|
---|
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] |
Text
- _ _ - _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ - _ _ _ _ _ - _ _ _
- + 4. f ..
.CP&L Carolina Power & Ught Company P.O. Box 10429 Southport, NC 28461-0429 JUN 011995 SERIAL: BSEP 95-0216 U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50-325/ LICENSE NO. DPR-71 RESPONSE TO NRC BULLETIN 80-13 EXAMINATION OF CORE SPRAY SYSTEM SPARGERS Gentlemen:
The purpose of this letter is to submit the results of visual examinations of the in-vessel core spray piping and spargers for the Brunswick Steam Electric Plant, Unit 1. The in-vessel core spray piping and spargers are being examined in accordance with NRC Bulletin 80-13 dated May 12,1980.
Enclosure 1 provides the results of the in-vessel examinations performed during the Brunswick Unit 1 Reload 9 outage (April- May 1995) and the basis for continued operation of Unit 1 until the
' next refueling outage. During the Unit 1 Reload 8 outage, two linear indications were identified in the in-vessel core spray piping ("B" loop) during visual examinations using a remotely-operated underwater camera. As described in the enclosed information, no siginificant change has been observed in either indication.
The conclusion of the enclosed analysis is that the Unit 1 core spray piping is acceptable in the as-found condition for the next operating cycle. The predicted crack length at the end of an eighteen month operating cycle will not reduce the structural or hydraulic design margins for the piping and sparger below allowable values. Therefore, the condition of the invessel core spray piping does not impose any restictions to unit 1 operation during the next operating cycle (Cycle 10). The piping will be re-inspected and evaluated during Unit 1 Refueling Outage 10 (B111R1), which is currently scheduled to begin in September 1996.
Please refer any questions regarding this submittal to Mr. George Honma at (910) 457-2741.
Sincerely, h \. JL R. P. Lopriore Manager- Regulatory Affairs Brunswick Nuclear Plant WRM/wrm I
t\
9506070287 950601 PDR ADDCK 05000325 P PDR
.o _ ___. .
^
. ,[o - .
Document Control Desk ;
BSEP 95-0216 / Page 2 i
Enclosures l cc: Mr. S. D. Ebneter, Regional Administrator, Region 11
.Mr. D. C. Trimble, NRR Project Manager- Brunswick Units 1 and 2 Mr. C. A. Patterson, NRC Senior Resident inspector- Brunswick Units 1 and 2 ,
The Honorable H. Wells, Chairman - North Carolina Utilities Commission i i
i t
l l
i
'h i
h I
l i
I i .
l ENCLOSURE 1 f BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50-325 LICENSE NO. DPR-71 RESPONSE TO NRC BULLETIN 80-13 EXAMINATION OF CORE SPRAY SYSTEM SPARGERS ,
I l
l l
I - - - -
__. _ . =- . . . -
, i Pago 1 of d
).- ;
Form 1 ENGINEERING SERVICE REQUEST ESR# Rev# WR/JO# Other Documents (ACR, FACTS, etcJ 9400063 1
~ '
Plent/Urvt Primary System # Primary System Name O Maia'. sysi.mo BNP 1005 821,B11-NUCLEAR BolLER (INC.RX VESSEL & Affected Title Originator / Phone CORE SPRAY PIPING REPAIR GILLMAN, TOM 1850-3181 Problem / Proposed Solution / Justification NOTE: PCN G0024C FAIM NO. A0003477 ,
TITLE: Invessel Core Spray Piping Repair, Tee-Box Seal Welds And Examinations .
Project
Description:
In accordance with IE Bulletin 80-13, a visual inspection (PT 90.1) of the Unit 1 core spray spargers and invessel core spray piping was {
performed during refuel outage 8. The inspection identified two linear indications in the B loop. One indication is in the heat affected zone of a ,
circumferential weld which is located in the invessel piping between the B-loop inlet nozzle and the sparger. This weld is located approximately 18" DUE DATE --
@ Continued ;
SCREENING Quality close is a 10CFR 50.59 Safety Review required por (plant specific procedure)7 Response Type
@ The Safety Evaluation for this ESR was revised. i A Safety-Related EVAL Other l
See installation package for signatures.
I 0 This ESR Revision does not effect the previous Safety Analysis (es) or Unreviewed Safety Question determination (s).
1st QSR: Date: l 2nd OSR: Date:
Engineering Die ' (Pri , Sign Derel Engineering / Plant Programe (Print Neme, Sion, Datel Mechanical w F/25/95 Civil / Seismic p, 4 F/L3/f $-
Meterials _
[ $~
System Eng b) ~ ,
23 *) [
4 System Eng A _
System Eng A r
1 I
Procedure: OPLP-30 Revision 1 DCM01b 02/1595 I
i
~
P:ge 2 st 3
" Form 1 ENGINEERING SERVICE REQUEST l 1
ESR # Rev # Title 9400063 1 CORE SPRAY PIPING REPAIR Problem / Proposed Solution / Justification downstream of the B-loop tee box. This linear indication is approximately 4" long. The second indication is on a tee-to-sparger are circumferential weld on one of the lower B-loop spargers. This indication is approximately 3" long.
The tee and sparger are located inside the shrotid at a lower elevation than the inlet piping where the other indication is located.
An evaluation based on inspection results from B110R1 is requested.
Procedure: OPLP-30 Revision 1 DCM03 01/0695
~
P:gQ of J
' Form 1 ENGINEERING SERVICE REQUEST ESR# Revi Title 9400063 1- CORE SPRAY PIPING REPAIR Plant customere teint some, sign, Dere) specletty novism Desi scetion f
vm ,
.lena u dras Jc.
53 Des q u AeVsee
[ NAS Before Approvel/ Implementation
Reference:
, NAS Gefore Closeout Reference;
, PNSC Before Approvel/ implementation
_, NRC Before implementation
Reference:
t Problem Resolution:
ESR 94-00063 was revised to change the ESR Attachment file names to the recommended standard and to document Metallurgy discipline review of the Safety Evaluation.
ESR 94-00063 Revision 1 evaluation is attached. The Evaluation is stored on the LAN at Address x:\pr\esr.oos\ attach \ final \9400063a.wp The Safety Review Package is attached. The Safety Review is stored on the LAN at Address x:\pr\esr.cos\ attach \ final \9400063s.wp l
0 Continued :
APPROVAL le this a modification which constitutes a reduction in design mergin? Interim Approval Required?
1 O Yee (PGM approvalis required)
E No (Engineering Mgr signe for PGM) Om E% Om Reeponsible Engineer TOM GILLMAN f 3-Responsible Manager (Print Neme, Sign, Dete) LQ ghg PIent Generol Meneger thint Name, Sign, Dete)
Procedure: OPLP-30 Revision 1 DCMd 02/15SS i
l i
- u. - _ -- .)
. 1 ESR 94-00063 Evaluation Page 1 Revision 1 ESR 94-00063 EVALUATION l UNIT 1 CORE SPRAY PIPING EVALUATION BASED ON B110R1 IVVI EXAMINATION RESULTS LIST OF EFFECTIVE PAGES i:P h d E 4 ' IREVISiOU 1 1 j l
2 0 )
l 3 0 4 0 5 0 6 0 l
7 0 8 0-9 0 10 0 11 1 12 1 i 13 1 l 14 1 l
l l
l
,. ' ;/ .
ESR 94-00063 Evaluation l Page 2 I Revision O l i
J TABLE OF CONTENTS 1
List of Effective Pages ..................................1 :
Ta blo o f Co n te n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Purpose ............................................3 Co n clu sio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 De sign in pu ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 !
Ev a lu a tio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 ;
industry Experience ....................................4 BN P-1 Ex pe rie nce . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 R FO B 10 9 R 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 -
RFO B110R1 ..................................... 6 Safety Classification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Previo us Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Leaka ge Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Structural Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 ,
Lost Parts Analysis ................................7 EC C S An alysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Discussion of Existing Condition . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 References .........................................10 ;
Do cu ment Updates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 ESR Action ite ms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Safety Review Cover Sheet ..............................11 Safety Analysis ......................................12 Item Classification ....................................13 Unreviewed Safety Evaluation Determination Screen . . . . . . . . . . . . . 14 i
ESR 94-00063 Evaluation Page 3 Revision O j PURPOSE 1
l This ESR Evaluation is required as part of CP&L's commitment to USNRC IE Bulletin I i
No. 80-13, " Cracking in Core Spray Spargers," dated May 12,1980. As such, this evaluation accomplishes the following:
i
- 1) Documents the in-Vessel Visual Inspections (IVVI) performed on the Invessel !
Core Spray piping during Refueling Outage (RFO) B110R1.
- 2) Evaluates the current IVVI data relative to previous inspection results and analyses.
I
- 3) Provides justification to use the Core Spray piping /spargers for another operating cycle in the as-found condition. (i.e. concludes that BNP 1 can safely operate in the present condition during the next fuel cycle (Cycle 10) without any operational changes or restrictions.)
CONCLUSIONS The BNP 1 Invessel Core Spray piping /spargers are " acceptable as is" for Operating Cycle 10. Crack growth experienced during Cycle 9 was substantially less than postulated by previous analysis. Furthermore, the postulated crack lengths at the end of Cycle 10 are fully bounded by previous analysis and will not reduce the structural or hydraulic design margins below allowable values. Therefore, the condition of the invessel core spray piping does not impose any restrictions to BNP 1 operation during the next cycle.
l EVALUATION 1.0 DESIGN INPUTS 1.1 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI,1980 Edition through Winter 1981 Addenda i
ESR 94-00063 Evaluation '
Page 4 Revision 0 1.2 Technical Specifications for Brunswick Steam Electric Plant Unit 1 l 1.3 IVVI Inspection data from BNP-1 Refueling Outages 8 (8109R1) and 9 i (8110R1) !
2.0 EVALUATION 1
2.1 INDUSTRY EXPERIENCE l Invessel Core Spray (CS) piping /spargers cracking is a BWR industry concern. r The first instances of cracking in CS spargers were reported in 1978 at Oyster Creek and in 1980 at Pilgrim. These cases prompted the development of USNRC IE Bulletin 80-13 (Reference 3.1), which requires Licensees to perform i a visual inspection of the CS invessel piping /spargers during each refueling outage. Subsequent inspections performed in accordance with 80-13 have revealed invessel CS piping /sparger cracking at several other facilities, including BNP-1 and BNP-2.
2.2 BNP-1 EXPERIENCE The BNP-1 invessel CS piping and spargers are examine 1 each refueling outage with a remote underwater camera in accordance with BNP Periodic Test OPT-90.1 (Reference 3.2), which complies with IE Bulletin 80-13. The inspections are recorded on video cassette for documentation and trending purposes.
RFO R109R1: During BNP-1 Refueling Outage #8 IVVI inspections, two cracks were discovered in the Core Spray B-loop piping. One crack (Crack A for the purposes of this report) was in the heat affected zone (HAZ) of a circumferential weld located approximately 18 inches downstream of the B-loop tee-box on the 5" (NPS) invessel piping. This crack was judged to be approximately 4 inches in length. Another crack (Crack B for the purposes of this report) was discovered in the HAZ of a tee-to-sparger arm circumferential
. .. . .. . -- . ~ . . . - - . _ - . - - - . . , -. . - . - . ~
b-
.L ESR 94-00063 Evaluation !
Page 5 l Revision 0 [
weld on one of the lower B-loop spargers (3%" NPS) and was judged to be i
approximately 3 inches in length. This condition was evaluated by General l Electric (GE) in report GE-NE-523-97-0793 (Reference 3.3), in terms of four. I relevant issues. The issues and conclusions are summarized in Table 1. !
1 TABLE 1 i
- x !
. . n.srs .. m .
,, ;n ..,..-.>..~. x , ,
l "ICONCLUSION! 2;, ',
. WISSUES #s:% M ", 4 . > ^ l l
Leakage Through Estimated leak rate based on End of Cycle (EOC) ;
Cracks postulated crack lengths is well within the margins 'f inherent in the CS system design and performance evaluations. l Structural The results of the evaluations confirm that a Integrity of through-wall crack of up to 240*around the CS pipe j Piping /Spargers circumference would not cause CS line failure and up l
to 220* around the circumference of CS sparger arm 'l would not cause sparger failure. EOC crack lengths' ;
were estimated to be significantly less, therefore structural integrity of CS pipe and spargers will be- )
1 maintained for all normal operating conditions during 1 Cycle #9.
Lost Parts Lost parts analysis concludes that the consequences (loose pieces) of a postulated loose piece do not pose a safety concern. (Additionally, because structural integrity was demonstrated, lost parts are not expected.)
Effect on LOCA The inherent conservatism present in current LOCA Analysis analyses more than offset the amount of leakage postulated through the two cracks. Therefore no change to the present Maximum Average Plant Linear Heat Generation Rate (MAPLHGR) for BNP-1 is required.
n l
ESR 94-00063 Evaluation Page 6 L Revision 0 RFO B110R1: During BNP-1 Refueling Outage #9 IVV1 inspections, the two cracks discovered in the Core Spray B-loop piping /spargers during RFO B109R1 were reinspected. In each case, crack growth was much less than postulated in the GE analysis (Reference 3.3). No additional relevant -
indications were noted as a result of the IVVI examinations. A summary of RFO B109R1 and RFO B110R1 IVVI data for Crack A and Crack B and the crack growth estimates from Reference 3.3 are presented in Table 2.
TABLE 2 TATTR'IBUTE ?CRACKN ^ LDRAdNSh l Crack Length from RFO B109R1 IVVI Approx 4" Approx 3" Estimated End Of Cycle Crack Length s5.2" s4.1 "
from Reference 3.3 (RFO B110R1)
Crack Length from RFO B110R1 IVVI Approx 4.2" Approx 3.2" Estimated Crack Growth per Operating Approx 0.2" Approx 0.2" Cycle (from IVVI Data) 2.3 SAFETY CLASSIFICA TION The internal core spray piping and spargers are non-ASME Code components, however they are classified as safety related since the Core Spray system is part of the Emergency Core Cooling System. The function of internal Core Spray piping and spargers is to provide a contained flow path to direct coolant to the core region in the event of a LOCA.
ESR 94-00063 Evaluation Page 7 Revision 0 2.4 PREVIOUS ANALYSES Cracks A and B were evaluated by General Electric Company in 1993 (Reference 3.3) for the issues summarized in Table 1. A brief discussion of the GE analysis follows.
Ianksga Analysis GE estimated leakage through Cracks A and B (conservatively assumed as through wall cracks extending 180* around the circumference). Then they considered the effect of such leakage on the ability of the Core Spray system to provide design flow to the core region in the event of a core spray injection. The conclusion was that even using conservative leakage rates, there is sufficient margin in the existing core spray system beyond the design minimum such that the amount lost through the indications would not prevent the core spray system from performing as designed, structural Analysis GE concluded that neither Crack A nor Crack B would grow enough in Operating Cycle #9 to affect the structural integrity of the invessel piping or spargers. All design margins for structural integrity of the in-vessel core spray piping and spargers would still be met at the end of the cycle.
l_nnt Parts Analysis The effect of fragments of the in-vessel core spray piping and spargers breaking loose was considered and there was no postulated adverse effect on any safety related equipment. The subsequent effect of any loose fragments on reactor vessel control rod drive components, fuel assemblies, or any reactor vessel internal components was considered insignificant.
4 ESR 94-00063 Evaluation Page 8 Revision 0 ECCS_ Analysis GE performed a Limiting Line Break and Single Failure analysis and postulated the impact of CS line/sparger leaks on existing ECCS analyses. The inherent conservatism present in current LOCA analyses more l
than offsets the amount of leakage postulated through the two cracks.
Therefore the present Maximurn Average Plant Linear Heat Generation Rate (MAPLHGR) for BNP-1 remains valid.
i 2.5 DISCUSSION OF EXISTING CONDITION The crack growth rates determined from IVVI examination data gathered prior to and after Operating Cycle 9 reveal that the growth rates postulated in the 1 previous GE analysis (Reference 3.3) were extremely conservative. This may be due to conservative estimates of (1) the oxidizing species concentrations in the region (No credit was taken for Hydrogen Water Chemistry) , and (2) the stress intensity factor at the crack tips.
A summary of bounding limits from the GE analysis and postulated growth through the end of Operating Cycle #10 is presented in Table 3. The bounding limits listed are those that allow the GE analysis conclusion to remain valid (i.e. that BNP-1 can safely operate during the next eighteen month fuel cycle and that no operational changes or restrictions are required during that period.)
i
ESR 94-00063 Evaluation Page 9 Revision 0 TABLE 3 ATTRIBUT'El iCRACK A ? ; CRACK BJ Maximum Evaluated Crack Length Approx 8.3" Approx 5.9" From Leakage Analysis '
Maximum Permitted Crack Length Based on Structural Analysis Approx 11.1" Approx 7.2" (Net Section Collapse Evaluation) (240* ) (220')
Length Data from RFO B110R1 IVVI Approx 4.2" Approx 3.2" Estimated Crack Growth Rate per Approx 0.2" Approx 0.2" Operating Cycle from IVVI Data Postulated Crack Length at End of Approx 4.4" Approx 3.4" Operating Cycle #10
' The leakage analysis was performed based on an assumed 180
- crack extent since crack arrest is expected at 180*. (This is due to rapid diminishing of the stress intensity factor caused by orders of magnitude increases in compliance of the pipe as the crack grows.) The GE analysis shows that postulated leakage through the cracks is far below l the threshold that would impact existing ECCS analyses. Therefore it is likely that maximum crack lengths permitted by structural analysis could also be justified by leakage analysis without impacting existing ECCS analyses.
The postulated lengths of Crack A and Crack B at the end of Operating Cycle
- 10 are significantly less than the limiting values considered in Reference 3.3.
Therefore the GE analysis bounds the existing condition and the conclusions reached by the analysis are considered applicable to the next operating cycle.
In summary, the internal core spray piping and spargers are acceptable in the l
1
ESR 94-00063 Evaluation PaDe 10 Revision 0 as-found condition for the next operating cycle of Unit 1. There is no postulated scenario involving the internal core spray piping /spargers that will affect the safe operation of the plant and all design margins for the core spray system will be maintained during the operating cycle. The predicted crack length at the end of an eighteen month cycle will not reduce the structural or hydraulic design margins for the piping /spargers below allowables. The condition of the internal core spray piping /spargers does not impose any restrictions to plant operation for the next operating cycle.
3.0 REFERENCES
3.1 USNRC IE-Bulletin 80-13, " Cracking in Core Spray Spargers", May 12,1980.
3.2 OPT-90.1, "in-Vessel, Core Spray, and Feedwater Visual Examination",
Revision 14 3.3 General Electric Company Report No. GE-NE-523-97-0793, " Core Spray Crack Analysis for Brunswick Steam Electric Plant, Unit 1, July,1993 3.4 EER No. 93-0479, " Evaluation of Unit 1 Core Spray in-vessel Piping and Spargers", Revision 0, and associated 10 CFR50.59 Safety Evaluation DOCUMENT UPDATES No document updates are required as a result of this ESR.
ESR ACTION ITEMS No ESR action items are required as a result of this ESR. Future inspections and reportings are governed by OPT-90.1 (Reference 3.2), which assures that the USNRC IE-Bulletin 80-13 (Reference 3.1) requirements are met.
27P RPV Aalmuth 28r-29r
- e nn. estion j B4M9 4
}
(
(
Header
/ [. 4a Wem Figure 1: Location of B-Loop Core Spray Piping Indication sss* RPV Atimuth FlowNozzle y{
f jb / . J n $on in Wels HAZ Figure 2: Location of B-Loop Core Spray Sparger Indication
ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 '
DOCKET NO. 50-325 LICENSE NO. DPR-71 RESPONSE TO NRC BULLETIN 80-13 EXAMINATION OF CORE SPRAY SYSTEM SPARGERS LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Carolina Power & Light Compny in this document. Any other actions discussed in the submittal represent intended or planned actions by Carolina Power & Light Company. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this document or any associated regulatory commitments.
Committed Commitment date or outage"
- 1. Re-inspect the Unit 1 in-vessel core spray piping and spargers in B111R1 accordance with NRC Bulletin 80-13.
E2-1