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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
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4 CP&L Carolina Power & Ught Company P.o. Box 10429 Southport, NC 28461-o429 APR 0 61999 SERIAL BSEP99-0050 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 NOTIFICATION OF MISSED AUGMENTED INSPECTIONS OF WELDS SUSCEPTIBLE TO l INTERGRANULAR STRESS CORROSION CRACKING l Gentlemen:
This purpose of this letter is to inform the NRC that certain Categcry C, D, and E piping welds in the Brunswick Steam Electric Plant (BSEP), Unit Nos. I and 2, have not been inspected in accordance with the frequencies provided by NRC Generic Letter 88-01, "NRC Position On IGSCC In BWR Austenitic Stainless Steel Piping," dated January 25,1988, and its associated technical basis, NUREG-0313, Revision 2, " Technical Report On Material Selection and Processing Guidelines For BWR Coolant Pressure Boundary Piping." The circumstances associated with these missed inspections are summarized below, and are more fully described in
' the enclosed BSEP Licensee Event Report (LER) 1-1999-001-0, which was previously submitted to the NRC byletter dated Febmary 19.1999 (Serial: BSEP 99-0022).
In response to NRC Generic Letter 88-01, Carolina Power & Light (CP&L) Company committed to inspect piping welds containing austenitic stainless steel that are susceptible to intergranular stress corrosion cracking (IGSCC). Generic Letter 88-01 adopted the guidance contained in NUREG-0313 Revision 2. NUREG-0313 defines seven categories of welds, A through G, based on their degree of susceptibility to IGSCC. Inspection frequencies are established for each lj ,
j
,f
/ '
category of weld. Category C welds are comprised of IGSCC non-resistant materials that have undergone stress improvement (SI) after two years of operation.: Category C welds require inspection within two refueling cycles following SI, after which they must be inspected every
- 10 years._ Category D welds are comprised of nonresistant materials that have not undergone SI.
Category D welds require inspection every two refueling cycles. Category E welds have ,0 ! {
identified cracks which were either reinforced by weld overlay or were mitigated by St. )
Category E welds require an initial inspection, after which they must be inspected every two refueling cycles. These inspection requirements were incorporated as augmented inspections in the Inservice Inspection Program for BSEP, Units 1 and 2.
9904140034 990406 ~
PDR ADOCK 05000324 P PDR gg ;
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J
l Document Control Desk BSEP 99-0050 / Page 2 f In 1997, a revised inspection schedule was implemented to perform the weld inspections on a single recirculation loop in each refueling outage rather than inspections on bc,th recirculation loops in each outage. This change was made to optimize setup and demobilization activities, dose, and manpower expenditures. The missed weld inspections occurred during the transition to the revised examination schedule. Until the transition period, the augmented weld inspections were performed at the appropriate frequency.
l l
Upon discovery of the missed weld inspections, evaluations were performed which demonstrated that the structural integrity of the affected systems was not adversely impacted by the missed weld inspections. One BSEP, Unit 2 Category D weld was inspected on January 23,1999; the weld was found acceptable with no recordabic indications. The remaining missed inspections will be completed during each unit's next refueling outage (i.e., B214R1 for BSEP, Unit 2, j scheduled to begin April 1999, and B113R1 for BSEP, Unit 1, scheduled to begin in February 2000).
1 On May 1,1997 (Scrial: BSEP 97-0104), CP&L requested NRC conemTence with a plan to !
discontinue the augmented weld inspections for certain Category E welds and resume the I inspection frequency of the ASME Code,Section XI. However, based on the discovery of the missed weld inspections, as well as an ongoing Boiling Water Reactor Owners' Group initiative 1 l
to revise the weld inspection frequencies, CP&L is withdrawing its May 1,1997, request.
There are no regulatory commitments being made in this submittai. Please refer any questions j regarding this submittal to Mr. Warren J. Dorman, Supervisor - Licensing, at (910) 457-2068.
l Sincerely, I
' ~
Keith R. Jury Manager - Regulatory Affairs l Brunswick Steam Electric Plant WRM/wnn
Enclosure:
Licensee Event Report 1-1999-001-0 I
i
4 i
Document Control Desk BSEP 99-0050 / Page 3 1 cc: U. S. Nuclear Regulate y Commission, Regien 11 ATTN: Mr. Luis A. Reyes, Regional Administrator Atlanta Federal Center ,
. 61 Forsph Street, SW, Suite '23T85
-l Atlanta,GA 30303 !
U. S. Nuclear Regulatory Commission
. ATTN: Mr. Theodore A. Eastick, NRC Senior Resident Inspector 8470 River Road
. Southport, NC 28461-8869 l
U. S. Nuclear Regulatory Commission i A'ITN: Mr. Allen G. Hansen (_ Mail Stop OWFN 13E2'l) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission F.O. Box 29510 Raleigh, NC . 27626-0510 Division of Boiler and Pressure Vessel North Carolina Department ofI2bor ATTN: Mr. Jack Given, Assistant Director of Boiler & Pressure Vessels
' 4 West Edenton Street Raleigh, NC 27601-1092 l
l l
I I
d
. . ENCLOSURE
)
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 NOTIFICATION OF MISSED AUGMENTED INSPECTIONS OF WELDS SUSCEPTIBLE TO INTERGRANULAR STRESS CORROSION CRACKING i
i LICENSEE EVENT REPORT l-1999-001-0 l
l I
CP&L Carolina Power & Ught Company P.o. Box 10429 Southport, NC 28461-0429 February 19,1999 10 CFR 50.73 SERIAL: BSEP 99-0022 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. I DOCKET NO. 50-325/ LICENSE NO. DPR-71 LICENSEE EVENT REPORT l-1999-001-00 Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Carolina Power &
Light (CP&L) Company submits the enclosed Licensee Event Report. This report fulfills the requirement for a written report within thirty (30) days of the discovery of a reportable occurrence.
Please refer any questions regarding this submittal to Mr. Keith R. Jury, Manager - Regulatory Affairs, at (910) 457-2783.
Sincerely, J r > . Lyash la it General Manager Bmnswick Steam Electric Plant MAT / mat i
Enclosure:
Licensee Event Report g 3, g ,7 1
- g g 4 7-4/ 'h'
,~ , . .
Document Control Desk BSEP 99-0022 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region 11 ATTN: Mr. Luis A. Reyes, Regional Administrator Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-3415 U. S. Nuclear Regulatory Commission A1TN: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. David C. Trimble, Jr. (Mail Stop OWFN 14H22) 11555 Rockville Pike l Rockville, MD 20852-2738 l Ms. Jo A. Sanford l Chair - North Carolina Utilities Commission P.O. Box 29510 i
Raleigh, NC 27626-0510 l
l i
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6 1998) APPROVED BY OMB NO. 3150-0104 EXPlRES 06/30/2001 E stimated burden per response to comply with this mandatory entormation collection request: 50 hrs. Reported lessons learned a*e LICENSEE EVENT REPORT (LER) '=,'l'*d c ,, ,
a
- ',agc'a=g ogc' $,*ad $6'cL'c,'aju$g'a'g ,
(See tsverse for required number of Dranch (T 6 Fh3). U.S, Nuclear Regulatory Commession, Wanhangton 20555 0001, and to the Paperwork Reduction Protect (3150 0104),
digits /characte'rs for each bioch 0*c' a' M*"*0*"ient and Budget, washington. oc 20503. it an information collection does not desplay a currently vahd OMB control number. the NRC may not conduct or sponsor, and a person is not requered to respond to, the enformation collection F ACluTY NAMt (1)
' DOCKET NUM8ER (2) PAGE (3)
Brunswick Steam Electric Plant (BSEP), Unit No.1 05000325 OF 1 7 i TITLE tel l Missed Augmented Inservice Weld Inspections EVENT DATE -(5) LER NUMBER (G) REPORT DATE (7)
MONTH DAY YEAR YEAR OTHER FACILITIES INVOLVED (81 SEQUENHAL RE VISION MONTH DAY YEAR F ACIUTV NAME DOCKE1 NUMBER NUMBER NUMBER RSEP, Unit No. 2 05000324 F ACil'IY NAME DOCKET NUM8f R 01 20 1999 1999 -- 001 - 00 02 19 1999 OPERATING j MODE 19) THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFRt: (Check one or more) (11) 20.2201(b) 20.2203(a)(2Hv) X 50.73(aH2Hi) 50.73(aH2)(vm)
- POWER jQQ 20.2203(aH1) 20.2203(aH3)l) 50.73(aH2Hu) 50.73(a)(2Hx)
LEVEL 00) 20.2203(aH2)6) 20.2203(aH3Hu) 50.73(aH2Hm) 73.71 yg 4,. -
20.2203(aH2Hii) 20.2203(eH4) 50.73(aH2)(iv) OTHER
- } gj;) , ,. 20.22031aH2Hin) 50.36(cH1) 50.73(aH 2Hv) speciev m Abstract beio. o, in l
r v F"# #
20.2203(aH2Hsv) 50.36(cH2) 50.73(aH2Hvn) NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONF NUMetR fanciuos Area Coas) l Mark A. rurkal, Project Engineer - Regulatory Affairs (910)457-3066 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER TO Epix ' REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY Y t.AR YES SUBMISSION i Uf yes, complete EXPECTED SUBMISSION DATE). X NO DATE 115)
ADSTRACT (Limit to 1400 spaces,i.e., approximately 15 single-spaced typewntten lines)116)
On January 20,1999, with Units I and 2 both at 100 percent of rated thermal power, Carolina Power & Light (CP&L) Company determined that certain Category E welds on Units 1 and 2 had not been inspected per the schedule provided in Generic Letter 88-01,"NRC Position On IGSCC In BWR Austenitic Stainless Steel Piping," dated January 25,1988. Subsequently, on January 21,1999, and January 27,1999, CP&L determined that the required inspection frequency for certain Category D and C welds had also not been properly implemented. These inspections are augmented inspection requirements of the Brunswick Steam Electric >
Plant's Inservice Inspection (ISI) Program and, at the time the inspections were missed, a requirement of Technical Specification 4.0.5.f for both Units I and 2. As such, this condition is being reported, in accordance with 10 CFR 50.73(a)(2)(i)(B), as a condition prohibited by the plant's Technical Specifications.
The root cause of this condition is personnel error; the ISI Program Manager inappropriately revised the inspection schedule for the affected welds. Corrective actions include performance of Engineering evaluations which demonstrated that the structural integrity of the affected systems was not adversely impacted by the missed weld inspections. ISI Program enhancements, and the scheduling of inspections of the missed welds during upcoming refueling outages on each unit.
1 NHC f OHM .46161We8
NRC FQRM 366A U.S. NUCLEAR REGULATORY CoMMISSloN (6-1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FAettlTY NAME (1) ft t i LER NUMBER (6) PAGE (3)
", UMP !
",0,' O Brunswick Steam El i *.ric Plant, Unit No.1 -- 001 05000325 1999 -
00 2 OF 7 TEXT filmore space is required, use additional copies of NRC Form 366A) t17)
TITLE Missed Augmented Inservice Weld Inspections INITIAL CONDITIONS On January 20,1999, the Brunswick Steam Electric Plant (BSEP), Unit Nos. I and 2 were both operating at ,
100 percent of rated thermal power. j EVENT NARRATIVE On January 20,1999, Carolina Power & Light (CP&L) Company determined that certain Category E welds on Units 1 and 2 had not been inspected in accordance with the schedule provided in Generic Letter 88-01, l "NRC Position On IGSCC In BWR Austenitic Stainless Steel Piping," dated January 25,1988.
Subsequently, on January 21,1999, and January 27,1999, it was determined that the required inspection frequency for certain Category D and C welds had also not been properly implemented. The welds in question are listed in the following tables.
Category C Welds Weld Identification System IB32RECIRC-22-AM-4 Recirculation [AD]
1B32RECIRC-22-BM-1 Recirculation 1B32RECIRC-22-BM-5 Recirculation 1B32RECIRC-28-A-2 Recirculation 1B32RECIRC-28-A-5 Recirculation 1B32RECIRC-28-A-13 Recirculation 1B32RECIRC-28-B-2 Recirculation 1B32RECIRC-28-B-3 Recirculation 1B32RECIRC-28-B-9 Recirculation 1B32RECIRC-28-B-16 Recirculation 1B32RS2B2-10-FWB39 Residual lieat Removal [BO]
Category D Welds Weld Identification System 12B211N88-JPI-FWRI22-2 Jet Pump Instrumentation 1B21N4C-6-FWN4C225-3 Feedwater [SJ) i NRC FORM 366A (6-1998)
NRC FORM 366A U S. NJCLEAR REGULATORY CoMMJSSION (6-1998)'
UCENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) Nu B e1 L ER NUMBER (6) PAGE (3)
NE "dvsda" l
Brunswick Steam Electric Plant, Unit No.1 05000325 - 001 - 00 3 OF 7 l1999 TEXT III more space is required. use additional copies of NRC Form 366A) t17}
Category E Welds Weld Identification System 1B32RECIRC-4-B-1 Recirculation 2B32RECIRC-4-B-1 Recirculation 2B32RECIRC-28-B-10 Recirculation 2B32RECIRC-28-B-11 Recirculation These inservice inspections of the above welds are augmented inspection requirements of BSEP's Inservice Inspection (ISI) Program. In response to Generic Letter 88-01, CP&L committed to inspect welds containing austenitic stainless steel susceptible to intergranular stress ccrrosion cracking (IGSCC). This commitment was incorporated into the Technical Specifications (TSs) for both Unit I and 2 as TS 4.0.5.f, which stated:
The Inservice Inspection Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods and personnel and sample expansion included in this letter.
On July 25,1998, CP&L implemented the Improved Techneial Specifications (ITS) at BSEP. With implementation of ITS, the requirements of TS 4.0.5.f were relocated to Section 5.2.3.4.2.4 of the BSEP Updated Final Safety Analysis Report (UFSAR). Ilowever, at the time the inspections were missed, TS 4.0.5.f was still in effect. As such, this condition is being reported, in accordance with 10 CFR 50.73(a)(2)(i)(B), as a condition prohibited by the plant's Technical Specifications.
NRC FORM 366A (6-1998)
(- .. .
~
NI.C FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6 1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
~
FACILITY NAME (1) lJUMBER f 2) LER NUMBER (6) PAGE (3)
- " ",U@ "Jf3 Bmnswick Steam Ele + Plant, Unit No.1 05000325 1999 - 001 - 00 4 OF 7 TEXT Vimore space is required. use additional copies of NRC Form 366A) (17)
EVENT CAUSE The root cause of this condition is personnel error. The ISI Program Manager inappropriately revised the mspection schedule for the affected welds. Additionally, programmatic weaknesses allowed this error to go undetected.
In response to Ge .eric Letter 88-01, CP&L committed to inspect welds containing austenitic stainless steel susceptible to IGSCC. Generic Letter 88-01,in turn, adopts the guidance contained in NUREG-0313, Revision 2, " Technical Report On Material Selection And Processing Guidelines For BWR Coolant Pressure Boundary Piping." NUREG-0313 describes seven categories of welds (i.e., A through G) based on their degree of susceptibility to IGSCC. Inspection frequencies are then established for each category of welds.
Category C welds are welds on IGSCC nonresistant materials that have undergone Stress Improvement (SI) after two years cf operation. Category C welds require inspection within two refueling cycles following the SI, after which they must be inspected every 10 years. Category D welds are welds on nonresistant materials that have not undergone St. Category D welds require inspection every two refueling cycles. Category E welds are welds that have identified cracks, which were either reinforced by weld overlay, or were mitigated by SI. Category E welds require an initial inspection, after which they must be inspected every 2 refueling cycles, similar to the Category D welds.
As required by NUREG-0313, the original inspection schedule for the BSEP Category E welds was based upon the original performance of SI or weld overlay. Thesc activities were completed for both A and B recirculation loops during the same outage on each unit. Thus, each subsequent refueling outage required examinations of approximately half of the A loop welds and half of the B loop welds with the remaining welds to be inspected in the following outage. Similarly,initialinspections of Category D welds on both A and B recirculation loops were completed during the same outage on each unit.
Performing the weld inspections on both loops in a single outage is not efficient with respect to dose and manpower expenditures. By limiting setup and demobilization activities to a single recirculation loop in each outage, a significant dose savings is realized. In ord ;o achieve this, the ISI Program Manager i inappropriately implemented a mvised examination schedule in mid 1997. The missed weld inspections '
occurred during the transition to the revised examination schedule. Until this transition period, the augmented weld inspections were performed at the appropriate frequency.
The ISI Program Manager incorrectly believed that, similar to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI required inspections, the only requirement was to ensure that each Category D and E weld is inspected at least once in the two refueling cycle period.
Hence, a given weld could be inspected during the first refueling cycle of a given two cycle period and the second refueling cycle of the next two cycle period. This concept was the bases of the schedule revision to divisionalize the Category D and E weld inspections.
b NRC FOMA 306A (61998)
. ,~
NRC FORM 366A U.S. NUCLEAR REGULATORY CoMMISSloN to-1C98)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) Nu ti LER NUMBER 161 PAGE 13)
"MP 3*$
Brunswick Steam Electric Plant, Unit ho.1 05000325 1999 - 001 -- 00 5 OF 7 TEXT lit more space is required. use additional copies of NRC Form 366A) (17)
A similar thought process was applied to the revised inspection schedule for Category C welds. That is, the examinations of individual welds could be performed at any time within the ten year examination period.
This meant that the frequency between weld inspections for any given weld did not have to be regular: for instance, a Category C weld could be inspected at the beginning of the first ten-year period, and again at the end of the second ten year period.
However, NUREG-0313 requires that there be no more that two refueling cycles between inspections of a given Category D or E weld and no more that 10 years Ltween inspections of a given Category C weld. As a result, the inspection frequency, previously required by TS 4.0.5.f. was not maintained for the affected Category C, D, and E welds when transitioning to the revised inspection schedule.
A contributing factor of this condition is a programmatic weakness in the ISI Program. Specifically, there are no proceoural requirements for independent reviews or management approvals of changes to the augmented program weld inspection schedule.
CORRECTIVE ACTIONS Upon discovery of the missed weld inspections, Engineering evaluations were initiated in accordance with the requirements of Required Compensatory Measure A.] of Section 3.14, "Stmetural Integrity." of the Technical Requirements Manual. These evaluations demonstrated that the structural integrity of the affected systems was not adversely impacted by the missed weld inspections and that continued operation until the next refueling outage on each unit is acceptable.
On January 23,1999, the Unit 2 Category D weld (i.e.,2G3114-1-14-FW1960) on the Reactor Water Cleanup system was inspected. The weld was found to be acceptable with no recordable indications. The remaining missed inspections will be completed during each unit's next refueling outage (i.e., B214R1 for Unit 2, scheduled to start in April 1999, ;ind B113R1 for Unit 1, scheduled to start in Febmary 2000).
CP&L reviewed the remaining IGSCC weld inspection records to ensure there were no other missed weld inspections.
CP&L will revise the governing procedures for the ISI Program (i.e., OENP 16, " Procedure' for Administrative 3
Control of Inservice Inspection Activities" and/or OENP-16.2, " Administrative Control of ASME Section XI I Non-Destructive Examination Program")(1) to require independent reviews for fumre changes to regulatory-critical information such as the inspection schedule and (2) to require that the augmented ISI weld programs (e.g., IGSCC) be subject to the same auditing requirements imposed upon code weld programs.
CP&L will review other programs, including reguhtory augmented programs, to confirm sufficient review controls for revisions are preser NRC f ORM 366A (61998)
. l NRC FORM 1366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998n LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION ,
DOCKET (2)
FACILITY NA'ME (1) NUMBER f2) LER NUMBER (6) PAGE (3)
"E W CE Brunswick Steam Electric Plant, Unit No.1 05000325 1999 -- 001 2 00 6 OF 7 TEXT (lt more space is requ d. use additional copies of N9C Form 366A) l11)
SAFETY ASSESSMENT The safety significance of this occurrence is minimal. Upon discovery ot the missed weld inspections, Engineering evaluations were initiated in accordance with the requirements of Required compensatory Measure A.1 of Section 3.14, "Stmetural Integrity," of the Technical Requirements Manual. These evaluations demonstrated that the structural integrity of the affected systems was not adversely impacted by the missed weld inspections and that continued operation until the next refueling outage for each unit is acceptable.
PREVIOUS SIMILAR EVENTS CP&L has reviewed Licensee Event Reports (LERs) frc,m 1996,1997, and 1998 and identiDed the following repons associated with missed surveillance intervals:
- 1. LER l-97-012, " Standby Gas Treatment System Fire Protection System Deluge Valve Surveillance Interval Exceeded," dated October 8,1997. The apparent root cause of this condition was the lack of an adequate definition for testable versus non-testable valves.
- 2. LER l-97-009, " Missed Increased Frequency Inservice Testing Requirement," dated August 13,1997.
This condition involved the failure to pioperly increase the test frequency for a valve based on degradation in the measured stroke time. The root cause of the event was lack ofInservice Testing Program controls necessary to ensure that completed valve stroke time tests were trended in a timely manner.
- 3. LER l-97-008, " Main Stack Radiation Monitor Surveillance Interval Exceeded," dated September 18,1997. The root cause of this condition was an inadequate review of the UFSAR change associated with removal of the Main Stack Radiation Monitor response time test requirements from the TSs.
- 4. LER l-97-003," Response Time Elimination," dated April 4,1997, as supplemented April 1,1998. The root cause of this condition was an inadequate review of the UFSAP. change associated with removal of the response time testing requirements for the Reactor Protection system and Isolation Actuation system instrumentation from the TSs.
- 5. LER 2-96-004, " Jet Pump Surveillance Not Performed Prior To Exceeding 25% Reactor Power," dated October 11,1996. The root cause of this condition was human performance problems.
- 6. LER l-96-001, " Technical SpeciDeation Required Surveillance Not Performed Within Allotted Time,"
dated February 14,1996. This LER reponed a missed monthly Reactor Building Vent tritium sample surveillan'ce. The root cause of this condition was a process inadequacy in the scheduling of the monthly surveillances.
NRC FORM 366A (61998)
, NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION l (6 19987 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME 11) Nt B f LER NUMBER (6) PAGE (3)
"^"
l "EE ",17%n" Brunswick Steam Electric Plant, Unit No.1 05000325 1999 - 001 - 00 7 OF 7 TEXT (11more space is required. use additionalcopies of NRC Form 366A) (17)
Although there have been several instances of missed surveillances over the past three years, corrective actions for the root causes of these events would not have reasonably been expected to have prevented the situation reported in this LER (i.e., LER l-99-001).
COMMITMENTS Those actions committed to by CP&L Company in this document are identified below. Any other actions discussed in the submittal represent intended or planned actions by CP&L. They are described for the NRC's info mation and are not regulatory commitments. Please notify the Manager - Regulatory Affairs of any questions regarding this document or any associated regulatory commitments.
- 1. Inspections of the affected IGSCC susceptible welds will be compkted during each unit's next refueling outage (i.e., B214R1 for Unit 2, scheduled to start in April 1999, and Bl13R1 for Unit 1, scheduled to start in February 2000).
l 2. CP&L will revise the governing procedures for the ISI Program (i.e., OENP 16, " Procedure for Administrative Control of Inservice Inspection Activities" and/or OENP-16.2, " Administrative Control of ASME Section XI Non-Destnictive Examination Program") (1) to require independent reviews for future changes to regulatory-critical information such as the inspection schedule and (2) to require that the augmented ISI weld programs (e.g., IGSCC) be subject to the same auditing requirements imposed upon l
code weld programs. The required procedure changes will be implemented by October 8,1999.
- 3. CP&L will review other programs, including regulatory augmented programs, to confirm sufficient review controls for revisions are present. This review will be completed by September 10,1999.
Energy Industry Identification System (EIIS) codes are identified in the text as [xx].
i NRC FORM 366A 161998) m_. . .
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