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Category:CORRESPONDENCE-LETTERS
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 ML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl ML20211K9001999-08-27027 August 1999 Forwards Insp Repts 50-324/99-05 & 50-325/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant ML20210S9061999-08-11011 August 1999 Informs That GE Document Entitled, Addl Info Regarding 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20210S9121999-08-11011 August 1999 Informs That Document NEDC-31624P,Suppl 2,Rev 6,entitled, Loss-Of-Coolant Accident Analysis Rept for Brunswick Steam Electric Plant Unit 2,Reload 13,Cycle 14 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) ML20210P8221999-08-11011 August 1999 Advises That Info Contained in Which Submitted Document,Prepared by Siemens Power Corp,EMF-2168(P) Rev 0, Marked Proprietary,Will Be Withheld from Public Disclosure, Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20210P9381999-08-10010 August 1999 Forwards SE Accepting Licensee & Suppls & 0517,which Submitted Assessment of Impact on Operation of Unit 1 with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P8911999-08-10010 August 1999 Forwards SE Authorizing Relief Requests CIP-01,02,06,07,08, 09,10,11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Requests CIP-04 & 05 Would Result in Hardship,Relief CIP-03 Not Required & CIP-11 Denied in Part BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl ML20210Q4581999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section to Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit List of Individuals to Take exam,30 Days Before Exam Date ML20210P2031999-08-0505 August 1999 Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2 ML20210N2041999-08-0505 August 1999 Forwards SE Accepting Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46, & Suppl 1 BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld ML20210G2941999-07-28028 July 1999 Discusses Public Meeting Conducted on 990720 to Present Results of Periodic Plant Performance Review for Brunswick Facility for Period of May 1997 to January 1999.List of Attendees Encl BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld ML20210E1181999-07-19019 July 1999 Forwards Insp Repts 50-324/99-04 & 50-325/99-04 on 990509- 0619.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl ML20196H8191999-06-21021 June 1999 Informs That on 980915,Commission Suspended SALP Program for an Interim Period Until NRC Completes Review of Process for Assessing Performance at NPPs ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20196A8111999-06-14014 June 1999 Ack Receipt of 990401 Response to NRC Ltr Issued on 990302 Re OI Investigation to Determine Whether Former BSEP Manager Threatened to Fire Employees Who Brought Safety Concerns to Nrc.Concluded That No Violation Occurred ML20195J1971999-06-14014 June 1999 Advises That GE-NE-523-B13-01920-56,Rev 1,submitted with 990202 Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G5581990-11-23023 November 1990 Forwards Insp Repts 50-324/90-44 & 50-325/90-44 on 901022- 26.No Violations or Deviations Noted ML20062G3851990-11-19019 November 1990 Forwards Insp Repts 50-324/90-41 & 50-325/90-41 on 901002-1104.Violations Noted ML20058G5671990-11-0808 November 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/90-25 & 50-325/90-25 ML20062D3921990-11-0505 November 1990 Forwards Insp Repts 50-324/90-46 & 50-325/90-46 on 901017.No Violations or Deviations Noted ML20058H4371990-11-0101 November 1990 Forwards Summary of 901016 Enforcement Conference Re Events Surrounding 900819 Unit 2 Reactor Scram ML20058E9681990-10-30030 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/90-29 & 50-325/90-29 ML20058F3061990-10-29029 October 1990 Forwards Insp Repts 50-324/90-42 & 50-325/90-42 on 900924-28.No Violations or Deviations Noted ML20058B0511990-10-18018 October 1990 Forwards Insp Repts 50-324/90-37 & 50-325/90-37 on 900908-1001.Violations Noted ML20058B1141990-10-18018 October 1990 Forwards Insp Repts 50-324/90-32 & 50-325/90-32 on 900806-10.No Violations or Deviations Noted ML20059M7961990-09-20020 September 1990 Ack Receipt of Util 900806 Response & 900629 & 0308 Supplemental Responses to NRC 900308 Notice of Violation ML20059M6391990-09-19019 September 1990 Forwards Augmented Insp Team Insp Repts 50-325/90-36 & 50-324/90-36 on 900821-25 ML20059M1731990-09-13013 September 1990 Forwards Summary of 900806 Meeting in Atlanta,Ga Re Corporate Emergency Preparedness & Recent Drill Performance. List of Attendees & Viewgraphs Encl IR 05000324/19900191990-09-0505 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/90-19 & 50-325/90-19 ML20059M3591990-08-30030 August 1990 Discusses Region II 900808 Review of Emergency Response Facilities Focusing on Availability of Workspace & Communications for NRC Personnel in Event Agency Response Warranted.Summary of Mods/Additions to NRC Resources Encl ML20059H3271990-08-29029 August 1990 Forwards Summary of 900815 Meeting W/Util in Region II Ofc to Discuss Corrective Action Plan Re Requalification Program.List of Attendees Encl ML20059K8291990-08-27027 August 1990 Forwards Insp Repts 50-325/90-31 & 50-324/90-31 on 900730-0803.No Violations or Deviations Noted ML20059J0201990-08-24024 August 1990 Forwards Insp Repts 50-324/90-28 & 50-325/90-28 on 900723-27.No Violations or Deviations Noted ML20059D0261990-08-24024 August 1990 Forwards Partially Withheld Safeguards Insp Repts 50-324/90-30 & 50-325/90-30 on 900730-0803.No Violations or Deviations Noted ML20059H0751990-08-23023 August 1990 Forwards Insp Repts 50-324/90-26 & 50-325/90-26 on 900701-31 & Notice of Violation ML20058Q3961990-08-15015 August 1990 Forwards NRC Operational Evaluation Repts 50-324/OL-90-04 & 50-325/OL-90-04 on 900725 & 26 ML20058Q2231990-08-0303 August 1990 Forwards Corrected Summary Page for Insp Repts 50-324/90-27 & 50-325/90-27,per ML20056A7711990-08-0202 August 1990 Forwards Fr Notice of Withdrawal of 900419 Application to Amend Tech Spec 4.8.1.1.2.d.1 to Allow One Time Only Extension of Surveillances Until 901031 ML20059A7201990-08-0101 August 1990 Forwards Insp Repts 50-325/90-27 & 50-324/90-27 on 900709-12.No Violations or Deviations Noted ML20056A4871990-07-27027 July 1990 Confirms 900815 Mgt Meeting in Atlanta,Ga to Discuss Issues Re Operator Training Program,Including Root Cause & Corrective Actions,Shortcomings in Root Cause Analysis, Scheduling Future Insps & Integration of Action Plan Items ML20058L7041990-07-27027 July 1990 Confirms 900806 Mgt Meeting W/Util in Atlanta,Ga to Discuss Recent Significant Potential for Personnel Overexposure ML20058L7281990-07-26026 July 1990 Forwards Insp Repts 50-324/90-25 & 50-325/90-25 on 900709-13.Violations Noted & Under Consideration for Escalated Enforcement Action ML20058L7381990-07-25025 July 1990 Ack Receipt of 900628 Response to Confirmation of Action Ltr Re Results of Root Cause Analysis for Failures of Requalification Exam & Operational Evaluation & Associated long-term Corrective Action Plan ML20056A9071990-07-17017 July 1990 Forwards Insp Repts 50-324/90-19 & 50-325/90-19 on 900601-30 & Notice of Violation ML20058L7731990-07-16016 July 1990 Forwards Operational Evaluation Repts 50-324/90-03 & 50-325/90-03 on 900609-10.Results of Evaluations Discussed ML20055H4291990-07-13013 July 1990 Forwards Insp Repts 50-324/90-22 & 50-325/90-22 on 900611-15.No Violations or Deviations Noted ML20055F6951990-07-13013 July 1990 Advises That Util 900502 Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plant' Per 10CFR50.54(f) Meets All Guidance Provided in Generic Ltr ML20055H4111990-07-11011 July 1990 Forwards Insp Repts 50-324/90-23 & 50-325/90-23 on 900611-15.No Violations or Deviations Noted.Insp Concluded That Adequate Control Over Engineering Work Requests Existed IR 05000324/19900021990-07-11011 July 1990 Documents 900610 Approval for Restart of Plant in Confirmation of Action Ltrs 50-324/90-02 & 50-325/90-02 on 900521 ML20055H4551990-06-28028 June 1990 Confirms 900622 Telcon Scheduling 900823 Mgt Meeting at Plant Site Re Status of Integrated Action Plan & Schedule for Upcoming Unit 1 Refueling Outage ML20055H3861990-06-27027 June 1990 Forwards Insp Repts 50-324/90-21 & 50-325/90-21 on 900521- 25.No Violations or Deviations Noted.Separate Insp to Review Engineering Work Requests Scheduled Due to Concerns Raised in Area IR 05000324/19900141990-06-26026 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.NRC Understands That Supplemental Response Will Be Issued by 900723 Re Improvement of Equipment Anomalies ML20059M8571990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20248F1341989-09-28028 September 1989 Forwards Insp Repts 50-324/89-30 & 50-325/89-30 on 890905-08.No Violations or Deviations Noted ML20248C8621989-09-26026 September 1989 Forwards Insp Repts 50-325/89-24 & 50-324/89-24 on 890814-18.No Violations or Deviations Noted.Unresolved Item Noted ML20248C4621989-09-22022 September 1989 Forwards Corrected Pages to Insp Repts 50-324/89-22 & 50-325/89-22 ML20248A9041989-09-22022 September 1989 Forwards Insp Repts 50-324/89-20 & 50-325/89-20 on 890801-31 & Notice of Violation.Particular Attention in Response to Identification of Root Cause of Problem of Similarity to Violation Noted in Notice Forwarded by Requested ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu IR 05000324/19890111989-09-15015 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/89-11 & 50-325/89-11 ML20247L1301989-09-14014 September 1989 Forwards Insp Repts 50-324/89-27 & 50-325/89-27 on 890824-25.No Violations or Deviations Noted ML20247K1511989-09-12012 September 1989 Forwards Summary of 890907 Meeting W/Util Re Self Assessment of Plant.Meeting Provided Better Understanding of Actions to Promote Improvement During Stated SALP Period ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247D7061989-09-0707 September 1989 Forwards Insp Repts 50-324/89-22 & 50-325/89-22 on 890724-28.No Violations or Deviations Noted ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM 1990-09-05
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified ML20211K9001999-08-27027 August 1999 Forwards Insp Repts 50-324/99-05 & 50-325/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20210S9061999-08-11011 August 1999 Informs That GE Document Entitled, Addl Info Regarding 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20210P8221999-08-11011 August 1999 Advises That Info Contained in Which Submitted Document,Prepared by Siemens Power Corp,EMF-2168(P) Rev 0, Marked Proprietary,Will Be Withheld from Public Disclosure, Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20210S9121999-08-11011 August 1999 Informs That Document NEDC-31624P,Suppl 2,Rev 6,entitled, Loss-Of-Coolant Accident Analysis Rept for Brunswick Steam Electric Plant Unit 2,Reload 13,Cycle 14 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) ML20210P8911999-08-10010 August 1999 Forwards SE Authorizing Relief Requests CIP-01,02,06,07,08, 09,10,11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Requests CIP-04 & 05 Would Result in Hardship,Relief CIP-03 Not Required & CIP-11 Denied in Part ML20210P9381999-08-10010 August 1999 Forwards SE Accepting Licensee & Suppls & 0517,which Submitted Assessment of Impact on Operation of Unit 1 with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210Q4581999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section to Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit List of Individuals to Take exam,30 Days Before Exam Date ML20210P2031999-08-0505 August 1999 Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2 ML20210N2041999-08-0505 August 1999 Forwards SE Accepting Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46, & Suppl 1 ML20210G2941999-07-28028 July 1999 Discusses Public Meeting Conducted on 990720 to Present Results of Periodic Plant Performance Review for Brunswick Facility for Period of May 1997 to January 1999.List of Attendees Encl ML20210E1181999-07-19019 July 1999 Forwards Insp Repts 50-324/99-04 & 50-325/99-04 on 990509- 0619.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20196H8191999-06-21021 June 1999 Informs That on 980915,Commission Suspended SALP Program for an Interim Period Until NRC Completes Review of Process for Assessing Performance at NPPs ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195J1971999-06-14014 June 1999 Advises That GE-NE-523-B13-01920-56,Rev 1,submitted with 990202 Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20196A8111999-06-14014 June 1999 Ack Receipt of 990401 Response to NRC Ltr Issued on 990302 Re OI Investigation to Determine Whether Former BSEP Manager Threatened to Fire Employees Who Brought Safety Concerns to Nrc.Concluded That No Violation Occurred ML20195H6931999-06-0707 June 1999 Forwards Insp Repts 50-324/99-03 & 50-325/99-03 on 990328-0508.Two Violations Noted & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20195E8721999-05-28028 May 1999 Informs That Meeting Re Recently Completed Plant Performance Review for Licensee Facility Scheduled for 990720 ML20207B6081999-05-27027 May 1999 Informs That Staff Finds That RWCU Sys Piping Outboard of Second CIV at Bsep,Units 1 & 2,meets Staff Criteria of Schedule a as Delineated in Encl.Licensee Proposal to Eliminate Augmented Insp Per GL 88-01,acceptable ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML20206G1811999-05-0404 May 1999 Forwards SE Approving Three of 25 Relief Requests Submitted by for Third 10-year ISI Program.Remaining Reliefs Will Be Evaluated in Separate SEs ML20206B9291999-04-26026 April 1999 Forwards Insp Repts 50-324/99-02 & 50-325/99-02 on 990214-0327.Three Violations Being Treated as non-cited Violations ML20206A1561999-04-0909 April 1999 Informs That on 990316,M Herrell of CP&L & Author Confirmed Initial Operator Licensing Exam Schedule for Y2K. Initial Exam Dates Will Be Wks of 000214 & 20 for Approx 16 Candidates.Nrc Will Write Exam ML20205J9121999-03-31031 March 1999 Informs That Effective 990328,A Hansen Became NRR Licensing Project Manager for Brunswick Steam Electric Plant,Units 1 & 2 ML20205F8681999-03-30030 March 1999 Discusses Approval of Change to EP Eliminating Incorporation of Technical Support Center Into Protected Area.Forwards SE Related to Location of Technical Support Center ML20205D5541999-03-30030 March 1999 Discusses Core Shroud Reinsp Plan Submitted by CP&L on 980828 & 981221 for BSEP Unit 2 Refueling Outage 13 (B214R1) Scheduled to Begin on 990417.Concludes That Proposed Reinsp Plan & Schedule for Reinsp of Weld H5 Acceptable ML20205D2931999-03-23023 March 1999 Advises of NRC Planned Insp Effort Resulting from Plant PPR Completed on 990204,to Develop Integrated Understanding of Safety Performance.Historical Listing of Plant Issues & Details of Insp Plan for Next Eight Months Encl ML20204J8071999-03-18018 March 1999 Forwards Insp Repts 50-324/98-14 & 50-325/99-14 on 990111-15,25 & 29.Violations Being Treated as non-cited Violations ML20204J7241999-03-15015 March 1999 Forwards Insp Repts 50-324/99-01 & 50-325/99-01 on 990103- 0212.No Violations Noted.Five Violation Being Treated as non-cited Violations ML20207H4291999-03-0202 March 1999 Discusses NRC OI Rept 2-1998-014 on 980429-990112.NRC Determined That There May Have Been Atmosphere at BSEP Such That Employees Were Reluctant to Report Safety Problems. Requests Written Response Re Position on Environ ML20203D5831999-02-10010 February 1999 Forwards Biological Opinion for CP&L Review & Comment Re Impact on Endangered Sea Turtles of Operation of Brunswick Steam Electric Plant ML20203D6871999-02-0909 February 1999 Forwards SER Accepting Licensee 980225 & 0806 Relief Requests PRR-02,VRR-02,VRR-03,VRR-05,VRR-11,VRR-12 & RFJ-03, Associated with Third 10-year Interval Inservice Testing Program for Brunswick Steam Electric Plant,Units 1 & 2 ML20203G5371999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20202J5761999-01-28028 January 1999 Forwards Insp Repts 50-324/98-11 & 50-325/98-11 on 981122-990102.No Violations Noted.Evaluated 990120 Response to NOV 50-325/98-10-03 & Found Response Meets Requirements of 10CFR2.201 ML20199K9921999-01-22022 January 1999 Ack Receipt of Util 990112 Withdrawal of Request for Exemption, from 10CFR70.24 Requirements for Criticality Monitoring Sys in Areas of Brunswick Steam Electric Plant ML20199G7621999-01-15015 January 1999 Responds to Util ,As Supplemented by 980225 & 0520 Ltrs,Describing Spring 1998 Core Shroud Reinspection Plan for Unit 1.NRC Found Plan Acceptable ML20199K3071999-01-14014 January 1999 Informs That on 990117,Region II Will Implement Staff Reorganization as Part of agency-wide Streamlining Effort. Copy of Organization Charts for Info Encl ML20198P0121998-12-28028 December 1998 Ltr Contract:Task Order 35, Brunswick Safety Sys Engineering Insp, Under Contract NRC-03-98-021 ML20206R8781998-12-23023 December 1998 Provides Summary of 981105 Training Managers Conference Held in Atlanta,Georgia.Conference Agenda,List of Conference Attendees,Presentation Slides & Preliminary Schedule for FY99 & FY00 Encl ML20198P4621998-12-21021 December 1998 First Partial Response to FOIA Request for Documents. Documents Listed in App A,Already Available in Pdr.Documents Listed in App B,Being Release in Their Entirety.Documents Listed in App C,Withheld in Part (Ref FOIA Exemption 6) ML20198P0211998-12-21021 December 1998 Forwards Insp Repts 50-324/98-10 & 50-325/98-10 on 981011- 1121 & Nov.Two Violations of NRC Requirements Identified. Violation a of Concern Because NRC Identified Two Standby Gas Treatment Sys Valves Out of Position ML20198C6641998-12-17017 December 1998 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, Issued on 980506 ML20196F5151998-12-0202 December 1998 Forwards RAI Re Extension of Balance of Plant & Emergency Electrical Bus Aot,Submitted as Part of Application for Converting to ITS for Plant,Units 1 & 2 Dtd 961101.Response Requested within 30 Days from Receipt of Ltr ML20196G2481998-11-25025 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting on 981102.Insp Plan for Next 4 Months & Historical Listing of Plant Issues,Called Plant Issues Matrix, Encl ML20196D4831998-11-24024 November 1998 Forwards Insp Repts 50-324/98-13 & 50-325/98-13 on 981026-30.No Violations Noted.Rept Partially Withheld Ref 10CFR73.21 ML20196D6481998-11-20020 November 1998 Informs That Ssei Repts 50-324/99-01 & 50-325/99-01 at Brunswick Facility Have Been Scheduled for 990111-15 & 25-29.Insp Objective Will Be to Evaluate Capability of Hpci& RCIC Sys to Perform Safety Functions Required ML20196C9921998-11-13013 November 1998 Informs That on 981007,NRC Administered Generic Fundamentals Exam Section of Written Operator Licensing Exam.Copy of Answer Key & Master Bwr/Pwr Encl,Even Though Util Did Not Participate in Exam.Without Encls ML20195G4121998-11-0909 November 1998 Forwards Insp Repts 50-324/98-09 & 50-325/98-09 on 980830-1010.NRC Concluded That Info Re Reasons for Violation & C/A Taken & Planned to Correct Violation & Prevent Recurrence,Already Adequately Addressed in Encl Insp Rept ML20155C6771998-10-27027 October 1998 Forwards Audit Rept on Year 2000 Program for Plant,Units 1 & 2,conducted on 981006-09 as Followup to NRC GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Issued on 980511 1999-08-05
[Table view] |
Text
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Docket' Nos. 50-324 and 50-325 CPPR-67 and 68 Carolina Power & Light Company ATTN: Mr. J. A._ Tones Senior Vice President Engineering & Operating Group 336.Fayetteville Street Raleigh,' North Carolina 27602 Gentlemen:
With' your letter dated November'9, 1970, you provided forty copies of a document'containing the following 7esign Reports:
- 1. 9esign Report No. 4 'BSEP DR-4) titled " Seismic Analysis of the Primary and Secondary Containments."
- 2. Design Report No. 5 'BSEP 9R-5) titled " Final Report, Test Fill Program Results and Backfill Recousnendations for Class I Backfill, Brunswick Steam Electric Plant, Southport, North Carolina."'
- 3. ~ Design Report No. 6'(BSEP DR-6) titled " Final Report, Test Fill
. Program Results and Backfill Reconnendations for Class II Backfill, Brunswick Steam Electric Plant, Southport, North Carolina."'
To complete our review'df the above described document in connection with j our review of those metters on the Brunswick Plant that were deferred for resolution during construction, we need additional information on the matters addressed'in Design Report No. 4. The specific information requested is described in the enclosure.
A timely conclusion of our review of this matter requires that you submit the requested information as soon as possible. 'Please contact us if you desire additional discussion or clarification of the material requested.
Sincerely.
Ori;in:1.icn:d by F. Schrx 'er e er A. Po M s O actor
.0709280091 PDR pogg 870921 -[ Division of Reactor Licensing NENZB7-111 PDR /
Enclosure:
StN'ci tt!a ched.. . . . . . . . . . . . . ,
SURNAME > . . . , , , , , , , . . , , ,, , , , ,, , ,, , ,
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i Carolina Power & Light Company 2
Enclosure:
Request for Additional Information cc: George F. Trowbridge, Esq.
Shaw, Pittman, Potts, Trowbridge & Madden 916 17th Street, N. W.
Washington, D. C. .
200 %
Distribution:
Docket (2)
AEC PDR (2)
'DR Reading DRL Reading BWR-1 File .
CKBeck MMMann SHanauer FSchroeder.
RSBoyd RDeYoung.
DSkovholt TRWilson EGCase RRMaccary PWHowe ,
BGrimes DRL/DRS Br. Chiefs SMKari WRButler DKartalia, OGC Compliance (2)
ACRS (16)
WNyer (2)
Newmark & Hall (2)
(PAGE 1 and Enclosure rewritten per FSchroeder. See attached for previous letter and enclosure.) (12-28-70) m omcr > ..DRh,/,B,WR ,1 , DRL/,BWR-1 RL/AD WR Dg, ,
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l REQUEST FOR ADDITIONAL INFORMATION DOCKET NOS. 50-324 & 50-325 l l
- 1. The assalyses using the single degree of freedom modal method described in Design Report No. 4 may not be adequate for the multi-mass Brunswick System. Provide the basis for and indicate the conservatism in the use
-of this method by demonstrating that the results obtained are equivalent l to those obtained by a multi-mass time history method applicable to I i
the Brunswick site, 2., Provide the design criteria to be used to account for conditions that are present when the structure, equipment and piping are in resonance with each other.
- 3. Provide the design criteria and analytical procedures applicable to piping that take-into account the differential movement between floors and equipment at different elsvations.
- 4. In Section VI-5.0 of Design Report No. 4, you state that seismic testing will be- performed for systems and components that are not readily analyzed.
Explam why seismic testing will not be performed on all vital systems aed components except where it is impractical or impossible to do so.
.5 In Section VI-8.2-a-1 of Design Report No. 4, you specify an upper bound of "...less than 0.5 g..." for seismic testing. What i5: the lower bound acceleration for these tests?
- 6. Explain why the proposed seismic testing program for vital instrumentation and control equipment does not include operating mode tests to determine if spurious a: tion, or system failure, will result.
OFFICE > , , ,, , ,
SURNAME > , ,, ,, , _ , ,,
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l Docket Nos. 50-324 [ gMc M* " * \
CPPR-67 nd 6 Mb#
& u) , &+W A% qr Q1s., AY'Dn, '
Carol Power & Light Company ;/
ATIN: b J. A. Jones y Se r Vice President /
Engineering Operating Group /
336 Fayettevi le Street
'/ \/
Raleigh, North %rolina 27602
\ /
Gentlemen:
With your letter dateh November 9,1970, you provided forty ) copies of a document containing the foll,owing Design Reports:
~
- 1. Design Report No. 4 (BSEP DR-4) titled " Seismic Analysis of the Primary and Secondary, containments."
. /
- 2. Design Report No. 5 (BS DR-5) titled " Final Report, Test Fill Program Results and Ba fill Recounsendations for Class I Backfill, Srunswick Steam Elect c Plant, Southport, North Carolina."
- 3. Design Report No. 6 .BSEP DR-6) titled " Final Report, Test Fill
/ Program Results and Backfill Recoussendations for Class II Backfill, Brunswick Steam El ctric Plant, Southport, North Carolina." - : ,
Lc" 6 / d ' ur b )" We b M d -
I
__ ___f eview of the above described documen we heardensad 2_
6 addition ~ infor:sstion on the matters dddressed, n Design. ,-
Report No. 4. ~0 7 o a (p th r milar- that ti (/ ;
w ,et e ve ,
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spTclfic irifo ion Y:T*. is described in the enclo __%rv. ,...- . r l' %
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cs A timely con usion of our review of this matter requires that you sub-mit the re sted information as soon as possible. Please ,._11 _ i h /J b /
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Sincerely,
- ';;;r A. Merri;, Dir;;ter 1 omcr > . . . . . . . .. .. .
. D.ivis. ion . o f, Rea c t or. , Li c hn s ing , , _ , , , , , ,
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see attached l ,
. . .., . .,((N ;- - """ "" -
REnUEST FOR ADDITIONAL INFORMATION j
%Q9
_ DOCKET NOS. 50-324 & 50-325 ,,- ,7 jf
- 1. The emara=9 M the single degree of freedorar mo$ method
,./ ':x h<h, multi-mass Br swickDesign described in t!ER System.Report No. 4 may not be adequate for the C{
the conservatism Provide the basis for and indicate Qquer:1: a . - in the use of this method by demonstrating theBrunswicksitehJ a gulti-mass time history method applicable '/ % / Q to
% c. -
~
- 2. \ / . f d' t.4 /
Provide the design criteria to be,osed to account for conditions that -
with each other.are present when the sebycture, s'quipment and piping are N..'A' in resonance
\ / ,,
\ /
- 3. Provide the design criteriar#
ded analytical procedures applicable to piping that take floors and equipment at into ace 'nt the differential movement between ifferents, eleva tions.
4.
willbhperformedfo,rsgtysandcomponentsthaInSectionVI-5.0 are not readily analyzed.
all vital syst M ::LbCi r wnf' n seismic testing '
and components except wh'ere it oc h be performed on to do so. He .4, L,- .< ' s impractical or impossible
- g. _ _ _ . I, .
- 5. In Section bound the low of ' . . . less than 0.5 g. . ." for seismic W :: testing.I-8.2-a-1 of D bound decelerations for these tests? '
n-. ^ M'1 das n
- 6. '"
S and Q f' f why the proposed seismic testing program for vit if ontrol equipment does not include operating mode test.g to determine purious action, or system failure, will result.
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l Form AEC.318 (nn, s-63) g u.5 Gomuunenwrmcrraanse o-w " '##
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