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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:NRC TO UTILITY
MONTHYEARML20062G6791990-11-21021 November 1990 Forwards SE Determining That Load Profile Used During Surveillance Test Procedures Meets Requirement of Tech Spec 4.8.2.3.2.e,per Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80 IR 05000317/19900281990-11-14014 November 1990 Discusses 901102 Enforcement Conference Re Insp Repts 50-317/90-28 & 50-318/90-28 Covering Security Event ML20216K1541990-11-13013 November 1990 Forwards Safety Insp Repts 50-317/90-31 & 50-318/90-31 on 901029-1102.No Violations Noted ML20217A0131990-11-0909 November 1990 Forwards Insp Repts 50-317/90-25 & 50-318/90-25 on 900916-1020.One Noncited Violation Noted ML20058E9821990-11-0101 November 1990 Forwards List of Unimplemented Generic Safety Issues at Plant,Per Util 900627 Response to Generic Ltr 90-04 ML20058A7001990-10-19019 October 1990 Forwards Safeguards Insp Repts 50-317/90-28 & 50-318/90-28 on 901010 & 11.Violation Noted ML20058A6841990-10-17017 October 1990 Forwards Insp Repts 50-317/90-23 & 50-318/90-23 on 900812- 0915.No Violations Noted ML20062B2041990-10-12012 October 1990 Advises of Acceptance of 900924 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28, Item 2.2,Part 2 Vendor Interface for Safety-Related Components ML20059N9421990-10-12012 October 1990 Advises of Resolution of Auxiliary Feedwater Issue,Per .Issue Concerns Ability of AFW Sys to Provide Flow to Steam Generators Following Pipe Break IR 05000317/19900081990-10-11011 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/90-08 & 50-318/90-08 ML20059N5781990-10-0909 October 1990 Advises That Util 900510 Submittal of Revised Section of Inservice Insp Program Plan Addressed Provisions of Safety Evaluation ML20062B8361990-10-0909 October 1990 Forwards Special Team Insp Rept 50-317/90-24 on 900904-07 Re 900830 Reactor Vessel Water Level Anomaly ML20059N2231990-10-0101 October 1990 Forwards Safety Evaluation Accepting Proposed Actions Re Potential Design Deficiency,Per LER 89-023 ML20059N1181990-09-28028 September 1990 Forwards Safety Insp Repts 50-317/90-22 & 50-318/90-21 on 900827-31.No Violations Noted.Post Maint Testing Program Assessed to Be Comprehensive,Well Implemented & Met Objectives of Performance Improvement Program ML20059M7751990-09-27027 September 1990 Advises That NRC Approved Request for Relief from ASME Code Section XI Re Reactor Coolant Charging Pumps in ML20059K7041990-09-0707 September 1990 Ack Receipt of Util 900515 Response to Violations Noted in Insp Repts 50-317/90-01 & 50-318/90-01.Agrees That Thrust of Notice of Violation Not Accurate But That Actual Violation Was Failure to Comply w/10CFR50,App B,Criterion Xvi ML20059E3371990-08-27027 August 1990 Forwards Insp Repts 50-317/90-17 & 50-318/90-15 on 900710-13.No Violations Noted.Util Requested to Provide Complete Corrective Actions Being Considered to Prevent Recurrence of Welding Deficiencies within 30 Days ML20059E1921990-08-24024 August 1990 Forwards Insp Repts 50-317/90-18 & 50-318/90-17 on 900716-20.No Violations Noted ML20059E2981990-08-23023 August 1990 Advises That 890313,1103 & 900228 Revs 9,10 & 11 to Plant Contingency Plan,Consistent w/10CFR50.54 & Acceptable.Revs Withheld (Ref 10CFR73.21) ML20058N3641990-08-0909 August 1990 Forwards Notice of Withdrawal of 900801 Applications for Amend to License DPR-69 Re Shift of Min Pressurization Temp Between 530 & 20 Psia on Heatup & Cooldown Curves ML20058P1331990-08-0808 August 1990 Forwards Radiation Safety Insp Repts 50-317/90-14 & 50-318/90-12 on 900625-29.No Violations Noted ML20058N0481990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Should Provide for Sharing of Info & Experiences Involving Engineering Initiatives & Solutions of Problems Common to All ML20056A4081990-07-24024 July 1990 Forwards Insp Repts 50-317/90-12 & 50-318/90-11 on 900604-08.No Violations Noted ML20055G5951990-07-18018 July 1990 Corrected Cover Ltr Forwarding Insp Repts 50-317/90-10 & 50-318/90-10 ML20055G5931990-07-18018 July 1990 Forwards Corrected Cover Ltr for Insp Repts 50-317/90-10 & 50-318/90-10,revising Insp Rept Numbers ML20055H1211990-07-18018 July 1990 Advises That Encl Review of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Inadequate.Insufficient Bases Provided to Conclude That Power Surge Line Meets Code Limits for 40-yr Plant Life ML20055F9561990-07-17017 July 1990 Advises That Actions Re NRC Bulletin 87-002, Fastener Testing to Determine Conformance W/Applicable Matl Specs, Adequate,Per Insp Repts 50-317/90-08 & 50-318/90-08 ML20055F9241990-07-17017 July 1990 Informs That All Activities Re Reactor Vessel Level Monitoring Sys & Core Exit Thermocouples Completed Except for Tech Specs Based on Review of 870501 & 880427 Submittals ML20055G1331990-07-12012 July 1990 Forwards Insp Repts 50-317/90-13 & 50-318/90-13 on 900603-30.No Violations Observed ML20055F5421990-07-10010 July 1990 Advises That Requalification Program Evaluation Scheduled for Wk of 901022.Facility Requested to Furnish Approved Items Listed in Encl 1, Ref Matl Requirements in Order for Examiners to Adequately Prepare for Visit ML20055E5311990-07-0606 July 1990 Forwards Request for Addl Info Re Facility Control Assembly Action Program,Per 900607 Control Element Assembly Failure at Maine Yankee.Confirmation of NRC Understanding That Util Intends to Implement C-E Plan Also Requested ML20055E9081990-07-0202 July 1990 Forwards Exam Repts 50-317/90-07OL & 50-318/90-07OL on 900507-10 ML20055J3181990-06-29029 June 1990 Forwards Insp Repts 50-317/90-10 & 50-318/90-10 on 900604-08.No Violations Noted ML20055D0731990-06-27027 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 901029.Ref Matls,Listed on Encl,Should Be Provided by 900829 IR 05000317/19900041990-06-14014 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/90-04 & 50-318/90-04.Also Ack Schedular Slippage from 900601 to 0701 for Resolution of Unresolved Items ML20059M8351990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248E9161989-10-12012 October 1989 Advises That Licensing Activities Associated W/Nrc Bulletin 88-004,considered Complete ML20248D3591989-09-25025 September 1989 Forwards Amend 10 to Indemnity Agreement B-70,reflecting Changes to 10CFR140,effective 890701 IR 05000317/19890191989-09-22022 September 1989 Forwards Safety Insp Repts 50-317/89-19 & 50-318/89-20 on 890807-11.No Violations Noted ML20247Q2781989-09-21021 September 1989 Forwards Safety Insp Repts 50-317/89-21 & 50-318/89-21 on 890818 & Notices of Violation & Deviation ML20247P6701989-09-20020 September 1989 Forwards Request for Addl Info Re Util 890525 Response to Generic Ltr 88-14, Instrument Air Supply Problems Affecting Safety-Related Equipment. Info Requested within 35 Days of Ltr Date ML20247P6611989-09-18018 September 1989 Requests Addl Info Re Generic Ltr 88-05, Boric Acid Corrossion of Carbon Steel Reactor Pressure Boundary.... NRC Should Be Notified of Full Implementation of Program within 30 Days Following Implementation ML20247Q2371989-09-15015 September 1989 Requests Addl Info Re Util 890502 Response to Generic Ltr 89-08 Re Implementation of long-term Erosion/Corrosion Monitoring Program to Ensure Structural Integrity of All & Two Phase high-energy Carbon Steel Sys at Plant ML20247G2841989-09-13013 September 1989 Approves 890207 Request to Withhold CEN-382(B)-P, Verification of Acceptability of 1-PIN Burnup Limit of 60 Mwd/Kg for Calvert Cliffs,Units 1 & 2 from Public Disclosure (Ref 10CFR2.790) ML20247E8311989-09-0909 September 1989 Requests Util Furnish Ref Matl in Encl List, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exam, by 891004.Written Exam Scheduled for 891204 & Operating Exams Scheduled for 891205-08 ML20246Q1781989-09-0505 September 1989 Discusses Conclusions of Investigation 1-89-003 Re QC Inspector Harassment & Intimidation by Craft Personnel. Insufficient Evidence Found to Conclude Incidents Constitute Violation of 10CFR50.7.Response Requested within 30 Days ML20246K1251989-08-31031 August 1989 Ack Receipt of & Payment of Civil Penalty in Amount of $75,000,proposed by NRC in ML20246L3301989-08-28028 August 1989 Forwards Insp Repts 50-317/89-14 & 50-318/89-14 on 890516-0703 & Notice of Violation.Mgt of Surveillance Programs Has Been Source of Continuing Concern to NRC IR 05000317/19890121989-08-24024 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/89-12 & 50-318/89-12 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 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 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 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 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 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 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 ML20196E0371999-06-16016 June 1999 Forwards Insp Repts 50-317/99-03 & 50-318/99-03 on 990321-0508.Apparent Violation Being Considered for Escalated Enforcement Action ML20207G4331999-06-0707 June 1999 Informs That in Response Request by Nrc,Fema Evaluated Adequacy of Evacuation Plans & Training of Local First Responders for Area Around Ccnpp.Copy of FEMA & Encl to Ltr,Which Provides FEMA Recommendations Encl ML20207G4701999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20207B2491999-05-21021 May 1999 Forwards Insp Repts 50-317/99-04 & 50-318/99-04 on 990405-16.No Violations Noted.Insp Revealed Few Potential & Plausible Aging Effects NRC Team Determined Should Be Included in License Renewal Application ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206A6171999-04-22022 April 1999 Responds to Request for Statistics on Allegation Re Plant by J Osborne.Encl Tables Provides Breakdown of Allegations by Source Category for Allegations Receive in CY95-98 & First Six Month of 1999 ML20205R0961999-04-15015 April 1999 Forwards Insp Repts 50-317/99-01 & 50-318/99-01 on 990131- 0320.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20205P1381999-04-0909 April 1999 Discusses 990223 Ppr.Forwards Plant Issues Matrix & Insp Plan.Since Spring 1998 Unit 1 Operated at Essentially Full Power.Unit 2 Had Similar Power History Except for Jul 1998 Manual Reactor Trip Due to Small Bore Pipe Steam Leak ML20205P1281999-04-0808 April 1999 Forwards Monthly Status Rept on Licensing Activities & Regulatory Duties of NRC for Mar 1999.Targets for Licensing Action Age & Completion Rates & License Renewal Process for Calvert Cliffs Remains on Schedule ML20205E5511999-03-26026 March 1999 Forwards Insp Repts 50-317/99-02 & 50-318/99-02 on 990208-12.No Violations Noted.Insp Was First of Three Planned Visits to Verify Ccnpp License Renewal in Compliance with Requirements of Rule for License Renewal ML20205G8841999-03-24024 March 1999 Discusses Bg&E Application Filed on 980408 for Renewal of Operating Licenses DPR-53 & DPR-68 for Calvert Cliffs Units, 1 & 2.For Listed Reasons,Partial Exemption from 10CFR170 Fees Granted IAW 10CFR170.11(b)(1) ML20205B0291999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of License Renewal Application for Plants,Units 1 & 2,dtd 980408,that Staff Determines Has Generic Value to Industry ML20204H6281999-03-21021 March 1999 Forwards SER Reflecting Status of Staff Review of Util License Renewal for Calvert Cliffs Nuclear Power Plants, Units 1 & 2 ML20207E9641999-03-0404 March 1999 Forwards Insp Repts 50-317/98-12 & 50-318/98-12 on 981213- 990130 & Notice of Violation Re Failure of Maint Workers to Tighten Bolting for Svc Water Heat Exchanger ML20207G8631999-02-25025 February 1999 Forwards Operator Initial Exam Repts 50-317/99-301OL & 50-318/99-301OL on 990122 & 25-29 (Administration) & 990201- 05 (Grading).All Applicants Passed All Portions of Exams ML20203D3981999-02-0505 February 1999 Forwards Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20203A6141999-02-0303 February 1999 Submits Details on Listed Areas Re Inspection Plan of Insp Scheduled for 990203 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20199G4121999-01-20020 January 1999 Forwards SE Accepting Util USI A-46 Implementation Program for Plant ML20199K8481999-01-19019 January 1999 Forwards Insp Repts 50-317/98-11 & 50-318/98-11 on 981025-1212.No Violations Noted ML20199L6621999-01-19019 January 1999 Informs That Licensee Authorized to Administer Initial Written Exam to Listed Applicants on 990122.NRC Region I Operator Licensing Staff Will Administer Operating Test to Applicants ML20199F4101999-01-0808 January 1999 Forwards SE Accepting Util 960213,0725 & 981202 Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety- Related Power-Operated Gate Valves ML20198S4291999-01-0707 January 1999 Requests Addl Info Re License Renewal Application as Application Relates to Staff Position on Environ Qualification ML20198S7491999-01-0707 January 1999 Forwards SER Accepting Licensee ,Suppl by 980424 & 1124 Ltrs Proposing Changes to Rev 49 of Calvert Cliffs Nuclear Power Plant Quality Assurance Program Description in Accordance with 10CFR50.54(a)(3) ML20196K2991999-01-0404 January 1999 Forwards Notice of Consideration of Approval of Transfer of Facility Operating License & Matl License & Opportunity for Hearing in Response to Application ML20202D0271998-12-15015 December 1998 Forwards Notice of Withdrawal of Application for Amend to License DPR-69.Proposed Change Would Have Modified Svc Water Head Tanks.Without Encl ML20198L3431998-12-12012 December 1998 Forwards Insp Repts 50-317/98-10 & 50-318/98-10 on 980706-10 & 1118.Insp Rept Documents App R Issues Which Constituted Violations of NRC Requirements.Nov Not Issued Because, Violations Identified by Licensee Staff as Part of C/A ML20198B1791998-12-10010 December 1998 Advises of Planned Insp Effort Resulting from Calvert Cliffs NPP Review Conducted on 981110.Details of Insp Rept for Next 6 Months & Historical Listing of Plant Issues Considered During Process Encl 1999-09-08
[Table view] |
Text
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April 28, 1986 Docket Nos. 50-317 Distribution: Dockat"FijU
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NRC & L PDRs and 50-318 PWR #8 Files " PKreutzes DJaffe OELD ACRS 10 EJordan JPartlow BGrimes FMiraglia Mr. J. A. Tiernan AThadani Vice President - Nuclear Energy Baltimore Gas & Electric Company P. O. Box 1475 Baltimore, Maryland 21203
Dear Mr. Tiernan:
The Comptroller General in a Report to the Congress dated September 19, 1984, stated "NRC needs better management controls to ensure implementation of generic issue solutions." To correct this situation, the Nuclear Regulatory Commission is working on a long-term program which will improve its documentation on the status of power reactor licensees' implementation of approved regulatory improvements.
To assist me in developing this information for the Calvert Cliffs Plant, Units 1 and 2, please review the enclosed plant-specific lists, add omitted significant actions to the lists, and provide the dates that all aspects of each identified requirements were completed / implemented or are expected to be completed. For each requirement that has been completed, enter " completed" under the Status column and the date the item was completed. For requirements that have not been completed / implemented, provide the projected date and enter " projected" <
under the Status column. I do not expect or want a major effort made to obtain precise dates. Rather, I will accept readily-known or best estimate dates for actions that have been completely implemented. For example, the year only would be acceptable for completions prior to 1984; the month as well as year is needed for requirements completed after that time. For projected completions /implementa-tions in 1986, use month and year. Use year only for projections thereafter.
Please provide a response in the form of a marked up listing by May 31, 1986.
In the future, NRR will need estimated dates prior to issuance of the safety evaluation so that the estimated schedule may be included in the evaluation.
This request is covered by 0MB Clearance Number 3150-0011, which expires September 30, 1986.
i Sincerely,
/S/
' 8605000557e6o42h David H. Jaffe, Project Manager PDR ADOCK 0 % Dn PWR Project Directorate #8 P Division of PWR Licensing-B
Enclosures:
As stated cc w/ enclosures: y See next page PWR# PWR#8 DJaf ;ef Aga ni L/ 86 86 l
1 l
4
Mr. J. A. Tiernan
, Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant cc:
Mr. William.T. Bowen, President Regional Administrator, Region I Calvert County Board of U.S. Nuclear Regulatory Commission Commissioners Office of Executive Director Prince Frederick, Maryland 20768 for Operations 631 Park Avenue D. A. Brune, Esq. King of Prussia, Pennysivania 19406 General Counsel -
Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Jay E. Silberg, Esq.
Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Mr. M. E. Bowman, General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4, P. O. Box 1535 Lusby, Maryland 20657-0073 Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box 437 Lusby, Maryland 20657-0073 Bechtel Power Corporation ATTN: Mr. D. E. Stewart Calvert Cliffs Project Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 Combustion Engineering, Inc.
ATTN: Mr. R. R. Mills, Manager Engineering Services P. O. Box 500 Windsor, Connecticut 06095 Department of Naturai Resources Energy Administration, Power Plant Siting Program ATTN: Mr. T. Magette Tawes State Office Building Annapolis, Maryland 21204
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t-1208751-001 REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO. 71 i
FACIt ITY IMPLEMENTATI0'N 03/31/86
- ACILITY: CALVERT CLIFFS 1
'LANT LOCATION: 40 MI S OF ANNAPOLIS, MD LICENSED PDHER: 2700 MNT PROJECT MANAGER: D. JAFFE 30CKET NUMBER: 050-00317 DESIGN POWER: 0845 MNE BRANCH CHIEF: A. THADANI 1RCH/ ENGINEER: BECH NSSS VENDOR: COMB LIC. ASSISTANT: P. KREUTZER tE INSPECTOR: T. FOLEY LIC ACT LICENSEE IAC NO. MPA 9 TITLE COMPLETE STATUS MI.E 108042 A-Of 10 CFR 50.55 A(G) - ISI 12/16/82C 108136 A-02 APPENDIX I - ALARA 02/22/85C 106606 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS 03/28/79C 181383 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 02/05/81C
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1 110658 A-10 CONTINGENCY PLANNING 08/18/80C i
110639 A-11 GUARD TRAINING PLANS 02/20/81C 110655 A-12 VITAL AREA ANALYSIS 03/31/82C 111291 A-14 10CFR 50.55 A(G) - INSERVICE TESTING 02/08/82C 112554 A-15 9UALITY ASSURANCE REGUEST REGARDING DIESEL GENARAT 04/11/80C l 147046 A-16 90ALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 07/23/82C i 151078 A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN 06/30/86 153367 A-18 TECM SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 06/06/84C 159079 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS 159944 A-21 10 CFR 50.61, PRESSURIZED THERMAL $ NOCK RULE l 106735 B-02 FIRE PROTECTION 09/14/79C 198373 3-03 PNR MODERATOR DILUTION 03/01/79C 4
187154 B-07 STEAM GENERATOR FEEDNATER FLON INSTABILITY 03/10/80C 197843 B-09 CHARGING SYSTEMS PIPE VIBRATIONS 10/18/79C 108946 B-14 CEA GUIDE TUBE N6Ak 06/16/81C i
112158 B-16 EMERGENCY PLANNING AND REVISIONS 01/01/70C i
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'ALVERT CLIFFS 1 (CONTINUATION)
LIC ACT LICENSEE AC NO. MPA_0 TITLE COMPLETE STATUS DAIE 108971 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 12/28/81C 110310 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 01/01/70C
- 110372 B-21 LOSS OF 125-V DC BUS VGLTAGE HITH LOSS OF ANNUNCIA 02/09/82C K8954 3-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 12/28/81C 111317 B-23 DEGRADED GRID VOLTAGE 07/31/79C I 110218 B-24 VENTING AND PURGING CONTAINMENTS HNILE AT FULL POW 01/01/70C 142584 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW O2/01/82C 110247 B-26 INADVERTANT SAFETY INJECTION DURING COOLDOWN 09/14/79C C8967 B-36 RESISTANCE TEMPERATURE DETECTOR (RTB) RESPONSE - C 06/30/81C ,
198955 B-37 STEAM GENERATOR TUBE DENTING AND SUPPDRT PLATE MOD 12/12/80C 07522 3-38 TENDON SURVEILLANCE - BECHTEL CONTAINMENTS 08/01/83C 110818 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/14/80C 111105 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 10/02/80C 145800 3-41 FIRE PROTECTION - FINAL TECM-SPECS (INCLUDES SER S 03/18/82C I43802 3-41 FIRE PROTECTION # FINAL TECM SPECS (INCLUDES SER S 06/30/81C 543798 B-41 FIRE PROTECTIDN - FIl>L TECN SPECS CINCLUDES SER S 09/27/82C, -
^
111734 B-42 TMIFOLLONUP-AL[ PLANTS
l 181789 B-43 PHR FEEDWATER LINE CRACKS 03/05/80C 143130 B-43 PWR FEEDWATER LINE CRACKS 5 05/25/82C /
130464 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130465 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C ,
130466 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130467 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C k
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t-1208731-001 REOULAT0RY INF0RMATION TRACKINO SYSTEM PAGE No. - 73 FACILITY IMPLEMENTATI0'N 03/31/86 ALVERT CLIFFS 1 (CONTINUATION) l
! LIC ACT LICENSEE j TAC NO. MPA 0 TITLE COMPLETE STATUS DAIE 130468 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130469 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130470 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130471 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130472 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C l 130473 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C l 130474 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C i
l 130475 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C i '30476 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C
! 130477 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 112S61 3-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 112880 B-45 NASN 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 08/15/80C 112595 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/28/81C 942074 3-46 ANALYSIS OF TURBINE DISC CRACKS 05/15/80C 142108 B-46 ANALYSIS OF TURBINE DISC CRACKS 06/16/81C 112724 B-47 ECC$s CLAD SHELLING AND RUPTURE 09/10/80C 112670 3-48 ADEGUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 05/10/82C I 943793 B-52 REVIEN OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 05/01/81C 4
942890 B-59 MASONRY HALL DESIGN 07/18/85C
! M42494 B-60 ENVIRONMENTAL DUALIFICATION 11/20/84C M42659 B-61 LOSS OF NON CLASS IE 18C POWER 07/28/82C i
i M42729 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 03/16/82C 443888 3-63 INTERIM PROCEDURES FOR SNORT TERM BLACKOUT 08/28/81C i i
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-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.s 74 [
FACILITY IMPLEMENTATION 03/31/86f ALVERT CLIFFS 1 (CONTINUATION) l LIC ACT LICENSEE i AC NO. MPA 0 TITLE COMPLETE STATUS RAIE !
1 47158 B-66 NATURAL CIRCULATION C00LDOWN 07/08/83C 07546 B-67 THERMAL SHOCK 02/03/83C 4 r 47027 ' B-67 THERMAL SHOCK 01/21/82C _
46827 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDM 08/01/83C 49725 B-72 NUREG 0737 TECN SPECS (GENERIC LETTER 82-16) 08/01/33C
< 52'744 B-76 ITEM 1.1 - POST TRIP REVIEN; PROGRAM DESCRIPTION 8 04/11/85C 53825 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION 8 VENDOR INTER 08/31/86 j 32906 5-78 ITEMS 3.1.1 8 3.1.2 -POST MAINTENANCE TEST PROCEDU 11/21/85C ,
52987 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 05/30/86
, 53062 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDC 11/21/86C .'
a
- 53115 B-81 ITEMS 4.2.1 8 4.2.2 -PREVENTATIVE MAINT_ PROG FOR R 87/10/85C I
54523 B-83 ~7ECM SPECIFICATIONS COVC2ED BY GENERIC LETTERS 83- 02/22/85C i 53576 B-85 SALEM ATHS 1.2 DATA CAPABILITY 04/31/86 53659 B-86 SALEM ATNS 2.2 5-R COMPONENTS 12/01/86
, 53742 3-87 SALEM ATNS 3.2.1 8 3.2.2 S-R COMPONENTS 11/21/8 5C 53825 3-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 05/30/46 i i
- 53902 3-89 SALEM ATHS 4.2.3 8 4.2.4 LIFE COMPONENTS 12/31/86 1 i
! 5C052 3-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 11/21/85C 4
f 53969 B-93 SALEM ATHS 4.5.2 8 4.5.3 TEST ALTERNATIVES 12/31/86 07224 C-04 PUMP SUPPORT-LAMELLAR TEARING 04/17/81C 08963 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 05/18/79C
'87978 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE- 05/27/83C 10953 C-12 BORON SOLUSILITY DURING LONG TERM COOLING FOLLONIN 06/16/81C i :
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., t 4-1308731-001 REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO.: 75 FACILITY IMPLEMENTATION 03/31/86 i
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LIC ACT LICENSEE IAC NO. MPA 6 TITLE COMPLETE STATUS PAff, 107311 C-12 BORON SOLUBILITY DURING LONG TERM COOLING FOLLONIN 01/01/70C i 143634 C-14 AUXILIARY FEEDWATER SEISMIC GUALIFICATION 03/21/84C 152215 C-15 CONTROL OF NEAVY LOADS - PHASE II (FDLLONUP OF MPA 06/28/85C 158048 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIDMS CONCERN 12/11/85C ,
108959 D-06 PEAKING MODEL CNANGE FOR CE REACTOR CORE 03/31/78C 108951 D-10 ASYMMETRIC LOCA LOADS 110096 D-11 FISSION GAS RELEASE 06/14/79C i
112314 D-15 HIGN ENERGY LINE BREAK S CONSE90ENTIAL SYSTEM FAIL 01/31/84C 143025 D-17 DEFINITION OF DPERABLE 04/03/81C
- 155846 D-19 DIESEL GENERATOR RELIABILITY TECN SPECS (GL 84-15) 12/31/85C 111930 E-01 SPENT FUEL POOL EXPANSIONS 09/19/80C 112506 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 12/12/80C 198233 E-03 CORE RELOADS REGUIRING PRIOR NRC APPROVAL 06/14/79C 198965 E-06 CEA POSITION INDICATION FAILURES - CE 02/08/82C ,
144009 F-01 I.A.1.1 SNIFT TECHNICAL ADVISOR 07/09/82C 144077 F-02 I.A.1.3 SHIFT MANNING 04/21/83C f
j M4148 F-03 1.A.2.1 UPGRADING OF R0 AND SRO TRAINING 11/24/82C 1 144219 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/07/84C l
144289 F-05 I.C.1.2/3.8 PROCEDURES GENERATION PACKAGES (NUREG 06/30/86 147202 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 11/03/81C 4
% 7274 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/05/81C 151148 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 10/10/84C l
151228 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 03/30/86 N
t-1308731-001 REGULATORY INF0RMATION TRACKINO SYSTEM PAGE N0.8 76 FACILITY IMPLEMENTATIO'N 03/31/86 '
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LIC ACT LICENSEE TAC NO. MPA 0 TITLE CREPLETE STATUS DAIL 144360 F-10 II.B.1 RCS NIGN POINT VENTS 09/07/83C 147926 F-11 II.B.2 PLANT SNIELDING 08/16/84C 144428 F-12 II.B.3 POST ACCIDENT SAMPLING 02/12/85C 144498 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 11/24/82C 144569 F-14 II . D .1 RV AND SV TRAINING 06/01/86
+
144661 F-15 II.E.1.1 AFH SYSTEM EVALUATION 06/29/81C 144703 F-16 II.E.1.2.1 AFM SYSTEM INITIATION 06/21/82C i
444742 F-17 II.E.1.2.2 AFM SYSTEM FLOW INDICATION 06/21/82C 144766 F-18 II.E.4.1 DEDICATED NYDROGEN PENETRATION 09/18/81C 3
440837 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY O2/01/82C 144908 F-20 I I . F .1.1 NOBLE GAS MONITOR 11/02/81C
! 144979 F-21 II.F.1.2 IODINE / PARTICULATE SAMPLING 11/02/81C 145050 F-22 II.F.1.3 CONTAINMENT NION RANGE MONITOR 01/07/82C 147587 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 04/21/83C 147658 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 04/21/83C
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147729 F-25 II.F.1.6 CONTAINMENT NYDROGEN MONITOR C4/21/83C
- 145121 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEGUATE 07/31/87 146877 F-30 II.K.2.13 THERMAL-MECNAMICAL REPORT 06/05/84C 147793 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 10/24/83C 145260 F-36 II.K.3.1 AUTO PORV ISOLATION 10/06/83C 145306 F-37 II.K.3.2 REPORT ON PORV FAILURES 10/06/83C j 145330 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 03/09/82C 145427 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C t
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- ALVERT CLIFFS 1 (CONTINUATION)
LIC ACT LICENSEE
'AC NO. MPA 0 TITLE COMPLETE STATUS p_ATI i 105616 F-47 II.K.3.17 ECCS OUTAGES 08/08/83C 148443 F-53 II.K.3.25 PDHER ON PUMP SEALS 10/07/85C 145812 F-57 II.K.3.30 SB LOCA METHODS 06/28/85C 148153 F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 06/25/85C 145932 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 12/31/87 146003 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 12/31/87 100075 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 12/31/87 146147 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C 146219 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/11/83C 146291 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 12/31/87 143362 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 03/09/82C 146433 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 09/05/82C 156110 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLONUP TO 03/31/87 149674 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 06/30/86 4
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R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 78 FACILITY IMPLEMENTATION 03/31/8,6 FACILITY: CALVERT CLIFFS 2 PLANT LOCATION: 40 MI S OF ANNAPOLIS, MD LICENSED P0HER: 2700 MHT PROJECT MANAGER: D. JAFFE DOCKET NUMBER: 050-00318 DESIGN P0HER: 0845 MNE BRANCH CHIEF: A. THADANI ARCH / ENGINEER: BECH NSSS VENDOR: COMB LIC. ASSISTANT: P. KREUTZER IE INSPECTOR: T. FOLEY LIC ACT LICENSEE TAC NO. MPA 0 TITLE COMPLETE STATUS Half M03761 A-01 10 CFR 50.55 A(G) - ISI 12/16/82C M08137 A-02 APPENDIX I - ALARA 02/22/85C M08313 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS 03/28/79C M11382 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 02/05/81C M10659 A-10 CONTINGENCY PLANNING 08/18/80C M10640 A-11 GUARD TRAINING PLANS 02/20/81C M10656 A-12 VITAL AREA ANALYSIS 03/31/82C M11292 A-14 10CFR 50.55 A(G) - INSERVICE TESTING 02/08/82C M12555 A-15 00ALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 04/11/80C M48607 A-16 0UALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 07/23/82C M51079 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 06/30/86 M59080 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS M59945 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE M08232 3-02 FIRE PROTECTION 09/14/79C M08374 B-03 PHR MODERATOR DILUTION 03/01/79C M07844 B-09 CHARGING SYSTEMS PIPE VIBRATIONS 10/18/79C M08945 B-14 CEA GUIDE TUBE HEAR O2/10/81C .
M12159 B-16 EMERGENCY PLANNING AND REVISIONS 01/01/70C M08970 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 12/28/81C M10311 5-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 01/01/70C i
t-1308731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 79 FACILITY IMPLEMENTATION 03/31/86 lALVERT CLIFFS 2 (CONTINUATION)
LIC ACT LICENSEE rAC NO. MPA_1 TITLE COMPLETE STATUS Ralg 110373 8-21 LOSS OF 125-V DC BUS VOLTAGE NITH LOSS OF ANNUNCI A 02/09/82C 108953 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 12/28/81C j 108545 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 03/10/80C 111318 B-23 DEGRADED GRID VOLTAGE 07/31/79C 110217 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 01/01/70C 142585 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL PON 02/01/82C 110248 B-26 INADVERTANT SAFETY INJECTION DURING C00LDOWN 09/14/79C 108968 B-36 RESISTANCE TEMPERATURE DETECTOR (RTD) RESPONSE - C 06/30/81C 108956 B-37 STEAM GENERATOR TUBE DENTING AND SUPPORT PLATE MOD 02/10/81C 108696 B-39 PNR PRESSURE - TEMPERATURE LIMIT TECN SPECS 11/14/80C 111106 3-41 FIRE PROTECTION - FINAL TECN SPECS (INCLUDES SER S 10/02/80C 09/27/82C 443799 B-41 FIRE PROTECTIOh - FINAL TECN SPECS (INCLUDES SER S 3 443801 3-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 03/18/82C 143803 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 06/30/81C 111735 3-42 TMI FOLLON UP - ALL PLANTS 04/21/81C 111790 3-43 -PNR FEEDHATER LINE CRACKS 03/05/80C 1
943131 3-43 PHR FEEDNATER LINE CRACKS 05/25/82C 130478 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130479 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C j 130480 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C
! 130481 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130482 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 130483 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 1
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-1208731-001 REGULAT0RY INF0AMATION TRACKINO SYSTEM PAGE NO.8 80 FACILITY IMPLEMENTATION 03/31/86, ALVERT CLIFFS 2 (CONTINUATION)
LIC ACT LICENSEE AC NO. MPA 8 TITLE COMPLETE STATUS RAIE 30484 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 30485 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 30486 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 30487 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 30488 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 30489 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 30490 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 30491 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 12362 B-44 LESSONS LEARNED IMPLEMENTATION 04/07/80C 12881 B-45 NASN 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 08/15/80C 4
12596 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/28/81C 42109 B-46 ANALYSIS OF TURBINE DISC CRACKS 06/16/81C 12725 B-47 ECCS CLAD SHELLING AND RUPTURE 09/10/80C 12671 3-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 05/10/82C 42891 3-59 MASONRY NALL DESIGN 07/18/85C 42495 B-60 ENVIRONMENTAL QUALIFICATION 11/20/84C 42660 3-61 LOSS OF NON CLASS IE ISC P0HER 07/28/82C 42730 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 03/16/82C 43889 B-63 INTERIM PROCEDURES FOR SNORT TERM BLACKOUT 08/28/81C 47159 B-66 NATURht CIRCULATION C00LDOWN 07/08/83C
- 46828 B-69 IER 80-4 MAINSTEAM LINE BREAK HITN CONTINUED FEEDW 08/01/83C 09726 B-72 NUREG 0737 TECM SPECS (GENERIC LETTER 82-16) 08/01/83C 1 52745 B-76 ITEM 1.1 - POST TRIP REVIEN; PROGRAM DESCRIPTION 8 04/11/85C
%-1208731-C01 REOULAT0RY INF0RMATION TRACKING ,YSTEM PAGE NO.8 81 FACILITY IMPLEMENTATION 03/31/86, ALVERT CLIFFS 2 (CONTINUATION)
LIC ACT LICENSEE ,
TAC NO. MPA 0 TITLE COMPLETE STATUS RAlg 152826 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION 8 VENDOR INTER 08/30/86 152007 B-78 ITEMS 3.1.1 8 3.1.2 -POST MAINTENANCE TEST PROCEDU 11/21/85C 152988 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 05/30/86 153063 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 11/21/85C 153116 B-81 ITEMS 4.2.1 8 4.2.2 -PREVENTATIVE MAINT PROD FOR R 07/10/85C 154524 B-83 TECN SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 02/22/85C 153577 B-85 SALEM ATHS 1.2 DATA CAPACILITY 04/30/86 l 153660 B-86 SALEM ATHS 2.2 5-R COMPONENTS 12/31/86 153743 B-87 SALEM ATHS 3.2.1 8 3.2.2 S-R COMPONENTS 11/21/85C 153826 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 06/30/86 153903 B-89 SALEM ATHS 4.2.3 8 4.2.4 LIFE COMPONENTS 12/31/86 154053 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 11/21/85C
, 153970 B-93 SALEM ATHS 4.5.2 4 4.5.3 TEST ALTERNATIVES 04/31/87 i
108948 C-06 PUMP SUPPORT-LAMELLAR TEARING 04/17/81C 108962 C-07 FUEL NANDLING ACCIDENT INSIDE CONTAINMENT 95/18/79C 197979 C-10 CONTROL OF NEAVY LOADS OVER SPENT FUEL P0OL (PNASE 05/27/83C 197968 C-12 BORON SOLUBILITY DURING LONG TERM COOLING FOLLONIN 06/16/81C 143635 C-14 AUXILIARY FEEDNATER SEISMIC QUALIFICATION 03/21/84C 152216 C-15 CONTROL OF HEAVY LOADS - PNASE II (FOLLOWUP OF MPA 06/28/85C
' 158049 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 12/11/85C 108958 D-06 PEAKING MODEL CNANGE FOR CE REACTOR CORE 10/21/78C 108950 D-10 ASYMMETRIC LOCA LOADS 110097 D-11 FISSION GAS RELEASE 10/21/78C
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-1208731-001 REGULAT0RY INF0RMATIoN TRACKINO SYSTEM PAGE NO.8 82 FACILITY IMPLEMEN7ATIOk 03/31/86 ALVERT CLIFFS 2 (CONTINUATION)
IIC ACT LICENSEE AC NO. MPA 8 TITLE COMPLETE STATUS PAIE 12315 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 01/31/84C 43026 D-17 DEFINITION OF OPERABLE 04/03/81C 55847 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 12/31/85C I
11931 E-01 SPENT FUEL POOL EXPANSIONS 09/19/80C 11332 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 11/19/79C 07798 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 10/21/78C 08966 E-06 CEA POSITION INDICATION FAILURES - CE 02/08/82C 40010 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 07/09/82C 44078 F-02 I 4.1.3 SHIFT MANNING 04/21/83C
{ 44149 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 11/24/82C 44220 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/07/84C 44290 F-05 I.C.1.2/3.3 PROCEDURES GENERATION PACKAGES (NUREG 06/30/86 47203 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 11/03/81C 47275 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/03/81C
- 51149 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEN PROGRA 10/10/84C 51229 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 03/30/86
- 44361 F-10 II.B.1 RCS NIGN POINT VENTS 09/07/83C 47927 F-11 II.B.2 PLANT SHIELDING 08/16/84C
! 44429 F-12 II.B.3 POST ACCIDENT SAMPLING 02/12/85C 44499 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 11/24/82C 44570 F-14 II.D.1 RV AND SV TRAINING 06/01/86 44662 F-15 II.E.1.1 AFM SYSTEM EVALUATION 06/29/81C 44704 F-16 II.E.1.2.1 AFM SYSTEM INITIATION 06/21/82C i
1-1208731-001 REOULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO. 83 FACILITY IMPLEMENTATION 03/31/86 lALVERT CLIFFS 2 (CONTINUATION) 4 LIC ACT LICENSEE TAC NO. MPA 0 TITLE COMPLETE STATUS RaIg i 144743 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 06/21/82C j 140767 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 09/18/81C
'l 144838 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 02/01/82C 144909 F-20 II.F.1.1 NOBLE GAS MONITOR 11/02/81C 144980 F-21 II.F.1.2 IODINE / PARTICULATE SAMPLING 11/02/81C 145051 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/07/82C i 147588 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 04/21/83C 147659 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 04/21/83C 147730 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/21/83C 445122 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 07/31/87 146880 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/05/84C M47794 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 10/24/83C M45261 F-36 II.K.3.1 AUTO PORV ISOLATION 10/06/83C 445307 F-37 II.K.3.2 REPORT ON PORV FAILURES 10/06/83C M45331 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 03/09/82C 445428 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C
- M45417 F-47 II.K.3.17 ECCS OUTAGES 08/08/83C 1
< M48444 F-53 II.K.3.25 POWER ON PUMP SEALS 10/07/85C M45813 F-57 II.K.3.30 SB LOCA METHODS 06/28/85C f M48154 F-58 II.K.3.31 COMPLIANCE HITN to CFR 50.46 06/25/85C
! M45933 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 12/31/87
! M46004 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 12/31/87 i M46076 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 12/31/87 1
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R-1208731-001 REOULATORY INF0RMATION TRACKINO $Y$ TEM PAGE NO.s 84 FACILITY I M P L E M E N T A T I 0'N 03/31/86 CALVERT CLIFFS 2 (CONTINUATION) i LIC ACT LICENSEE TAC NO. MPA 9 TITLE COMPLETE STATUS PAJ.E 146148 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C M46220 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/11/83C M46292 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 12/31/87 M46363 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 03/09/82C M46434 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 09/03/82C M56111 F-71 I.D.1.2 DETAILED CONTROL RDOM REVIEN (FOLLONUP TO 03/31/87 M49675 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 06/30/86 i
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