|
---|
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 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 ML20062B8361990-10-0909 October 1990 Forwards Special Team Insp Rept 50-317/90-24 on 900904-07 Re 900830 Reactor Vessel Water Level Anomaly ML20059N5781990-10-0909 October 1990 Advises That Util 900510 Submittal of Revised Section of Inservice Insp Program Plan Addressed Provisions of Safety Evaluation 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 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 ML20055G5931990-07-18018 July 1990 Forwards Corrected Cover Ltr for Insp Repts 50-317/90-10 & 50-318/90-10,revising Insp Rept Numbers 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 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 ML20199K8481999-01-19019 January 1999 Forwards Insp Repts 50-317/98-11 & 50-318/98-11 on 981025-1212.No Violations Noted 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 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) ML20198S4291999-01-0707 January 1999 Requests Addl Info Re License Renewal Application as Application Relates to Staff Position on Environ Qualification 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
. i
. i JUL 101990 !
Docket Nos. 50-317/318 Baltimore Gas and Electric Company ATTN! Mr. George C. Creel
- Vice President-Nuclear Energy 1 Calvert Cliffs Nuclear Power Plant MD Rts 2&4, P. O. Box 1535 :
Lusby, Maryland 20657 :
Gentlement ,
t SUBJECT REQUALIFICATION PROGRAM EVALUATION !
In a telephone conversation between Mr. John Hill and Mr. Brian Hughes, arrangements were made for an evaluation of the requalification prrgram >
and 14 sensed personnel at the Calvert Cliffs Nuclear Power Plant, Unit j Nos. I and 2. The evaluation visit is scheduled for the week of-October 22, 1990.
For this visit, . the NRC examiners will administer NRC prepared I operating and written examinations. The NRC examiners will visit the site approximately fourteen days in advance to meet with the ,
appropriate facility personnel and operators to review the schedule and t the-process for these examinations. For the examiners to adequately prepare- for this visit, it will be necessary for the facility to furnich the approved items listed in Enclosure 1 " Reference Material' ,
naquirements. " Mr. Hill has been advised of our reference material requirements and where they are to be sent.
NRC reserves the right to postpone NRC administered roqualification examinations if the facility generated materials are inadequate for i examination preparation.
It is requested that an employee be provided to complete- the ,
examination team. The employee shall. be an active SRO (per the requirements of 10 CFR 55.53 (e)- or (f) SRO from the Operrtions ,
)
Department. If desired by the facility, and agreed to by the chief Examiner, an additional employee from the Training Departmenc sc be a member of the examination team. This employee shall pref"r2 .y be an active SRO (per the requirements of 10 CFR 55.53(e). or (f) nny be a facility or INPO certified instructor. These-individuals must not be scheduled for an NRC administered examination during this visit, or
. participate as instructors once selected. The facility representatives will be required to certify that they did not knowingly compromise any !
portion of the examination.
.The facility representative shall be restricted (1) from knowingly
' communicating by any means the content or scope of the examination to '
unauthorized persons and (2) from participating in any facility programs such as instruction, examination, or tutoring in which an identified requalification examinee (s) will be present. These
%7%o 0FFICIAL RECORD COPY \ f
restrictions shall apply after their first involvement with the examination or knowledge of its content.
In addition to these individuals, the assignment of a simulator operator is requested 14 days prior to the scheduled examination date.
The simulator operator will be under examination security restrictions similar to those above, except that his/her restrictions shall apply from 14 days prior to the examination date.
The facility management is responsible for providing adequate space and accomodations to properly develop and conduct the examinations.
Enclosure 2, " Administration of Requalification Examination," describes our requirements for developing and conducting the examinations. Mr.
Hill has also been informed of these requirements. Also, a facility operations management representative (as a minimum, first level above shift supervisor) should observe the simulation facility examination process at the site.
Enclosure 3, contains the "NRC Rules and Guidance for Examinees" that will be in effect during the administration of the written examination.
The facility management is responsible for ensuring that all operators are aware of these rules. The requalification examinations and the subsequent evaluation of the facility requalification program will be performed in accordance with ES-601.
This request is covered by Office of Management and Budget clearance Number 3150-0101, which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing and mailing the required material. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and the Paperwork Reduction Project (3150-0101), Office of Management and Budget, Washington, D.C.
20503.
Thank you for your consideration in this matter. If you have any question on the evaluation process, please contact me at (215) 337-5211.
Sincerely, D w P\ ncb Peter W. Eselgroth, Chief PWR Section Operations Branch Division of Reactor Safety
Enclosures:
- 1. Reference Material Requirements
- 2. Administration of Requalification Examinations
- 3. NRC Rules and Guidance for Examinees 0FFICIAL RECORD COPY i
f, .. l Lt i' .
c l I cc w/ encl. 3 i T.-Magette, Administrator,-Nuclear Evaluations i- J. Walter,' Engineering Division, Public Service Commission of MD 1
!E G. Adams, Licensing (CCNPP) !
K. Burger,-Esquire, Maryland People's Counsel (
P. Birnie, Maryland Safe Energy Coalition Public Document Room (PDR)
Local -Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of Maryland (2) i
, bec w/ enc 1:
Region I Docket Room (w/ concurrences) !
Management Assistant, DRMA (w/o encl)
R. Bellamy, DRSS C. Cowgill, DRP ,
K. Lathrop, DRP M. Callahan, OCA D.-Mcdonald, NRR' J. Caldwell, EDO l B. Hughes, DRS f P. Eselgroth, DRS ,
OL Facility File DRS_ Files.(3) ,
v 0FFICIAL RECORD COPY
{
r rl -
th 07/, /90 07//# /90 07//0/90 *
)
i s
, i
. ES-601 i Rev 5 01/01/89 i
i ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS 1.
For the written examination, the following items must be provided to the :
NRC 60 days prior to the examination date: ;
Proposeo R0 and SR0 requalification written examination test items.
minimum of 350 per section of the examination.) (A s
Sincethe meet thefollowing:
written examination is open reference, examination items must a.
Items that require only memorization or recall are not permitted; ,
b.
Items should require that the examinee comprehend i interpret, integrate, or apply available information; i
- c. ;
Items should contain situations, aspects, or conditions that do not duplicate lesson plans or references; and a
d.
Items should require examinees to locate and use references.
L ,
be completed in 1-1/2 hours.The written examination will be compose Each section will be separate. Section A ;
will in a be administered classroom setting.on a static simulator; Section B will be administered Section A is designed to evaluate the operator's knowledge of plant tion and controls. In addition, systems, integrated plant operations, and instrumenta- '
recognition of Technical Specification LCOs evaluated. and the operator's ability to diagnose postulated events should be Section B of the written examination is designed to evaluate 1 the ability of the operator to analyze a given set of conditions and deter- '
mine the proper procedural and/or administrative guidance. ,
2.
All reference material and objectives for the proposed operating test items. '
For the simulation facility, the following items must be provided to the i NRC 60 days prior to the examination date: t i
a.
A minimum of 15 scenarios i' The scenarios should sample areas such as LERs, emergency and I
abnormal procedures, and design and procedural changes that exer-cise the crew's ability to use facility procedures in accident ,
prevention and mitigation. s The scenarios should evaluate each crew member as appropriate to his/her license, and shall exercise ,
r their abilities in the use of Emergency Operating Procedures.
Technical Specifications, and the Emergency Plan.
The scenario's
- net time (not including time spent on briefings, setup or simula-tion facility real time problems) should average 50 minutes, based upon performance.
ES-601 Rev 5 01/01/89 Enclosure 1 (Continued)'
For the plant walk through examination, the following items must be provide '
to the NRC 60 days prior to the examination date:
(1)
A list of systems and topics appropriate to the plant walk through examination that were covered during the requalification cycle and are important to safety. All reference material required to support an examination on these topics should be provided.
(2) Seventy five (75) job performance measures. i These performance measures should be both in plant and control
-of room theoperator facility. functions, that are required for the safe operation '
criteria. They shall include acceptable performance
.t 1
(3) Any additional reference material required for examination pre-paration will be requested by the examination team.
3.
A sampling plan shall be provided by the facility which indicates the '
ification training cycle. relative emphasis of topics which were included i
5 I
h 9
i
~
ES-608 Rev 5 02/01/89 ENCLOSURE 2 ADMINISTRATION OF REQUALIFICATION EXAMINATIONS
- 1. Twenty percent of the facility licensed operators shall be selected for evaluation. Normally the crew currently in the requalification cycle will be selected. A random sample without replacement will be used to preclude a satisfactory operator from being subject to reexamination by the NRC during the term of the license. The sample will include other shift (s) made up of licensed personnel who are not routinely performing shift duties.
- 2. The simulator and a simulator operator (s) will be provided for examination development. The date(s) and duration of time needed to develop the exami-nations will be agreed upon by the chief examiner and the facility.
- 3. The reference material used in the simulator will be reviewed by the chief examiner, No material will be used that is solely used for training.
4 A single room shall be provided for completing Section B of the written examination. The location of this room and supporting rest room facili-ties shall be such as to prevent contact with all other facility and/or
,- contractor personnel during the duration of the examination.
- 5. Minimum spacing is required to ensure examination integrity as determined by the chief' examiner. Minimum spacing should be one examinee per table, with a 3-foot space between tables. No wall charts, models other training materials shall be present in the examination room. , and/or
- 6. Copies of reference material for Section B of the written examination will be provided for each examinee. The reference material will be reviewed by the chief examiner and will consist of Technical Specifications, operating /
abnormal procedures, administrative procedures Emergency Plans as available to the plant operators.
- 7. Video taping capabilities may be utilized. The facility should contact the chief examiner for restrictions related to its usage.
8, Since common tasks and detailed systems knowledge will be probed during the walk through portion of the operating test, operators will be requested not.
to discuss the walk through with other examinees until after the complete examination has been administered.
- 9, An attempt will be made to distinguish between R0 and SRO knowledge and abilities to the extent that such a distinction is supported by the facil-ity. training materials.
t i
1 V
n -
7 '
- V ES-601 .
I g Rev 5 01/01/89- I j
ko
' ENCLOSURE 3 i
NRC RULES AND GUIDANCE FOR EXAMINEES '!
1.- Use black. ink.or dark pencil ONLY to facilitate legible reproductions.
2.. Print your name-in:the blank provided on the cover. sheet of the: examination.: -
3.: Fill in the.date on the cover sheet of the examination', if necessary.
4 Answer.each question on the examination. If additional paper is required, use only the lined paper provided by.the examiner.
- 5. 'Use abbreviations only if they rae commonly used in facility literature.
c' .,.
- 6. The point.value for each question is indicated in parentheses after the l auestion- and can be used as a guide for the depth of answer required. '
'7. Show all calculations, methods or assumptions used to obtain an answer to a, mathematical- problem, whether asked for~ in the. question or not.-
- 8. Unless solicited,.the location of references need not be stated.
9.- Partial credit.may be given. Therefore ANSWER. ALL PARTS OF_ THE QUESTION' AND D0'NOT LEAVE ANY ANSWERS BLANK. Par,tial credit will-NOT be given on multiple, choice ouestions.
10 .' If parts of the examination are not clear with respect.tostheir intent, askLquestions 'of' 9e examiner only. l t
- 11. ;You must sign the t...ement on the cover sheet that' indicates the' work on' the examination is your own and -that you have not . received or been given '
any assistance in completicg the examination. This must be signed AFTER the examination has been completed. t 1
- 12. Rest room trips are to be limited and only one examinee at a time:may leave.
,You must avoid all ' contact with anyone outside the' examination' room to .
j avoid even the appearcnce or possibility of examination compromise.
13 .' Chaating on the examination would result in a revocation of your. license I and-could result'in more severe penalties. i e
- 14. Each section of the examination is designed to take approximately 90- a
. minutes to complete. You will be given two~ hours to complete each section for a total of four nours. Each question has been time }'
validated, with the alloted time based on an average of knowledgeable f persons answering the question. You should be aware that the times 00 NOT allow for looking up and verifying each answer.
+ ,
- * . !. n t a;
} > ,
15.. Due to the' existence of questions that will require all examinees. to
, refer to the same indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of . compromise or appearance of cheating, m
- 16. ;When you are finished and have-turned in your completed examination, have the examination area.
- 17. Proportional grading will be applied. Any additional wrong information -
' that is provided may count against you. For example, if a question.is w
. porth one point and asks for four responses, each of~which is worth 0.25
' oints.
- 0,20' and you give five responses, each of your responses will be worth points.
If one of your five responses is incorrect 0.20 will be' deducted and your total credit for that question will be 0.80 instead of-1.00 even though you got the four correct answers.
L
- y.