailed disassembly /re-assembly instructions for various size motor operators.
- Functional Test Procedures: Contains instructions for limit switch, torque switch, tnd enrque bypass inspection and adjustment; ele:trical checks;.
post switch adjustment operational checks; motor current data; stroke timies; gives guidelines for post maintenance testing.
Preventive Maintenance Procedurer Mechanleal - Lubrication of operator; Electrical - Inspections, integrity checks, insulation resistance measurements.
- Operational Procedures: Full flow maximum differential pressure testing; stroke timing; neotor current data.
Ill. Post Mainsenance Testing of MOVs Written guidance is provided to ensure proper post maintenance testing is performed. This guidance specifies increasing levels of post maintensnee testing for a correspondingly increasing complexity of maintenance performed.
IV. Summary l The Calvert Cliffs program for IE Bulletin 85-0) MOVs combines limit switch l control with full differential pressure testing (on a refueling interval basis)
J to ensure MOV operability. The method of control has proven to proside reliable j MOV operation and has limited the maintenance required due to degradation of l
operators components. Full differential pressure testing of this bulletin's MOVs l under "as-found* conditions also serified the validity of this program.
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