|
---|
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 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 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 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 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) 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 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 ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 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 ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) 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 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 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 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 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 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 ML20055G5951990-07-18018 July 1990 Corrected Cover Ltr Forwarding Insp Repts 50-317/90-10 & 50-318/90-10 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 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 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 ML20246G1221989-08-22022 August 1989 Forwards Safety Insp Repts 50-317/89-17 & 50-318/89-18 on 890717-21 & Notice of Deviation 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
November 20, 1986 !
M/v\3 Oh Docket Nos. 50-317 and 50-318 Mr. J. A. Tiernan Vice President-Nuclear Energy Baltimore Gas & Electric Company P. O. Box 1475 Baltimore, MD 21203
Dear Mr. Tiernan:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - RETRAN REVIEW Your letter dated January 31, 1986, submitted the Topical Report A-85-11, "RETRAN Computer Code, Reactor System Transient Analysis Model Qualification,"
for Commission review and approval. We have determined with the assistance of our contractor, International Technical Service, Inc. , that additional information is required to complete our review. The request for additional information is enclosed.
Please provide the information as requested within 45 days following the receipt of this letter to permit the expeditious completion of our review. If additional time is needed to provide the requested information, please inform us within 30 days of your proposed schedule for providing this information.
This request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Origh! Q;uul by Scott Alexander McNeil, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page TRIBUTION ACRS-10 ocket Filg ) BGrimes NRC PDR JPartlow L PDR SMcNeil PBD-8 Rdg PKreutzer FMiraglia Gray File OGC-Bethesda NThompson
.EJordan PBD#8, PBD#8 P8D#8 PKredtzer ft AThadani 11/c;/86 SMg/h>/86 II 11/p86 i
861202o042ggbob17 ADOCK PDR PDR P
y 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, Pennys1vania 19406 General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Jay E. Silberg Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 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. W. R. Horlacher, III Project Manager P. O. Box 500 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 Department of Natural Resources Energy Administration, Power Plant Siting Program ATTN: Mr. T. Magette Tawes State Office Building Annapolis, Maryland 21204
I REQUEST FOR ADDITIONAL INFORMATION BALTIMORE GAS AND ELECTRIC COMPANY RETRAN CODE REVIEW
- 1. BG&E used the RETRAN02/ modo 3 computer code which has not been generically approved by the NRC. Discuss the differences between this code and the RETRAN02/ modo 2 code (which is the NRC approved version) and the impact of these differences on transient and accident analyses.
- 2. Provide the data and comparison which support BG&E's conclusion that the use of a single node for the secondary side of the steam generator will produce acceptable results. In addition, provide and justify the types of transients for which such a single node secondary volume is valid.
- 3. Justify the use of a single node non equilibrium pressurizer regarding rapid insurge and outsurge transients.
- 4. For the Multiple Secondary Side Malfunction (MSSM) event, BG&E assumes three heat transfer slabs transfering thermal energy to a single hydraulic node in the pressurizer. Discuss the effect of not subdividing the hydraulic node in the pressurizer in light of the temperature stratification of the fluid in the pressurizer.
- 5. Based on our review of Section 4.1 of the topical report, we have identified several anomalies. Provide explanations for the following anomalies:
(1) BG&E had postulated that "possibly higher run-out auxiliary feedwater (AFW) pump flow rates and lower post trip main feedwater (MFW) temperatures caused more rapid cooldown after 160 sec in plant data." However, we note
. that the plant data show the SG21 level pegged at about 200 sec and that differences in level in SG21 existed from about 70 sec, not 160. The RETRAN calculation of level in SG21 lagged the actual refill data by roughly 20 see throughout the transient; (2) The slope difference in the steam generator level between the RETRAN calculation and the plant data for SG22 resulted in a difference in dry out time of about 40 sec.
(3) The effect on the transient of the broader spike in RETRAN analysis.
(4) What happened in the plant data at approximately 140 sec following the event? Why was this transient curve not followed by the RETRAN calculations?
Is it related to dryout of the steam generator? Would a more detailed steam generator secondary side nodalization give better results?
- 6. The statement that the " difference in SG pressure response accounts for differences in primary coolant systems cooldown after 160 sec" is not exactly accurate. The differences in secondary side pressure began at roughly 70 sec and the large change in slope in secondary pressure data at roughly 110 sec was not matched by the RETRAN calculation of the steam generator pressure although the general characteristics of the steam generator pressure was followed. Explain the sources of all the signifi-cant deviations and justify the differences between the RETRAN calculation and the plant data.
i l
.n_ __. _ , - - _ _ _ _ _ _ - - - _ _ - - -
I
- 7. Expand your discussions on the RETRAN model sensitivity study to support your conclusion stated on page 27 of the report. In particular, did BG&E perform sensitivity studies to determine what happened on the secondary side and its impact on the primary side? If not, then discuss the secondary side flow data and the RETRAN modeling thereof, and justify any differences by discussion of their impact upon the overall transient results.
- 8. What input loss coefficients were adjusted to establish initial conditions in the transient of four pump coastdown from 20% power? Were any reverse flow loss coefficients used for the reactor coolant pumps? If the reverse flow coefficients were used, describe what caused the steep changes in flow data at roughly 45 sec? Were the same coefficients used in Section 4.3?
Was there a change in flow regime which caused the flow meter to give a different correlation? If the plant data is correct as plotted, why was the slope change not followed by RETRAN? Finally, provide estimates of the natural circulation that is predicted by RETRAN and compare RETRAN's estimates with the expected values.
- 9. BG&E states that sensitivity studies were performed to adjust the downcomer cross flow and RCP reverse flow coefficients. Although the cross flow takes place across a large area, perhaps the flow modeling is inaccurate and/or incomplete due to failure to model cross flows in the above core region.
Explain how the flows in the above core region were modeled; and justify BG&E's modeling of the cross flow. Provide detailed results from sensi-tivity studies of variation of cross flows and reverse flow coefficients.
Provide plots to accompany the analysis and discussions on comparison of RETRAN results with the measured plant data for each of five combinations of RCP operation (4, 3, 2 in the in the same loop, 2 in opposite loops, and 1 RCP running). Explain how flowrates of various cross flows were determined for the calculations, including the bypass flows which " flows circumferencially around the downcomer and out the cold leg nozzle (s) in the reverse direction through the shut down RCP(s) to the steam generator outlet plenum."
Compare the predicted flows in these various combinations with vendor computations and explain any significant differences. Provide the data that are available to verify the " actual flow path" for reduced RCP operation configurations. Describe how the RCP locked rotor reverse flow coefficient was determined.
- 10. With regard to the transient of one pump coastdown from 80% power, discuss the basis for adjustment of reactor coolant pump (RCP) moment of inertia and torque including the uncertainty of such pump information.
Were any cross flow sensitivity studies performed for the one RCP coast-down transient? The transient computation seems to substantially over-predict the flow reduction in the shutdown loop. Identify and describe the likely sources of over prediction. What results are obtained without cross flow and with nominal reverse flow coefficients? Why does plant data show nearly instantaneous pressurizer response while RETRAN seems to show no response for approximately 5 sec? Describe why, even though both
~
t the hot leg temperature and the steam generator pressure increase for about 5 see immediately following the RCP trip, and the cold leg temperature remains constant, neither the primary nor the secondary side pressures ,
immediately increase in the RETRAN calculations. Describe and quantify to the extent feasible the differences in the results between the case in which BG&E adjusted the RCS total flow to match hot and cold leg temperatures, and the case usfng the initial conditions described in Sections 4.3 and 4.4.
- 11. It appears that the RETRAN calculation for a total loss of flow transient from 40% power was initiated with a slightly different hot leg temperature from the plant data. Was there any difficulty in initializing the calcu-lation at 40% power? Were any loss coefficients adjusted in setting up initial conditions? If so, how did they compare to adjustments in Sections 4.3 and 4.47 What happened in the steam generator at 10 sec (see Figures 4.5-2, 3, and 5) and why wasn't it modeled in RETPAN? (We note 3' that there was relatively poor transient computation of temperatures between 10 and 60 sec because of these differences.) Since the time between 60 to 130 min is considered to be the more important period, provide transient curves for that period. The transient curves of primary flow and pressure are in agreement but do not agree for the hot and cold leg temperatures and SG secondary side pressure. What is the reason to cause this effect and why did the secondary side not have a stronger coupling to the primary side?
- 12. One of the objectives of this topical report is to present BG&E's capability in modeling control systems. Since it is apparent that the major reason for disagreement between TRAC and RETRAN results is the differences in the ADV modeling, BG&E should match the ADV control system used in TRAC and 4
+
rerun the calculation.
BG&E states that in spite of the fact that " primary pressure compares very well, RETRAN predicts the pressurizer to empty while TRAC does not" and that "this is consistent with previous comparison." If this difference is present in the revised calculation, then explain why one code predicts the pressurizer to empty and the other does not.
- 13. Provide detailed transient curves of RETRAN and TRAC secondary flows, pressures, and temperatures. Correlate to the transient curves for the secondary side with parameters on the primary side. Explain why the PORY reaches its set point about 500 sec earlier than the TRAC predictions.
Explain why RETRAN predicts that the pressurizer water level will rise to the top of the pressurizer 1250 sec before the TRAC predicted time.
In addressing the differences between the results, explain the impact that the noding may have in computing downcommer temperature. It seems unlikely to us that these differences are caused by the coarse RETRAN noding in the downcomer (2 vs 54). Discuss the crossflow betweea nodes in the TRAC nodalization, and provide the theoretical foundation for the
statements that imply crossflow would increase with increasing nodalization.
In addition, explain why increasing the number of nodes in the secondary side of the SG 5 not considered as an option to reduce the void formation in the upper tu e volumes.
- 14. Describe any differences between the BG&E RETRAN model and the RETRAN model used in initial analysis of L6-1 and L6-3 by EPRI as presented to the ACRS on January 14, 1981.
- 15. Verify the slip impact on secondary swell level by plotting results with an infinite bubble rise model in the steam generator secondary side. Compare the results from an infinite bubble rise model with results from a single node secondary side model. Explain significantiv greater depressurization andwhythemainsteamflowcontrolvalve(MSFCV)wasopen40%longerthan the test, and provide the transient curve of experimental and predicted flowrates. Describe the control system which governs the MSFCV operation in the experiment and how this was simulated by RETRAN. The depressurization computed by RETRAN was 50-60% larger than the test result, therefore, it appears to be not merely due to 40% longer opening of the MSFCV.
- 16. (LOFT-6-3) Modeling of the secondary side appears to be inadequate (see Figure 6.4-1, 2, and 5), causing primary side behaviors to differ from the test data. Explain and justify the secondary side modeling including a thorough explanation of why RETRAN calculates "somewhat higher terminal steam flow and feedwater flow."
- 17. With respect to BG8E's general analysis of the LOFT tests, BG&E selected two transients that were initiated on the secondary side. Since BG&E did not accurately model the secondary events, the primary response may be
, incorrectly computed. Develop secondary controls and input which accurately represent the transients conducted in the LOFT test. Rerun these compu-tations to obtain a valid comparison of RETRAN results with LOFT test data.
9
- - - -- _ -h..- -. - . - . _ _ . . _ _ . _ - - - _ _ . - - - . - , - . _ _ . .