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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-99-0153, 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-99-0147, 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-99-0151, 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-99-0149, 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-99-0150, 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-99-0112, 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-99-0148, 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-99-0130, 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-99-0132, 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 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 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 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-99-0110, 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-99-0123, 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 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-99-0127, 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 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 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 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 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 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 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) 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-99-0090, 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:INCOMING CORRESPONDENCE
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 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-99-0153, 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-99-0147, 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-99-0151, 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 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-99-0141, 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-99-0148, 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-99-0130, 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-99-0132, 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 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 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 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 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 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 BSEP-99-0092, Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld1999-06-0808 June 1999 Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld BSEP-99-0085, Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld1999-05-27027 May 1999 Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld BSEP-99-0078, Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT1999-05-17017 May 1999 Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT BSEP-99-0080, Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval1999-05-17017 May 1999 Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval BSEP-99-0083, Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6)1999-05-14014 May 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6) BSEP-99-0056, Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively1999-05-13013 May 1999 Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively BSEP-99-0073, Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by1999-05-12012 May 1999 Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by BSEP-99-0062, Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.171999-05-11011 May 1999 Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.17 BSEP-99-0079, Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-05-0707 May 1999 Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0066, Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided1999-05-0404 May 1999 Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided ML20195D6301999-04-30030 April 1999 Forwards Natl Marine Fisheries Svc Biological Opinion Based on Review of Continued Use of Cooling Water Intake Sys at Bsep.Rept Reviews Effects of Activity on Loggerhead,Kemps Ridley,Green,Hawksbill & Leatherback Sea Turtles BSEP-99-0071, Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6)1999-04-27027 April 1999 Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6) BSEP-99-0069, Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-171999-04-26026 April 1999 Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-17 BSEP-99-0063, Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link1999-04-21021 April 1999 Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link BSEP-99-0050, Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping,1999-04-0606 April 1999 Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, BSEP-99-0051, Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 21999-04-0101 April 1999 Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 2 BSEP-99-0015, Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-03-31031 March 1999 Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A8161990-09-14014 September 1990 Forwards Info Re Performance of NDE Exam of Feedwater Nozzles & Safe Ends During 1989/1990 Maint/Refueling Outage, Per NUREG-0619,Section 4.4.3.1(2) ML20059L0911990-09-12012 September 1990 Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML20059G2881990-09-0606 September 1990 Forwards Proprietary NEDC-31624P,Rev 2,Class III, Brunswick Steam Electric Plant Units 1 & 2 SAFER/GESTR-LOCA LOCA Loss of Coolant Accident Analysis, for NRC Approval.Rept Withheld ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty BSEP-90-0579, Informs That Util Plans to Replace Pilot Valve Assemblies on Listed Safety Relief Valves Prior to Startup1990-08-24024 August 1990 Informs That Util Plans to Replace Pilot Valve Assemblies on Listed Safety Relief Valves Prior to Startup BSEP-90-0564, Forwards Response to Violations Noted in Insp Repts 50-324/90-19 & 50-325/90-19.Corrective Actions:Procedures to Shutdown Reactor Feed Pump Using Manual Control Approved on 900627 & Real Time Training Provided to Operators1990-08-16016 August 1990 Forwards Response to Violations Noted in Insp Repts 50-324/90-19 & 50-325/90-19.Corrective Actions:Procedures to Shutdown Reactor Feed Pump Using Manual Control Approved on 900627 & Real Time Training Provided to Operators BSEP-90-0565, Responds to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06.Corrective Actions:Personnel Counseled on Closure of Locked High Radiation Area Doors & Preventive Maint Program Established for Reactor & Turbine Bldg Gates1990-08-16016 August 1990 Responds to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06.Corrective Actions:Personnel Counseled on Closure of Locked High Radiation Area Doors & Preventive Maint Program Established for Reactor & Turbine Bldg Gates ML20058N1671990-08-0909 August 1990 Forwards Updated Tech Spec Pages Re 900314 Application for Amends to Licenses DPR-71 & DPR-62.Amends Permit Removal of Rod Sequence Control Sys & Reduces Rod Worth Minimizer Cutoff Setpoint to 10%-rated Thermal Power BSEP-90-0535, Forwards Monthly Status Rept on Plant Integrated Action Plan.New Target Completion Date for D27 Will Be 9008151990-08-0707 August 1990 Forwards Monthly Status Rept on Plant Integrated Action Plan.New Target Completion Date for D27 Will Be 900815 ML20056A6931990-08-0707 August 1990 Advises of Plans to Complete Remaining Portions of Licensed Operator Requalification Exams During Oct-Dec 1990 BSEP-90-0545, Forwards Monthly Operating Rept for Jul 1990 for Brunswick Steam Electric Plant Units 1 & 2 & Corrected Operating Data Rept for June 1990,Unit 21990-08-0303 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Brunswick Steam Electric Plant Units 1 & 2 & Corrected Operating Data Rept for June 1990,Unit 2 ML20063Q0501990-08-0303 August 1990 Forwards Corrections to Plant Updated Fsar,Amend 8,per ML20056A0291990-07-30030 July 1990 Forwards Response to NRC 900206 Request for Addl Info Re Util 870817 License Amend Request,Extending Expiration Dates for OLs ML20056A0611990-07-27027 July 1990 Advises That Util Plans to Perform Next Integrated Leak Rate Test During Next Reload 8 Outage,Currently Scheduled for Sept 1991 ML20056A1801990-07-25025 July 1990 Forwards Info Re NPDES Permit Noncompliance Reported to Permit Agency for Month of Mar 1990,per 830426 Agreement BSEP-90-0524, Informs of Change to Info in NRC Insp Repts 50-324/90-01 & 50-325/90-01 Paragraph 3.b of Details1990-07-24024 July 1990 Informs of Change to Info in NRC Insp Repts 50-324/90-01 & 50-325/90-01 Paragraph 3.b of Details ML20055G6771990-07-20020 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.Corrective Actions:Event Included in Third Quarter Real Time Training for Personnel, Emphasizing Importance of Detection of Plant Deficiencies ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices BSEP-90-0459, Suppls Response to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06 Re Locked High Radiation Area Boundary.Three Options to Eliminate Design Problems W/Locked High Radiation Boundaries Will Be Submitted by 9008171990-06-29029 June 1990 Suppls Response to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06 Re Locked High Radiation Area Boundary.Three Options to Eliminate Design Problems W/Locked High Radiation Boundaries Will Be Submitted by 900817 ML20058K3551990-06-28028 June 1990 Responds to NRC Confirmation of Actions Ltr Re Licensed Operator Training Program Review.Curriculum Development Unit of Nuclear Training Section Will Develop Self Assessment Criteria to Increase Effectiveness of Training Program ML20055D2751990-06-28028 June 1990 Informs That Senior Operator License SOP-20687 for Rj Zuffa No Longer Needed & Should Be Terminated Upon Receipt of Ltr ML20055D7881990-06-27027 June 1990 Forwards Updated Tech Spec Pages to 890329 Application for Amends to Licenses DPR-71 & DPR-62 to Permit Expanded Operating Domain for Facility ML20055C8201990-06-18018 June 1990 Forwards Rev 0 to Rept of 1989/90 Inservice Insp for Brunswick Steam Electric Plant Unit 2, Per ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA 6220(b) ML20055H5501990-06-14014 June 1990 Discusses Confirmation of Concurrence Re Qualification of Fifth Operating Shift.Util Determined That Crew C Will Be Prepared for NRC Testing by 900723 & 24 to Provide Fifth Crew ML20043G4711990-06-13013 June 1990 Forwards Tech Specs to Support 900228 License Amend Request Re Fuel Cycle 8 Reload ML20043G4671990-06-13013 June 1990 Forwards Proposed Tech Specs Re Turbine Control Valves & Fire Detectors,To Support 900315 License Amend Request ML20043G4701990-06-13013 June 1990 Withdraws 900419 Request for License Amend Re one-time Extension of Diesel Generator Surveillance Interval.Util Investigating Methods of Dealing W/Situation & Will Keep NRR Project Manager Informed of Plans ML20043F1921990-06-0606 June 1990 Advises of Intentions to Delay Submittal of Permanent Change to Tech Spec 3/4.8.1,pending Resolution of Lessons Learned from Incident at Plant ML20043F0431990-06-0606 June 1990 Advises That Correct Date for Remedial Exercise Is 900622, Per Insp Repts 50-324/90-13 & 50-325/90-13.Procedures Will Be Revised by 900706 to Ensure Adequate Accountability for All Personnel within Protected Area ML20043C9021990-06-0101 June 1990 Responds to Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.Corrective Actions:Box Cover Closed Following Notification of Discrepancy & Human Performance Evaluation Initiated to Ensure Proper Corrective Actions Initiated ML20043D1851990-05-30030 May 1990 Forwards Response to NRC 900206 Request for Addl Info Re Util 870817 Proposed Change to Expiration Dates of Ols. Responses to Remaining Questions Will Be Submitted by 900629 ML20043B7821990-05-25025 May 1990 Responds to Violations Noted in Insp Repts 50-324/88-36 & 50-325/88-36.Allowable Working Loads for 1/2-inch Hilti Anchor Bolts Currently Used at Facilities Adequate Per NRC Info Notice 86-094.No Further Action Planned ML20043A3941990-05-16016 May 1990 Forwards Tech Spec Re 900419 Amend Request for One Time Extension of Diesel Generator Surveillance Requirements ML20043G4991990-05-14014 May 1990 Forwards Corrected Graph for 900531 Integrated Action Plan Status Rept Illustrating Level 1 Items Projected as of 900331 ML20042G5411990-05-0909 May 1990 Forwards Response to Request for Addl Info Re 891010 License Amend Request to Raise Allowable Containment Leak Rate from 0.5 to 1.0 Vol Percent Per Day.Core Thermal Power Level to Be Used in Calculation Is 2,550 Mwt ML20042F6111990-05-0202 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' Plant Procedures Provide Adequate Guidance for Operation of Overfill Protection Sys ML20042E8531990-04-27027 April 1990 Discusses Relocation of Primary/Secondary Containment Isolation Valve Listings to Plant Procedures.Relocation Will Help Avoid Future Expenditure of NRC Resources for Review & Processing of License Amend Requests ML20042E7281990-04-27027 April 1990 Provides Tech Spec Interpretation Evaluation of Offsite/ Onsite Electrical Distribution Sys,Per NRC Request During 900123 Telcon.Submittal of Amend Request Will Be Made by 900531 ML20012F4871990-04-0606 April 1990 Forwards Response to Regulatory Effectiveness Review.Encl Withheld (Ref 10CFR73.21) ML20012F4701990-04-0404 April 1990 Forwards Addl Info to Support Util Finding of NSHC for 900228 Application for Amend to License DPR-71,revising MCPR Safety Limit Specified in Tech Spec 2.1.2 from 1.04 to 1.07 for Unit 1,Cycle 8 Operation ML20042E1421990-04-0303 April 1990 Forwards Monthly Status Rept on Plant Integrated Action Plan ML20012E8681990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Per NUMARC 900104 Request.One Change to Coping Assessment Calculation Was Necessary & Deviations from NUMARC 87-00 Methodology Identified ML20012E4621990-03-27027 March 1990 Discusses Licensee Response to NRC 891010 Request for Recirculation Pipe Welds.Ultrasonic Testing Records Package on Weld Samples Assembled & Given to BNL During 891206 Facility Visit.Requested Welds Shipped to BNL on 900301 ML20012D9761990-03-22022 March 1990 Responds to Insp Repts 50-324/88-36 & 50-325/88-36 Re Util Response to IE Bulletin 79-02.Verification That Pipe Support Base Plate Flexibility Accounted for in Calculation of Anchor Bolt Loads Addressed ML20012C4601990-03-15015 March 1990 Forwards Control Loop Voltage Drop Calculation Inadvertently Omitted from 900313 Ltr Providing Addl Info Re Ari/Rpt ML20012E1701990-03-13013 March 1990 Forwards Addl Info Re Ari/Rpt Sys Power Supply,Per NRC 900110 Request ML20012A4271990-02-28028 February 1990 Forwards Rev 0 to Brunswick Unit 2,Cycle 9,Core Operating Limits Rept. ML20012A2491990-02-28028 February 1990 Forwards Supplemental Response to Violations Noted in Insp Repts 50-324/89-26 & 50-325/89-26.Corrective Actions:Ncr S-89-089 Initiated on F075 Event & Involved Operations Personnel Counseled on Events ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20011F3371990-02-23023 February 1990 Forwards Corrected Pages to Amend 171 to License DPR-62 Issued on 900206.Amend Changes Tech Specs to Add Footnote to Tables 2.2.1-1 & 3.2.2-2 for Adjustment of Main Steam Line Radiation Monitors When Water Chemistry Sys in Svc 1990-09-06
[Table view] |
Text
-y a CP&L carolin,a gowSMgid ompany
$ ru Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 March 30, 1984 FILE: B09-13510C SERIAL: BSEP/84-0887 Mr. James P. O'Reilly, Administrator U. S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N.W.
Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 SUPPLEMENTAL RESPONSE TO IE INSPECTION REPORT 83-11
Dear Mr. O'Reilly:
In our letter of February 9, 1984, Serial No. NLS-84-058, Carolina Power &
Light Company stated that an assessment of the Fire Protection Program was being performed and that appropriate programmatic upgrades would be incorporated. These upgrades heve been incorporated into a comprehensive program, a synopsis of which is enclosed for your information. CP&L will periodically provide updates of this program reflecting status and any programmatic or scheduler changes.
Should you require any additional information, please contact a member of my staff.
Very truly yours, C3 P. W. Howe, Vice President Brunswick Nuclear Project TEC/mcg/MSCDR1 Enclosures cc: Mr. R. C. DeYoung NRC Document Control Desk S404170371 e4043o pDR ADOCK 05000324 G
PDR ,
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ENCLOSURE 1 This enclosure describes the plan and schedule for preparing a comprehensive Fire Protection Program for Brunswick. The task can be broken down into five phases:
- 1. Performing a needs analysis.
- 2. Developing a set of specifications.
- 3. Writing the procedures.
- 4. Fire brigade organization. ,
- 5. Fire brigade training.
KEEDS ANALYSIS The needs analysis phase involves gathering the commitment documents which impact Brunswick's Fire Protection Program. These would include, but would not be limited to, NUREG 0800; SRP 9.5.1; BTP APCSB 9.5-1 (including Appendix A); 10CFR50 Appendix A and B; 10CFR50.48; Appendix R; Regulatory Guides 1.39, 1.78, 1.101, 1.120; the FSAR; NFPA 4, 4A, 6, 7, 8, 27, and others; commitments made to the NRC; QA audit findings and the Corporate QA Manual; and NRC findings and problems identified at other nuclear plants.
The analysis is an important function in that it must ensure that the program will satisfy all regulatory requirements.
SPECIFICATIONS AND PROGRAM DEFINITION This phase will begin once the needs analysis is complete. Preparation of the specifications is important because it is here that the Brunswick Fire Protec-tion Program will be defined. Specifications will then be generated for each procedure. These specifications will include the procedure's format, purpose, pertinent commitments, codes, regulations, and will indicate whet the procedure will do. Appropriate management review of the specifications will be complete prior to procedural development.
The set of specifications produced will be compared to ensure logical groupings of content, function, purpose, and quantity. This final action will result in a set of procedures which are comprehensive, cohesive, and integrated.
PROCEDURES The procedure writing phase will be straightforward. Using the procedure specifications, referenced codes, regulations, standards, commitments, exist-ing procedures, and drawings, the writer will develop the procedure using any additional assistance required. The procedure will be independently reviewed and then approved by appropriate management as required by regulations and plant procedures.
Procedures will be generated to replace the existing fire protection (FP) procedures, fire instructions (FI) including fire plans, and periodic tests which are performed as part of the Fire Protection Program.
Training of shift personnel and Fire Protection staff members will be conducted on these procedures prior to their implementation. Following this training, the procedures will be impicmented.
FIRE BRIGADE ORGANIZATION A new Fire Brigade organization will be implemented to enhance the brigade's fulfilling of regulatory requirements, fire fighting, and fire prevention at BSEP. The new organization will be implemented over the next 18 months in three phases to assure a smooth transition from the current organization.
The final organization will consist of six shifts of fully dedicated Fire Brigade personnel, supported by an administrative, technical, and supervisory staff during day shifts. The shift Fire Brigade personnel will perform fire protection-oriented tasks, such as pts, fire inspections, fire watch super-vision, and fire equipment checks. Their number will be a function of the normal work load which they will be expected to carry, with a planned minimum of five on each shift in accordance with regulations. It is expected that additional personnel will be required for each shift to perform the required tasks and to maintain continued training. Those which are not utilized for fire protection work activities will be utilized as A0s.
The Fire Brigade organization will be led by the Fire Support Supervisor who will fulfill the requirements for a Fire Chief. Reporting to him will be a Fire Support Specialist, Administrative Specialist, Drill Coordinator, Records Specialist, clerk, and six Shift Fire Supervisors. Firc Brigade members on each shift will report to the Shift Fire Supervisor.
Each operational shift will also have a licensed individual who is fully qualified and trained in fire protection and fire fighting. This person will act as the Fire Commander during a fire. The Fire Commander will be dispatched to the scene of the fire and will report to the Shift Foreman. The Fire Commander directs the fire fighting at the scene with the Shift Fire Super-visor reporting to him. The Shift Fire Supervisor is trained to direct the fire fighting if the Fire Commander is disabled or called to a second fire.
FIRE BRIGADE TRAINING ,
The Fire Brigade training responsibility will be shifted from Operations to the Training Unit. Drills,' practice fire fighting, and real-time training will remain under Operations' control.
The training goals will be to have a Fire Brigade fully trained to deal with fire situations that could reasonably exist and to qualify each Fire Brigade member as an AO. Qualified Fire Protection group personnel will be given A0 training in regularly scheduled A0 classes.
2-
_a
e a A comprehensive program is being developed to provide additional training for the Fire Brigade personnel. This training is anticipated to include:
- 1. Fire Academy Training
- 2. Fire Brigade Training
- 3. Fire Inspection
- 4. Fire Protection Procedures
- 5. Fire Protection Periodic Testing 1 6. Fire Protection Equipment Checks It is also anticipated that the Fire Support Supervisor, Shift Fire Supervisors, and the Fire Commanders receive the above training, plus the following:
- 1. Regulations and Specifications i
i 2. Fire Chief's Course
- 3. Supervision Course i
i
- 4. Fire Rescue .
i
- 5. EMT (Emergency Medical Technician) 1 Each Shift Foreman will receive the following training:
- 1. Fire Brigade Training
- 2. 24-Hour Academy Training
, A training schedule has been developed and the above training should be accomplished without disruption to the current fire protection responsibilities. Training will be tailored to accommodate a time phased approach to development of the organization.
SCHEDULE A comprehensive schedule has been developed to provide an effective management tool for implementation. This schedule currently calls for individual project start dates ranging from March through June 1984 and a final total completion date of December 1985. The extensive training program is tha primary reason for this extended time period. In addition, various projects cannot be started until prerequisite projects are completed (i.e., the needs analysis must be completed prior to specification development). Due to possible program changes and the availability of outside resources (i.e., Fire Academy), this schedule may change. These changes will be updated in the periodic reports.
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CLOSING COMMENTS The Brunswick station has developed and is implementing what it considers a very comprehensive Fire Protection Program. Many aspects of this program are included in this letter. In addition to those actions identified in this letter, which fall mainly under the auspices of the Operations Subunit and the Training Unit, an engineering program is also in effect. This program not only includes the requirements of Appendix R, but also incorporates many improvements and upgrades to the operation of the Fire Protection System at Brunswick. Should you so desire, CP&L would enjoy the opportunity to present its fire protection upgrade program to you or members of your staff.
4
CD&L Carolina Power & Light Company SERIAL: NLS-84-058 FEB 001984 Mr. Richard C. DeYoung, Director Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO NOTICE OF VIOLATION
Dear Mr. DeYoung:
Carolina Power & Light Company (CP&L) has received the letter f rom Mr. James P. O'Reilly dated January 10, 1984 transmitting a Notice of Violation and Proposed Imposition of Civil Penalty (EA 83-88). Ca rolina Power & Light Company has also received Inspection Reports 50-324/83-11 and 50-325/83-11 for the Brunswick Steam Electric Plant, Unit Nos. I and 2. Th e above referenced Inspection Reports do not contain any information of a proprietary nature.
Pursuant to 10 CFR 2.205, CP&L hereby encloses its check in the amount of forty-thousand dollars ($40,000) payable to the Treasurer of the United States, in payment of the proposed civil penalty. As required by 10 CFR 2.201, CP&L's response to the Notice of Violation issued with the Proposed Imposition of Civil Penalty is enclosed.
Should you need any additional information, please contact our Licensing Staff.
Yours very t ruly, M. A. McDuffie Senior Vice President Nucicar Generation WRM/ccc (9453WRM)
En closures c c: Mr. M. Grotenhuis (NRC) MCUM ORICI M Mr. J. P. O'Reilly (NRC-RII)
Mr. D. B. Vassallo (NRC) Cort 1tici Dy
/
_ c1 LN M. A. McDuf fie, having been first duly sworn, did depose add say that the information contained herein is true and correct to the best of his infornation, knowledge and belief; and the sources of his information are - ,,,
officers, employees, contractors, and agents of Carolina Power & Lighf. . '.
Comp any . .s M '. -
/ Notary (Seal) .
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ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 INSPECTION REPORTS 50-324/83-11 AND 50-325/83-11 RESPONSE TO NOTICE OF VIOLATION Inspection Reports 50-324/83-11 and 50-325/83-11 and the January 10, 1984 Notice of Violation (EA 83-88) identified six items that were in non-compliance with NRC requirements. These items and Carolina Power & Light Company's response to each are addressed in the following text:
VIOLATION A (SEVERITY LEVEL III):
In a response dated May 24, 1982, describing corrective action taken with respect to a Notice of Violation dated April 2, 1982, the licensee stated that Tables I and IA of Volume XI of the licensee's Plant Operating Manual had been revised to assure that all Q-list equipment was correctly identified on both tables. These tables are used by licensee personnel as a reference to determine if a plant instrument is a Q-item (i.e., safety-related).
Contrary to the above, on May 24, 1982, and as of November 1982, numerous discrepancies existed between Tables I and IA of Volume XI of the licensee's Plant Operating Manual, and consequently the tables did not correctly identify all Q-list equipment. For example, Table IA did not identify pressure switches as Q-list equipment while Table I did. Thus, the licensee's response to the NRC of May 24, 1982, contained a material false statement within the meaning of Section 186 of the Atomic Energy Act of 1954, as amended. The licensee's statement was false in that Tables I and IA did not correctly identify all Q-list equipment. The statement is material f or the NRC would have taken further regulatory action to correct the tables had it known they were incorrect.
l i CAROLINA POWER & LIGHT COMPANY'S RESPONSE:
- 1. Admission or Denial of Violation l
Carolina Power & Light Company acknowledges that the identificatioa of corrective actions set forth in CP&L's response to IE Inspection Report
! 50-324(325)/82-10, Violation D, was not accurate, due to an unintentional
! error, in that Tables I and IA of the Plant Operating Manual, Volume XI (Q-list), were not consistent.
- 2. Reason for Violation l
This event occurred due to the lack of clear definition of the scope of the Q-list upgrade project and to inadequate direction to all site subunits responsible for input.
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- 3. Corrective Steps Taken and Results Achieved ,
- a. The Q-list has been thoroughly reviewed for inconsistencies and corrected where applicable.
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- b. The Q-list has been reformatted to minimize the potential for inconsistencies.
- c. The Q-list has been made unit specific to prevent errors due to the differences in equipment.
- d. Enhanced procedural controls have been implemented to maintain the list up-to-date.
- e. A Project Engineer has been assigned to the Q-list to oversee future improvements.
- f. Plant procedures have been developed which provide more rigid controls for accuracy of data submitted to the NRC. These controls include statement verifications and additional management reviews prior to submittal.
- 4. Corrective Steps to be Taken
< No additional corrective actions are planned for this event.
- 5. Date Full Compliance will be Achieved Full compliance f or this event has been achieved.
VIOLATION B (SEVERITY LEVEL IV):
Technical Specification 3.7.8 for Brunswick, Unit Nos. 1 and 2, requires that all fire barrier penetrations, fire doors, and dampers, in fire zone boundaries protecting safety-related areas shall be functional. Te chnical Specification 3.7.8 Action Statement "a" requires that, with one or more of the fire barrier penetrations non-functional, within one hour a continuous fire watch must be established on at least one side of the affected penetration or verify the operability of fire detectors on at least one side of the non-functional fire barrier and establish an hourly fire watch patrol.
Contrary to the above, during the period of February 13 to April 5,1983, fire barrier penetrations protecting safety-related areas in Unit Nos. 1 and 2 were nonfunctional and the associated fire detectors were inoperable without continuous fire watch.
CAROLINA POWER & LIGilT COMPANY'S RESPONSE:
- 1. Admission or Denial of Violation Carolina Power & Light Company acknowledges that it f ailed to establish continuous fire watches as noted in the violation. This violation was identified by CP&L during an internal review of the Fire Protection Program.
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- 2. Reasons f or the Violation Die Operations Shif t Foreman made an erroneous determination that hourly versus continuous fire watches were to be maintained in the A0G Building when the area fire detectors were declared inoperable by considering only Technical Specification 3.3.5.7, which addresses detector operability.
Hourly fire watches had previously been established in accordance with Technical Specification 3.7.8 due to inoperable fire barriers in the A0G Building. When the fire detectors became inoperable, the Shif t Foreman failed to realize that Tech tical Specification 3.7.8 required continuous versus hourly fire watches since Technical Specification 3.3.5.7 did not provide any reference to other restrictions involving the operability of fire detectors.
- 3. Corrective Steps Taken and Results Achieved
- a. The use of hourly fire watches has currently been discontinued and replaced by the establishment of a continuous roving fire watch in cases where fire detector or fire barrier operability is concerned.
This fire watch, when required, is maintained in the affected area.
- b. Training modules f or the Fire Support group have been implemented and completed, emphasizing an increased understanding of Fire Protection systems. Additional training has been conducted on the interrelations of systems within Technical Specifications.
- 4. Corrective Steps to be Taken No additional corrective action f or this event is planned or anticipated. Corrective measures already implemented have resulted in satisfactory procedural controls for handling Fire Protection related LCOs to avoid future occurrences of this nature.
- 5. Date Full Compliance will be Achieved Full compliance for this event has been achieved.
VIOLATION C (SEVERITY LEVEL IV):
Technical Specification 6.8.1.f for Unit Nos. I and 2 requires that written procedures shall be established, implemented, and maintained covering Fire Protection Program implementation.
Contrary to the above, procedures covering the Fire Protection Program f or Unit Nos. I and 2 were not adequately implemented as demonstrated by the following examples:
- a. Fire Protection Surveillance Procedure, PT-35.7, was inadequately implemented on February 12, 20, 26, and March 7,1983, in that the position of valve WW-V207 was not properly identified. The valve was shut. The position was recorded as being locked open.
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- b. Fire Protection Surveillance Procedure, PT-35.1, was inadequately implemented on February 14, 21, 28, and March 7, 1983, in that valve WW-V207 was not properly verified as locked open.
- c. Fire Protection procedures PT-35.16 and PT-35.18 were not being adequately implemented in those surveillances to ensure the functional status of fire barrier penetrations were not being performed in accordance with the acceptance criteria specified in these tests.
CAROLINA POWER & LIGHT COMPANY'S RESPONSE:
- 1. Admission or Denial of Violation Carolina Power & Light Company acknowledges that it f ailed to adequately implement procedures covering the Fire Protection Program as stated in the violation. Two of the three examples were identified by CP&L during its investigation of the event.
- 2. Reasons f or the Violation
- a. PT-35.7, which contains a step to check the position of valve WW-V207, did not require a hands-on verification of the valve position. In addition, the subject valve is remotely located in a dimly lighted pipe chase below floor level which led to an inaccurate determination of its position by visual verification alone. This example was reported by CP&L.
- b. PT-35.1 includes a prerequisite to verify that the Fire Protection System is lined up per OP-41. Valve WW-V207 is contained in the OP-41 valve lineup procedure and was not in its required open position when PT-35.1 was conducted. No method existed for tracking exceptions to valve lineups, resulting in the f ailure to recognize that valve WW-V207 was out of position and under clearance.
- c. PT-35.16 and PT-35.18 were improperly implemented as a result of insufficient training of the Fire Protection personnel assigned to perform the pts. The determination of fire barrier seal operability was incorrectly based on visual inspection and experience rather than on the acceptance criteria specified in the PT. This example was reported by CP&L.
- 3. Carrective Steps Taken and Results Achieved
- a. PT-35.7 was revised on April 2, 1983, to require a hands-on-check of the associated fire protection valves. Fire Protection personnel who perform periodic testing have also been trained in the proper method to check valve position as specified in 01-13, Valve and Electrical Lineup Verification. As an interim measure until this training was completed, Fire Protection personnel who were assigned evolutions requiring valve position verification were required to be accompanied by Auxiliary Operators.
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- b. A method for tracking exceptions to valve lineups has been incorporated into 01-13, requiring the use of a valve lineup exception form as documentation for the reason that a valve is not in its specified lineup position.
- c. Fire Protection personnel have received training and were required to pass a written exam on Fire Protection related Technical Specifications. In addition, they have received training on Fire
- Protection training modules. Real time training is conducted on a continuing basis to maintain their degree of understanding and knowledge pertaining to current plant Fire Protection concerns.
Verbatim compliance with approved procedures has also been emphasized as a direct result of this event.
- 4. Corrective Steps to be Taken No additional corrective action for these events is planned or
' anticipated. Satisfactory controls have been established to avoid future occurrences of this nature.
- 5. Date Full Compliance will be Achieved Full compliance f or these events has been achieved.
VIOLATION D (SEVERITY LEVEL IV):
Technical Specification 6.9.1.8 for Unit No. I requires the reporting within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmation by telegraph, mailgram, or facsimile j transmission to the Director of the Regional Of fice or his designee no later than the first working day following operation of the unit or affected system when any parameter or operation subject to an LCO is less conservative than the least ' conservative aspect of the LCO established in the Technical >
Specification.
i Contrary to the above, the LCO violation described in the proposed civil '
penalty was a reportable event which was not reported to the NRC Region II within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
CAROLINA POWER & LIGHT COMPANY'S RESPONSE:
- 1. Admission or Denial of Violation Carolina Power & Light Company acknowledges that it f ailed to make the required prompt report when valve WW-V207 was found shut. This event was identified by CP&L on March 18, 1983.
I 2. Reasons for the Violation i The Shif t Foreman and Shif t .0perating Supervisor that were involved in
! identifying the need for an LCO due to the WW-V207 valve being found j closed f ailed to recognize that the conditions of the LCO had been
- exceeded, thus requiring a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report to be made in accordance with Te chnical Specification 6.9.1.8.b. No investigative action was initiated -
at that time. A review of the LCO form by the Regulatory Compliance group (9453WRM/ccc)
r later in the day also f ailed to reveal the need for a prompt notification based on the information provided on the LCO form. Five days later the full scope of the occurrence was recognized and a prompt report was made.
- 3. Corrective Steps Taken and Results Achieved
- a. A prompt report was made to the NRC Region II office on March 18, 1983.
- b. Formal documented " live time" training was initiated on March 29, 1983, for appropriate operating shif t personnel covering details of this event, including event description, investigation results, corrective actions, safety considerations, and reportability evaluation.
- 4. Corrective Steps to be Taken No additional corrective action f or this event is planned or anticipated.
- 5. Date Full Compliance will be Achieved Full compliance for this event has been achieved.
VIOLATION E (SEVERITY LEVEL IV):
Te chnical Specification 6.9.2 f or Unit No. I requires a special report to be issued within 30 days af ter a fire barrier penetration has been inoperable for seven days.
Contrary to the above, in four instances, once on January 26, twice on February 19, and once on March 12, 1983, fire barrier penetrations were inoperable for more than seven days and the req.* ired special reports were not submitted.
CAROLINA POWER & LIGHT COMPANY'S RESPONSE:
- 1. Admission or Denial of Violation Carolina Power & Light Company acknowledges that it f ailed to make required special reports as required by Technical Specifications. This event was identified by CP&L during its review of the Fire Protection Program.
- 2. Reasons for the Viointion
- a. At the time, there was no established system for the daily tracking -
of fire barrier seal LCOs. Consequently, whenever 'an LCO time frame was exceeded, there was no mechanism by which to notify plant Regulatory Compliance personnel that a 30 day special report'was required in accordance with Technical Specification 6.9.2.
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- b. Plant procedures did not provide a mechanism for notifying the Regulatory Compliance group that a protection system had exceeded the allowable technical specification time and that a special report was required.
- 3. Corrective Steps Taken and Results Achieved
- a. Plant Operating Instruction 01-04, which deals with the handling, tracking, and disposition of plant LCOs, was revised on April 8, 1983 to establish a positive tracking system for Fire Protection LCOs. In addition, it is now specifically outlined in the procedure which plant group is responsible f or notifying Regulatory Compliance of an exceeded LCO time frame and how to accomplish the notification.
- b. Special training was given to members of the plant Fire Protection group to upgrade their knowledge of the LCO tracking and handling system with respect to Fire Protection LCOs as reflected in the recently revised 01-04.
- c. The Senior Fire Protection System Specialist now maintains a daily running account of all active fire barrier seal LCOs. This ensures that those LCOs which have exceeded their specified time f rames are reported to Regulatory Compliance so that timely reporting to the Commission may be accomplished.
- d. Plant management also reviews, on each working day, the status of active plant and Fire Protection System LCOs. This will help to ensure expeditious processing, correction, and cancellation of these LCOs.
- 4. Corrective Steps to be Taken to Avoid Further Violations No additional corrective actions for this event are planned or anticipated. Corrective measures already implemented have resulted in a satisfactory awareness of Operations and Fire Protection personnel to avoid future occurrences of this nature.
- 5. Date Full Compliance will be Achieved Full compliance has been achieved. * *-
VIOLATION (SEVERITY LEVEL III; CIVIL PENALTY S40,000):
Technical Specification 3.7.7.2 for Brunswick, Unit No. 1, requires that the Deluge System for the Standby Gas Treatment System (SBGTS) Trains IA and 18, be operable whenever the SBGTS System is required to be operable. Action Statement "a" of Technical Specification 3.7.7.2 requires that, with the Deluge System inoperable, a continuous fire watch with backup suppression equipment be established within one hour.
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-g-Contrary to the above, the Unit No. 1 Deluge System for the SBGTS Trains IA and IB was rendered inoperable when valve WW-V207 was shut during the period of February 11 to March 13, 1983, and a continuous fire watch was not established. During this time, the plant was in a condition which required the S BGTS to be operable.
CAROLINA POWER & LIGHT COMPANY'S RESPONSE:
- 1. Admission or Denial of the Alleged Violation Carolina Power & Light Company acknowledges that a continuous fire watch was not established when valve WW-V207 was isolated as required by Te chnical Specifications. This event was reported in LER l-83-15 on April 1, 1983.
- 2. Reasons for the Violation Af fected Deluge Systems were unknowingly isolated by closing valve WW-V207 while attempting to isolate Service Water System vital header inleakage.
Since it was not recognized that the Deluge Systems were isolated, no LCO was initiated.
The following items were identified as contributing f actors:
- a. The plant Shif t Operating Supervisor (SOS) did not provide appropriate independent review and oversight and was too involved in the details of the actions being taken in association with generating the clearance.
- b. The plant drawing aperture card, utilized when attempting to isolate the Service Water System vital header inleakage, was not easily interpretable.
- c. Plant equipment clearance procedures did not provide for an overall plant systems impact consideration when additional clearance tags were placed on already existing equipment clearances.
- 3. Corrective Steps Taken and Results Achieved
- a. An appropriate LCO and fire watch were established when the event was identified and maintained until valve WW-V207 was reopened on March 15,1983.
- b. A complete internal operations audit of existing plant equipment clearances was conducted to ensure compliance with applicable LCOS.
This audit verified no LCOs were being violated.
- c. The involved SOS was extensively counseled concerning this event and further disciplinary action was taken.
- d. Informal on-shift counseling was conducted by the Manager - Plant Operations for shif t supervisory personnel concerning this event.
This informal counseling was begun immediately following the determination of the event.
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- e. Formal, documented " live time" training was begun on March 29, 1983, for appropriate operating shift personnel covering details of this event, including event description, investigation results, corrective actions, safety considerations, and reportability evaluations.
- f. The clearance procedure has been revised to require a complete review of the entire clearance when extending the boundary of an existing clearance.
- g. Appropriate in-line valve handwheels in the Fire Protection System have been painted red for immediate identification as a Fire Protection valve.
- h. Plant drawing aperture cards have been upgraded to allow easier interpretation of actual system layouts. This upgrade is continuing as an ongoing process.
The results of the immediate corrective actions taken corrected the violation and ensured that no similar conditions existed. Follow-u p corrective actions have improved operating practicca and operational administrative controls such that the possibility of reoccurence has been greatly reduced. '
- 4. Corrective Steps Taken to Avoid Further Violations No additional corrective actions f or this event are planned or anticipated.
- 5. Date Full Compliance will be Achieved Full compliance for this event has been achieved.
ADDITIONAL INFORHATION While Carolina Power & Light Company acknowledges that the Deluge Systems to the Unit No.1 SBGT Systems lA and IB were made inoperable from February 11 to March 13,1983, we would like to present several items which we believe reduce the safety significance of this event:
- 1. Although a fire watch was not specifically assigned to monitor the unprotected area, a radiation checkpoint station located between the SBGTs was continuously manned during this period.
- 2. A review of Shif t Foremen's log and LCOs indicate that the standpipe system and the fire dotection system in the area of the SBGTs were operable from February 11, 1983 to March 13, 1983 except for approximately one hour on March 10, 1983. Vie standpipe system was isolated f rom 10:45 a.m. to 11:40 a.m. to allow work on the system.
- 3. During the time of this event, Unit No. I was in Operational Condition 5 (Refuel) and the only equipment in the area required to be operable were the SBGTs. Ihving been in cold shutdown for two-to-three months prior to and during this event, the anticipated fission product heat loading would (9453WRM/ccc)
, 10 be greatly reduced f rom that of the design TID-14844 release. In any case, as a fire would make the SBGTs inoperable - so would activation of the Deluge System.
t BRUNSWICK IMPROVEMENT PROGRAM The notice of the proposed imposition of Civil Penalty also requested that
, CP&L include the changes we made, or plan to make, in the Brunswick Improvement Program (BIP) which address the programmatic problems in the Fire !
, Protection Program. Cp6L does not plan to initiate changes to the BIP to separately address the Fire Protection Program. Since this event occurred
- (approximately one year ago), many changes have been ef fected concerning Fire Protection - as addressed in the corrective actions to the enclosed '
violations. In addition, a Principal Engineer - Operations position has been !
4 staf fed with specific management responsibility for the Fire Protection Program. The filling of this position has been instrumental in providing the managerial guidance needed in this area. Following assumption of the Principle Engineering position, an assessment of the Fire Protection Program was performed in which several additional areas were identified which require f improvement. Based on the results of this assessment, and any futuru assessments, appropriate programmatic upgrades will be incorporated.
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