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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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BALTitAORC OAS AND
,ELECTRI CH ARLES CENTER . P, O. BOX 1475 + BALTIMOR E, MARYLAND 21203 Gtomat C CRttL Vic t Pat stDEwt th/catan Costmov March 7,1990 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATI'ENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Readiness Assessment Team Insnection
REFERENCES:
(a) Letter from Mr. William F. Kane (NRC) to Mr. G. C. Creel (BG&E), dated January 29, 1990, NRC Region i Inspection Report No. 50-317/89 Readiness Assessment Team inspection (b) Letter from Mr. G. V. McGowrin (BG&E) to Mr. J. M. Taylor (NRC), dated July 31, 1989, Performance Improvement Plan implementation Program Gentlemen:
The Baltimore Gas and Electric Company (BG&E) has thoroughly reviewed the Readiness Assessment Team inspection (RATI) report (Reference a), in the report, the Team concluded that improvements had been found in all areas within its scope of review.
The Team also found that overall performance at Calvert Cliffs Nuclear Power Plant was at a, level to provide adequate assurance of safe operation with the exception of one majorL area. The exception. Safety Tagging, has . been re-evaluated by BG&E and aggressive and comprehensive actions were taken to identify and correct the weaknesses and their root causes. Corrective actions included a review of the Calvert Cliffs Performance improvement Plan implementation Program (Reference b) to ensure actions being taken would effectively prevent recurrence of this type of problem. Safety Tagging is discussed in Attachment (1).
We are also taking action to provide additional assurance that corrective action programs will continue to function effectively during operation following plant restart. Corrective action - programs are discussed in Attachment (2).
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90031AD0 PDR O
04bo ,0030, K 05000317 PDC
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. March 7,1990 Page 2 j Should you have any further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, J
l GCC/LSL/RHB/bjd Attachments /
4- ,
cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A.Capra, NRC D. G. Mcdonald, Jr., NRC .
W. T. Russell, NRC !
L. E. Nicholson, NRC I
T. Magette, DNR 1
9
o A1TACHMENT f t)
BAL*I1MORE G AS AND ELECTRICCOMPANY RESPONSE 10 INSPECrlON REPORT 50-317/89-g1 SAFETY TAGGING j Significant improvements in the conduct of safety tagging at Cahert Cliffs have been completed within the past year as a result of corrective actions to past esents and near misses, most notably in the Spring of 1989. The November 1989 NRC Readiness Assessment Team Inspection (RATI) recognized these improvements and determined that tagouts were being properly researched, designed, approved, and installed. There were, however, weaknesses in program administration, self-assessment and management oversight. Symptomatic of these weaknesses were the failure to incorporate results of '
safety tagging audits into the corrective action system, and the failure to ensure that all monthly audits were completed in a timely manner. Another concern was the ,
apparently insufficient examination of safety tagging activities during the internal l restart verification process, which failed to recognize the lack of effective performance monitoring and management oversight.
The safety tagging process and the specific concerns of the Inspection Team have been i evaluated. Discussions of the specific concerns follow:
l
- l. Reasons for Weaknesses in the Safety Tagging Program:
The Safety Tagging Supervisor (STS) recognized that tag audits subsequent to !
the August 1989 audit would require considerable resources due to the large number of tagouts. After reflecting on the purpose of the audit and discussing ,
the problem with the Supervisor-Operations and Maintenance Coordination (OMC),
the STS drafted a change to the safety tagging procedure that reduced the 3 requirement for tag audits to once per quarter. This procedure change was ;
postponed several times to allow incorporation of comments. Since previous tag audits had not identified significant safety or procedural concerns and the STS assumed the audit frequency would be changed, the STS believed allowing the audit completion to slip was acceptable.
The STS did not inform higher level supervision about overdue audits because !
he rationalized that the proposed change to a quarterly frequency supported the delays in audit completion. Also, he did not believe another monthly audit during this time frame would make significant additional contributions to safety.
The General Supervisor did not inquire about the Tag audit status, results, or documentation, This was due to insufficient attention to detail on his part and to a 1989 reorganization which removed a key second-line supervisor from the safety tagging organization, which reduced supervisory attention to safety tagging. This supervisory position has since been reinstated.
Contributing to these errors was a failure by the General Supervisor to make clear to the STS management expectations consistent with our " Mutual Obligations" for the conduct of business in the safety tagging area.
Specifically, this pertained to the obligations dealing with following
-1
ATTACHMENT f1)
HALTIMORE G AS AND ELECTRICCOMPANY RESPONSE TO INSPECTION REPORT 50-31*//89-81 SAFETY TAGGING procedures, identifying problems, and providing the resources to do the job right. The
- Mutual Obligations" at Calvert Cliffs Nuclear Power Plant are o Problems must be identified, o A questioning attitude is an important part of safety. >
o When in doubt, proceed conservatively.
o Procedures and safety practices must be followed.
o Resources will be provided to do the job right. ,
o Do the job right the first time, o Pay attention to detail.
The same lack of clear management expectations was the primary cause for instances where the Safety Tagging Supervisor resolved some tagging discrepancies using informal methods instead of formal corrective action programs.
- 2. Reasons Self-Assessment Failed to Identify Safety Tagging Weaknesses The November 1989 RATI followed major initiatives which resulted in significant improvements in the safety tagging process. Deliberate action had been taken to identify the causes of earlier safety tagging weaknesses and correct them. This effort achieved a major improvement in the overall safety tagging process, yet the management controls associated with safety tagging did l not receive the same level of scrutiny as other parts of the program. The safety tagging $ ogram contained provisions for audits but these kinds of management codwols were not a significant factor in the safety tagging weaknesses experienced at the time. Therefore, they were not identified as an area of concern. The root cause analysis was incomplete in this respect.
Prior to the November 1989 RATI, a Restart Commitment Verification Team (RCVT) was charged with performing an overall and in-depth process evaluation.
As with most evaluation processes, the team relied on sampling to achieve reasonable assurance that the desired improvements had been obtained and placed into practice, and that controls and procedures were properly followed. At the I time the RCVT performed its evaluation, the tagging audits were being l completed on time.
The Quality Assurance (QA) Surveillance of safety tagging performed just prior to the RATI concentrated on the corrective actions taken in response to the l Confirmatory Action Letter. Again, the focus was on the major initiatives taken
!- to improve the adequacy of safety tagging which did not include management I controls such as tag audits.
l l As discussed earlier, problems identified during tag audits and the overdue audits were not elevated to the appropriate level of supervision for resolution in part due to the General Supervisor's failure to adequately convey management expectations to the Safety Tagging Supervisor.
2
A~tTACHMENT (1) l BALTIMOREG AS AND ELECTRICCOMPANY ,
RESPONSE TO INSPECTION REPORT 50-317/89-81 i i
SAFL'TY TAGGING Finally, problems, such as errors on laminated prints used as operator aids and staffing / resource tevels, were brought to management's attention but were still under review and not yet resolved at the time of the RATI.
- 3. Root Causes and Corrective Actions for Weaknesses in Safety Tagging: ,
A team was assembled to perform a special assessment of the weaknesses in safety l tagging and the restart verification process. The team identified two root '
l causes for the weaknesses discovered in the November 1989 NRC Readiness Assessment Team inspection:
- a. Insufficient shared expectations; and,
- b. Insufficient vertical communications.
SilORT TERM CORRECTIVE ACTIONS
- 1. The Manager-Calvert Cliffs Nuclear Power Plant Department (CCNPPD) issued a memorandum which re-emphasized the importance of management controls, specifically referring to the weaknesses discovered in the RATI. He then met with his General Supervisors and the Nuclear Maintenance Superintendent to clearly communicate his expectations regarding management controls and to inform-them that this issue is to be addressed in their 1990 performance objectives.
The General Supervisor-Nuclear Operations was counselled about the need to make his expectations clear regarding the importance of safety and quality. '
- 2. The recently created position of Assistant General Supervisor-Operations Support (AGS-OS) is now an integral part of the communications and management controls processes.
- 3. Concurrent with the irit.'rnal assessment conducted to analyze the NRC identified weaknesses, the General Supervisor-Nuclear Operations (GS-NO) took the following actions to ensure effective self-assessment of the Safety Ta; sag Program:
- a. All Safety Taggers in the Safety Tagging Unit reviewed the safety tagging procedure, provided suggestions to clarify it, and certified that it is being complied with. In addition, the GS-NO and the AGS-OS met with safety tagging personnel to re-emphasize expectations (including full compliance with administrative procedures) and to improve vertical communications. ,
- b. Approximstely 25 ' Operations Supervisory Job Observations", a Quality Control observation, and a QA surveillance were conducted to examine the tagging procats, identify potential concerns, and make ecommendations.
The administrative discrepancies identified were documented and are being resolved.
3
.- i ATTACHMENT (1) l BALTIMORE GAS AND ELECTRICCOMPANY ,
RESPONSE TO INSPECrlON REPORT 50-317/89-81 SAFETY TAGGING i
- c. The monthly Safety Tag Audit is now scheduled and tracked in accordance ,
with CCI-303,
- Operations Performance Evaluation Program", to ensure timely completion. The results of each Safety Tag Audit are now reported to higher level supervision. Significant discrepancies are documented on l Nonconformance Reports. i
- d. Safety meetings covering safety tag audit discrepancies were conducted to improve communication of management's expectations, s
- c. A number of improvements to the safety tagging procedure were identified and a change to this procedure has been approved,
- f. The use of laminated drawings as operator aids was discontinued because it proved to be ineffective.
- 4. The Manager-CCNPPD in a memorandum to the Safety Tagging Supervisor, reaffirmed the Safety Tagging Unit's primary responsibility toward safety of personnel and plant equipment, and directed him to frequently re-emphasize this priority to
- j. his personnel.
1 l LONG TERM CORRECTIVE ACrlONS AND MEASURES OF SUCCFM 1
- 1. An evaluation will be performed to assess computer linking the Control Room Operator. Shift Supervisor, Control Room Supervisor, Safety Tagging Authority, and the Operations Maintenance Coordinator. This information link may provide more consistent communication of outage schedule information, system and i equipment tagging and maintenance status, etc. This evaluation and resulting improvements will be implemented under Action Plan 3.6.3, Operations Improvement Plan which will be included in Revision I to the Performance improvement Plan Implementation Program (PIP-IP).
- 2. As discussed previonsly, there are two root causes to the weaknesses in safety tagging which could have guic implications:
- a. Insufficient Shared Expectations: This root cause correlates to Performance Improvement Plan-Implementation Program (PIP-IP) Root Cause l #1, insufficient Expectations and Performance Standards.
This root cause is addressed by PIP-IP Action Plans: Management !
Expectations; Performance Standards; Procedures Upgrade Program; Procurement Program Project, and Records Management / Document Control.
More specifically, the Wxedures Upgrade Program mandates the use of administrative procedures and contains a schedule for their systematic upgrade.
l
{. .
ATTACHMENT (1)
BALTIMOREGAS AND ELECTRICCOMPANY RESPONSE *ID INSPECTION REPORT 50-317/89-81 SAFETY TAGGING Improvements being implemented by the Action Plan for Site Integrated Scheduling (included as Action Plan 3.6.1 in Revision I of the PIP-IP) will improve scheduling deficiencies. These improvements will lead to better work control and more reliable schedules. This should lessen the likelihood of unanticipated schedule pressures which contributed to the weaknesses in safety tagging.
New Action Plans for Maintenance Work Control (Action Plan 3.6.2) and for Operations improvement, are included in PIP-IP Revision 1, and will provide improvements in the work flow process and foster bettu cooperation between work groups.
Additionally, clear expectations regarding management's commitment to the
" Mutual Obligations" will be the subject of a series of supervisor -
employee " Focus Meetings" in the first quarter of 1990.
- b. Insufficient Vertical Communications: This root cause corresponds closely to PIP-IP Root Cause #3, Insufficient Vertical and llorizontal Communications.
This root cause is addressed in a number of PIP-IP Action Plans.
Collectively, these Action Plans will serve to assure that important '
information is shared both horizontally at the working level and vertically between workers and appropriate levels of supervision and management.
The success of these Performance Improvement Plan initiative. at correcting the causes a of the weaknesses identified by the RATI will be measured by: '
- Surveys of people involved in the process to determine whetku " Mutual Obilgations" are being met:
- QA audits and surveillances of the safety tagging process;
- Supervisory Job Observations of safety tagging;
- Communications " tailgate" meetings; and,
- Performance Improvement Plan verificatio.1 techniques involving implementation, feedback, and effectiveness verifications.
We believe that the re-assessment of safety tagging and the corrective actions described above provide a high degree of assurance that the weaknesses in safety tagging have been corrected.
i i
]
I ATTACHMENT D) l BALTIMORE G AS AND ELECTRICCOMPANY l RESPONSE TO INSPECTION REPORT $0-317/89-81 l l
CORRECTIVE ACTION PROGR AMS l l
I BACKGROUND ]
i The Readiness Assessment Team inspection (RATI) noted that Calvert Cliffs Nuclear !
Power Plant uses a number of specialized corrective action programs. It was noted that these systems were for the most part functioning acceptably. The Team was also confident of the comprehensiveness of the current restart list because of the aggressive management attention, llowever, the team was concerned that:
o The number of corrective action systems would result in inconsistem.ies in the prioritizing, tracking, and management review of deficiencies during routine operation; and, o The interactions between these systems were not well defined and were subject to interpretation.
The Baltimore Gas und Electric Company was requested to provide additional measures of assurance that deficiencies identified during routine operation will be properly classified, prioritized, and tracked to assure effective corree:ive actions are completed on a schedule commensurate with safety significance.
CURRENT PROCESSES IIistorically, Calvert Cliffs has utilized a number of distinct corrective action systems to identify and track significant issues. Components of this process include:
o Nonconformance Reports (NCR) o Maintenance Orders (MO) o Quality Assurance (QA) Findings o Licensee Event Reports o Calvert Cliffs Instruction (CCI- 418) (Nuclear Operations Section Initiated - Reporting Requirements) Reports o Calvert Cliffs Event Reports (CCER) o Plant Operations and Safety Review Committee (POSRC) presentations o POSRC member concerns o Plant Operating Experience Assessment Committee (POEAC) concerns o Off Site Safety Review Committee (OSSRC) concerns o Interdepartmental Safety Committee (ISC) concerns o Line organization concerns The POSRC has served as a focal point for screening issues potentially affecting the safety of plant operations and making recommendations to the Plant Manager. Line supervision screened other issues and made appropriate recommendations, Critical examination of this process has revealed a number of areas for improvements.
l
- l. ,.
, i ATTACHMENT f2) )
)
BALTIMORE G AS AND ELECTRICCOMPANY RESPONSE TO INSPECrlON REPORT $0-317/89-81 CORRECTIVE ACrlON PROGRAMS a
NEAR-TERM IMPROVEMENTS A Significant issue Management System (SIMS) is being developed building on the components of the existing corrective actions systems which, as noted earlier, are ;
performing acceptably. The Manager-Calvert Cliffs Nuclear Power Plant Department (CCNPPD) is the sponsor of this system, lie will receive recommendations for placing items on the Plant Manager's Significant issues List from the POSRC, Operations Coordinator, Interdepartmental Safety Committee, Work Management Maintenance Committee, and the Director-Nuclear Regulatory Matters. Items placed on the list will i be tracked until they are satisfactorily resolved.
The Manager-CCNPPD will authorize additions, deletions, and changes of estimated completion dates for all items on his Significant Issues List, lie will ensure that the list is maintained current, published periodically, and that delinquent items are brought to the prompt attention of the appropriate department manager. Issues not selected for inclusion on the Plant Managers Significant Issues List will be prioritized, tracked, and resolved within the responsible organization. Our Commitment Management System will facilitate this process, The POSRC will continue to serve as the focal point for reviewing nuclear safety issues and will make recommendations to the Plant Manager for additions to his Significant issues List. To fulfill this role, POSRC will review candidate issues from the existing corrective action systems as described below. Since not all QA Findings, NCRs and POEAC concerns are reviewed by POSRC, screening criteria will be developed to define the threshold for presentation to POSRC and ensure correct and corisistent presentation of appropriate items.
1, Nonconformance Reports Quality Engineering conservatively screens all NCRs to determine if the nonconforming condition could be mode restraining. These NCRs are presented to the Manager-CCNPPD for additional consideration. Safety significant issues identifi2d in the process are presented to the POSRC. .
- 2. Indeoendent S1fety Evaluation Unit (ISEU)
The ISEU performs detailed reviews of plant events and trends plant operating experience. Adverse trends in plant operating experience are documented on NCRs which are screened and reviewed as described above. Recommendations from plant event investigations are reviewed and presented to POSRC if considered safety significant.
- 3. Ouality Assurance 626) Findines QA Findings are currently screened by the Supervisor-Quality Audits. QA Findings that affect nuclear safety, public safety or equipment operability (Level 1 Findings) are presented to the POSRC.
ATTACHMENT Q) 1 l
BALTIMORE G AS AND ELECTRICCOMPANY i RESPONSE TO INSPECrlON REPORT $0-?!?/89-81 l CORRECTIYE ACTIQNf_ROGRAMS I
, i
- 4. Licensee Event Reports (LERs)
All LERs are reviewed by the POSRC.
- 5. CCI-i l 8 (Checklist for Timelv Notification) Forms '
All CCl- f l 8 (Checklist for Timely Notification) forms are screened reportability.by the The Director-Nuclear Regulatory Matters (D-NRM) to assess Nuclear resulting LERs are reviewed by POSRC as stated above. CCI-I l 8, Operations Section Initiated Reporting Requirements, has been revised to require generation of NCRs in addition to initiation of the CCI-l l 8 form. The resulting NCRs will be screened and reviewed as described in #1 above.
(CCERs)
- 6. Calvert Cliffs Event Reoorts All CCERs are currently reviewed by POSRC.
7.
Plant Operations and Safety Review Committee (POSRC) Presentations '
Safety concerns raised during routine presentations to POSRC may result in recommendations to the Manager-CCNPPD.
- 8. POSRC MemberConcerns Discussion of potential safety concerns is an agenda item during all regularly scheduled POSRC meetings. Concerns raised by the members may result in recommendations to the Manager-CCNPPD.
- 9. Plant Oncratine Exoerience Assessment Committee (POEAC)
The POEAC functions as a subcommittee of the POSRC to perform review INPO of the nuclear power plants. This includes operating experience of other regularly reports Experience Reports. The POEAC Significant Operating significant issues and recommendations to the POSRC. POSRC reviews all POEAC meeting minutes. .
- 10. Off Site Safety Review Committee (OSSRC) !
The OSSRC can remand a shfety concern to the POSRC for further investigation or review.
I 1. 11uman Performance Evaluation System (IIPES) plant events investigations into The llPES Coordinator performs detailed involving human error. The results of all llPES investigations are given directly to the Manager-CCNPPD.
The Operations Maintenance Coordinator (OMC) is responsible for reviewing which and maintenance prioritizing all maintenance requests. Ile will recommend Manager's Significant Issues List, lie will deficiencies should be placed on the Plant also determine which maintenance orders should be followed up with an NCR.
+
ATTACHMENT (2)
BALTIMORE GAS AND ELECTAICCOMPANY RESPONSE TO INSPECrlON REPORT 50-317/89-81 CORRECTIVE ACrlON PROGRAMS The interdepartmental Safety Committee (ISC) is responsible for making recommendations on issues which affect personnel safety. The ISC Chairman will recommend which of these issues should be placed on the Plant Manager's Significant issues List.
The Work Management Committee (WMC) is responsible for recommending priorities for all Facility Change Requests (FCRs). The committee Chairman will be responsible for recommending which hardware modifications should be placed on the Plant Manager's Significant issues List.
The Director-Nuclear Regulatory Matters (D-NRM) is responsible for the review of NRC Reports, Bulletins, and Generic Letters to identify significant regulatory issues l
and commitments, lie will recommend which of these issues should be placed en the Plant Manager's Significant issues List.
Specific screening criteria will be developed to assure that the OMC, ISC, WMC and D-NRM employ consistent thresholds for their selection of items to be recommended for inclusion on the Plant Manager's Significant Issues List.
LONG TERM IMPROVEMENTE As stated above, a Significant issue Management System (SIMS) is under development.
l The major components of SIMS are in place and performing adequately at this time.
They provide assurance that problems are properly documented, prioritized, reviewed by management, and corrected on a schedule commensurate with their safety significance.
Our intent is to continue the development of SIMS, including the formalization of screening criteria and proceduralization of interfaces to enhance the effectiveness of SIMS.
An advanced issue management system is also under development. It will build on the
- Problem Report" concept and will provide a single document approach to the identification and documentation of deficiencies d!y:evered at Calvert Cliffs. This
- single document will be screened using approved criteria to assure that questions of l operability, reportability, and safety significance are promptly and consistently l addressed. This system will replace SIMS on a schedule which allows for a smooth transition between systems.
A preliminary Action Plan for this advanced issue management system will be included in Revision I to the Performance Improvement Plan-Implementation Program (PIP-IP). A fully developed plan and schedule will be included in Revision 2 of the PIP-IP which is planned for April 30, 1990.
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