|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 ML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl ML20211K9001999-08-27027 August 1999 Forwards Insp Repts 50-324/99-05 & 50-325/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl ML20210S9061999-08-11011 August 1999 Informs That GE Document Entitled, Addl Info Regarding 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant ML20210S9121999-08-11011 August 1999 Informs That Document NEDC-31624P,Suppl 2,Rev 6,entitled, Loss-Of-Coolant Accident Analysis Rept for Brunswick Steam Electric Plant Unit 2,Reload 13,Cycle 14 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) ML20210P8221999-08-11011 August 1999 Advises That Info Contained in Which Submitted Document,Prepared by Siemens Power Corp,EMF-2168(P) Rev 0, Marked Proprietary,Will Be Withheld from Public Disclosure, Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20210P9381999-08-10010 August 1999 Forwards SE Accepting Licensee & Suppls & 0517,which Submitted Assessment of Impact on Operation of Unit 1 with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P8911999-08-10010 August 1999 Forwards SE Authorizing Relief Requests CIP-01,02,06,07,08, 09,10,11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Requests CIP-04 & 05 Would Result in Hardship,Relief CIP-03 Not Required & CIP-11 Denied in Part BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 ML20210Q4581999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section to Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit List of Individuals to Take exam,30 Days Before Exam Date ML20210P2031999-08-0505 August 1999 Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2 ML20210N2041999-08-0505 August 1999 Forwards SE Accepting Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46, & Suppl 1 BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld ML20210G2941999-07-28028 July 1999 Discusses Public Meeting Conducted on 990720 to Present Results of Periodic Plant Performance Review for Brunswick Facility for Period of May 1997 to January 1999.List of Attendees Encl BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR ML20210E1181999-07-19019 July 1999 Forwards Insp Repts 50-324/99-04 & 50-325/99-04 on 990509- 0619.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl ML20196H8191999-06-21021 June 1999 Informs That on 980915,Commission Suspended SALP Program for an Interim Period Until NRC Completes Review of Process for Assessing Performance at NPPs ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20196A8111999-06-14014 June 1999 Ack Receipt of 990401 Response to NRC Ltr Issued on 990302 Re OI Investigation to Determine Whether Former BSEP Manager Threatened to Fire Employees Who Brought Safety Concerns to Nrc.Concluded That No Violation Occurred ML20195J1971999-06-14014 June 1999 Advises That GE-NE-523-B13-01920-56,Rev 1,submitted with 990202 Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 BSEP-99-0092, Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld1999-06-0808 June 1999 Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld BSEP-99-0085, Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld1999-05-27027 May 1999 Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld BSEP-99-0078, Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT1999-05-17017 May 1999 Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT BSEP-99-0080, Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval1999-05-17017 May 1999 Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval BSEP-99-0083, Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6)1999-05-14014 May 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6) BSEP-99-0056, Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively1999-05-13013 May 1999 Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively BSEP-99-0073, Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by1999-05-12012 May 1999 Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by BSEP-99-0062, Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.171999-05-11011 May 1999 Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.17 BSEP-99-0079, Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-05-0707 May 1999 Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0066, Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided1999-05-0404 May 1999 Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided ML20195D6301999-04-30030 April 1999 Forwards Natl Marine Fisheries Svc Biological Opinion Based on Review of Continued Use of Cooling Water Intake Sys at Bsep.Rept Reviews Effects of Activity on Loggerhead,Kemps Ridley,Green,Hawksbill & Leatherback Sea Turtles BSEP-99-0071, Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6)1999-04-27027 April 1999 Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6) BSEP-99-0069, Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-171999-04-26026 April 1999 Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-17 BSEP-99-0063, Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link1999-04-21021 April 1999 Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link BSEP-99-0050, Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping,1999-04-0606 April 1999 Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, BSEP-99-0051, Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 21999-04-0101 April 1999 Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 2 BSEP-99-0015, Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-03-31031 March 1999 Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A8161990-09-14014 September 1990 Forwards Info Re Performance of NDE Exam of Feedwater Nozzles & Safe Ends During 1989/1990 Maint/Refueling Outage, Per NUREG-0619,Section 4.4.3.1(2) ML20059L0911990-09-12012 September 1990 Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML20059G2881990-09-0606 September 1990 Forwards Proprietary NEDC-31624P,Rev 2,Class III, Brunswick Steam Electric Plant Units 1 & 2 SAFER/GESTR-LOCA LOCA Loss of Coolant Accident Analysis, for NRC Approval.Rept Withheld ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty BSEP-90-0579, Informs That Util Plans to Replace Pilot Valve Assemblies on Listed Safety Relief Valves Prior to Startup1990-08-24024 August 1990 Informs That Util Plans to Replace Pilot Valve Assemblies on Listed Safety Relief Valves Prior to Startup BSEP-90-0564, Forwards Response to Violations Noted in Insp Repts 50-324/90-19 & 50-325/90-19.Corrective Actions:Procedures to Shutdown Reactor Feed Pump Using Manual Control Approved on 900627 & Real Time Training Provided to Operators1990-08-16016 August 1990 Forwards Response to Violations Noted in Insp Repts 50-324/90-19 & 50-325/90-19.Corrective Actions:Procedures to Shutdown Reactor Feed Pump Using Manual Control Approved on 900627 & Real Time Training Provided to Operators BSEP-90-0565, Responds to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06.Corrective Actions:Personnel Counseled on Closure of Locked High Radiation Area Doors & Preventive Maint Program Established for Reactor & Turbine Bldg Gates1990-08-16016 August 1990 Responds to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06.Corrective Actions:Personnel Counseled on Closure of Locked High Radiation Area Doors & Preventive Maint Program Established for Reactor & Turbine Bldg Gates ML20058N1671990-08-0909 August 1990 Forwards Updated Tech Spec Pages Re 900314 Application for Amends to Licenses DPR-71 & DPR-62.Amends Permit Removal of Rod Sequence Control Sys & Reduces Rod Worth Minimizer Cutoff Setpoint to 10%-rated Thermal Power BSEP-90-0535, Forwards Monthly Status Rept on Plant Integrated Action Plan.New Target Completion Date for D27 Will Be 9008151990-08-0707 August 1990 Forwards Monthly Status Rept on Plant Integrated Action Plan.New Target Completion Date for D27 Will Be 900815 ML20056A6931990-08-0707 August 1990 Advises of Plans to Complete Remaining Portions of Licensed Operator Requalification Exams During Oct-Dec 1990 BSEP-90-0545, Forwards Monthly Operating Rept for Jul 1990 for Brunswick Steam Electric Plant Units 1 & 2 & Corrected Operating Data Rept for June 1990,Unit 21990-08-0303 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Brunswick Steam Electric Plant Units 1 & 2 & Corrected Operating Data Rept for June 1990,Unit 2 ML20063Q0501990-08-0303 August 1990 Forwards Corrections to Plant Updated Fsar,Amend 8,per ML20056A0291990-07-30030 July 1990 Forwards Response to NRC 900206 Request for Addl Info Re Util 870817 License Amend Request,Extending Expiration Dates for OLs ML20056A0611990-07-27027 July 1990 Advises That Util Plans to Perform Next Integrated Leak Rate Test During Next Reload 8 Outage,Currently Scheduled for Sept 1991 ML20056A1801990-07-25025 July 1990 Forwards Info Re NPDES Permit Noncompliance Reported to Permit Agency for Month of Mar 1990,per 830426 Agreement BSEP-90-0524, Informs of Change to Info in NRC Insp Repts 50-324/90-01 & 50-325/90-01 Paragraph 3.b of Details1990-07-24024 July 1990 Informs of Change to Info in NRC Insp Repts 50-324/90-01 & 50-325/90-01 Paragraph 3.b of Details ML20055G6771990-07-20020 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.Corrective Actions:Event Included in Third Quarter Real Time Training for Personnel, Emphasizing Importance of Detection of Plant Deficiencies ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices BSEP-90-0459, Suppls Response to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06 Re Locked High Radiation Area Boundary.Three Options to Eliminate Design Problems W/Locked High Radiation Boundaries Will Be Submitted by 9008171990-06-29029 June 1990 Suppls Response to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06 Re Locked High Radiation Area Boundary.Three Options to Eliminate Design Problems W/Locked High Radiation Boundaries Will Be Submitted by 900817 ML20058K3551990-06-28028 June 1990 Responds to NRC Confirmation of Actions Ltr Re Licensed Operator Training Program Review.Curriculum Development Unit of Nuclear Training Section Will Develop Self Assessment Criteria to Increase Effectiveness of Training Program ML20055D2751990-06-28028 June 1990 Informs That Senior Operator License SOP-20687 for Rj Zuffa No Longer Needed & Should Be Terminated Upon Receipt of Ltr ML20055D7881990-06-27027 June 1990 Forwards Updated Tech Spec Pages to 890329 Application for Amends to Licenses DPR-71 & DPR-62 to Permit Expanded Operating Domain for Facility ML20055C8201990-06-18018 June 1990 Forwards Rev 0 to Rept of 1989/90 Inservice Insp for Brunswick Steam Electric Plant Unit 2, Per ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA 6220(b) ML20055H5501990-06-14014 June 1990 Discusses Confirmation of Concurrence Re Qualification of Fifth Operating Shift.Util Determined That Crew C Will Be Prepared for NRC Testing by 900723 & 24 to Provide Fifth Crew ML20043G4711990-06-13013 June 1990 Forwards Tech Specs to Support 900228 License Amend Request Re Fuel Cycle 8 Reload ML20043G4671990-06-13013 June 1990 Forwards Proposed Tech Specs Re Turbine Control Valves & Fire Detectors,To Support 900315 License Amend Request ML20043G4701990-06-13013 June 1990 Withdraws 900419 Request for License Amend Re one-time Extension of Diesel Generator Surveillance Interval.Util Investigating Methods of Dealing W/Situation & Will Keep NRR Project Manager Informed of Plans ML20043F1921990-06-0606 June 1990 Advises of Intentions to Delay Submittal of Permanent Change to Tech Spec 3/4.8.1,pending Resolution of Lessons Learned from Incident at Plant ML20043F0431990-06-0606 June 1990 Advises That Correct Date for Remedial Exercise Is 900622, Per Insp Repts 50-324/90-13 & 50-325/90-13.Procedures Will Be Revised by 900706 to Ensure Adequate Accountability for All Personnel within Protected Area ML20043C9021990-06-0101 June 1990 Responds to Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.Corrective Actions:Box Cover Closed Following Notification of Discrepancy & Human Performance Evaluation Initiated to Ensure Proper Corrective Actions Initiated ML20043D1851990-05-30030 May 1990 Forwards Response to NRC 900206 Request for Addl Info Re Util 870817 Proposed Change to Expiration Dates of Ols. Responses to Remaining Questions Will Be Submitted by 900629 ML20043B7821990-05-25025 May 1990 Responds to Violations Noted in Insp Repts 50-324/88-36 & 50-325/88-36.Allowable Working Loads for 1/2-inch Hilti Anchor Bolts Currently Used at Facilities Adequate Per NRC Info Notice 86-094.No Further Action Planned ML20043A3941990-05-16016 May 1990 Forwards Tech Spec Re 900419 Amend Request for One Time Extension of Diesel Generator Surveillance Requirements ML20043G4991990-05-14014 May 1990 Forwards Corrected Graph for 900531 Integrated Action Plan Status Rept Illustrating Level 1 Items Projected as of 900331 ML20042G5411990-05-0909 May 1990 Forwards Response to Request for Addl Info Re 891010 License Amend Request to Raise Allowable Containment Leak Rate from 0.5 to 1.0 Vol Percent Per Day.Core Thermal Power Level to Be Used in Calculation Is 2,550 Mwt ML20042F6111990-05-0202 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' Plant Procedures Provide Adequate Guidance for Operation of Overfill Protection Sys ML20042E8531990-04-27027 April 1990 Discusses Relocation of Primary/Secondary Containment Isolation Valve Listings to Plant Procedures.Relocation Will Help Avoid Future Expenditure of NRC Resources for Review & Processing of License Amend Requests ML20042E7281990-04-27027 April 1990 Provides Tech Spec Interpretation Evaluation of Offsite/ Onsite Electrical Distribution Sys,Per NRC Request During 900123 Telcon.Submittal of Amend Request Will Be Made by 900531 ML20012F4871990-04-0606 April 1990 Forwards Response to Regulatory Effectiveness Review.Encl Withheld (Ref 10CFR73.21) ML20012F4701990-04-0404 April 1990 Forwards Addl Info to Support Util Finding of NSHC for 900228 Application for Amend to License DPR-71,revising MCPR Safety Limit Specified in Tech Spec 2.1.2 from 1.04 to 1.07 for Unit 1,Cycle 8 Operation ML20042E1421990-04-0303 April 1990 Forwards Monthly Status Rept on Plant Integrated Action Plan ML20012E8681990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Per NUMARC 900104 Request.One Change to Coping Assessment Calculation Was Necessary & Deviations from NUMARC 87-00 Methodology Identified ML20012E4621990-03-27027 March 1990 Discusses Licensee Response to NRC 891010 Request for Recirculation Pipe Welds.Ultrasonic Testing Records Package on Weld Samples Assembled & Given to BNL During 891206 Facility Visit.Requested Welds Shipped to BNL on 900301 ML20012D9761990-03-22022 March 1990 Responds to Insp Repts 50-324/88-36 & 50-325/88-36 Re Util Response to IE Bulletin 79-02.Verification That Pipe Support Base Plate Flexibility Accounted for in Calculation of Anchor Bolt Loads Addressed ML20012C4601990-03-15015 March 1990 Forwards Control Loop Voltage Drop Calculation Inadvertently Omitted from 900313 Ltr Providing Addl Info Re Ari/Rpt ML20012E1701990-03-13013 March 1990 Forwards Addl Info Re Ari/Rpt Sys Power Supply,Per NRC 900110 Request ML20012A4271990-02-28028 February 1990 Forwards Rev 0 to Brunswick Unit 2,Cycle 9,Core Operating Limits Rept. ML20012A2491990-02-28028 February 1990 Forwards Supplemental Response to Violations Noted in Insp Repts 50-324/89-26 & 50-325/89-26.Corrective Actions:Ncr S-89-089 Initiated on F075 Event & Involved Operations Personnel Counseled on Events ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20011F3371990-02-23023 February 1990 Forwards Corrected Pages to Amend 171 to License DPR-62 Issued on 900206.Amend Changes Tech Specs to Add Footnote to Tables 2.2.1-1 & 3.2.2-2 for Adjustment of Main Steam Line Radiation Monitors When Water Chemistry Sys in Svc 1990-09-06
[Table view] |
Text
i~ v Cp&L Carolina Power & Light Company MAY 0 81986 SERIAL: NLS-86-158 i Director of Nuclear Reactor Regulation Attention: Mr. Dan Muller, Director BWR Project Directorate #2 Division of BWR Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 IGSCC INSPECTION RESULTS - BRUNSWICK-2 RELOAD 6
Dear Mr. Muller:
By letter dated November 1,1985, Carolina Power & Light Company (CP&L) apprised your staff of the Company's plans for performing mitigative actions and examinations for IGSCC on Brunswick Unit 2 during the Reload 6 outage. These mitigative actions and inspections are complete. This letter contains descriptions of : 1) the Induction Heating Stress Improvement (IHSI) that has been performed on Recirculation System welds, 2) the Reactor Water Cleanup (RWCU) System piping replacement program,3) the IGSCC examination program, and 4) the weld-overlay repairs performed during the current refueling outage. A summary of the susceptible weld population describing mitigative actions applied and repairs is included as Table 1. In addition, this letter includes the basis for continued operation of Unit 2 until the next refueling outage presently scheduled to begin in January 1988.
Mitigative Actions IHSI was performed on 65 recirculation system weld joints as indicated in Table 1. The IHSI was performed by IHI, Inc., of Yokohama, Japan, in accordance with IHI procedures. IHSI is not specifically addressed by codes, standards, or regulations. The time-temperature recordings were made in accordance with ASME Boiler and Pressure Vessel Code, Section ill, Division 1, NB-4622.2 and capacitive discharge welding requirements for thermocouple settings were made in accordance with NB-4311.2 ai d
- NB-4311.3.
The entire Class 1,6-inch RWCU System piping was replaced from the RHR System tie-in to the outboard primary containment isolation valve,2-G31-F004. The piping was replaced with nuclear grade stainless steel piping. The RWCU primary containment penetration X-14 (suction side) was modified to eliminate the inaccessible weld inherent with the original flued head penetration design at Brunswick.
%[$b G
411 Fayettevtile Street
- P o Box 1551 e naleigh. N C 27602
,=~ _ mm , ,
Mr. Dan Mullar NLS-86-158/Page 2 Examirurtion Program Ultrasonic (UT) examinations were performed by General Electric Company (GE). The UT examinations performed during the Reload 6 outage are divided into the following categories:
- 1) Five weld overlay repairs made prior to the present refueling outage.
- 2) Re-examination and re-evaluation of the eleven flawed unrepaired welds listed in Table 2.
- 3) Inconel butter welds as recommended by IE Notice 84-41.
- 4) Welds subjected to IHSI and other examinations required by Generic Letter 84-11.
The UT personnel were qualified in accordance with Generic Letter 84-11 and the fall 1985 EPRI requalification program. The examinations incorporated the use of the fully-automated GE " SMART UT" System where geometrically feasible. The SMART UT System utilizes the Ultra Image lli computer-driven data acquisition system with the ALARA remote scanning device. The scanner is capable of positioning a transducer at any location circumferentially, axially, and at any angle to the weld centerline. Manual exams supplemented the SMART UT exams where geometrical limitations existed.
The sizing of IGSCC indications was performed using 2 to 5 MHz refracted-longitudinal transducers. The sizing methods used were those taught at EPRI including Satellite Pulse Observation Technique (SPOT), Pulse Arrival Time Technique (PATT), and 70* creeping wave technique.
The five existing weld overlay repairs listed in Table 3 were upgraded to meet full structural design requirements by addition of weld metal. The upgraded overlay surfaces were finished to meet or exceed EPRI surface finish requirements. These upgraded weld overlay repairs were examined using 2.25 MHz creeping waves for the overlay weld metal, O' 4.0 MHz straight beam for the overlay to pipe bond and 2.25 MHz 60*
refracted longitudinal wave, for the base material. The techniques used were those recommended by EPRI's weld overlay training program.
The eleven flawed unrepaired welds listed in Table 2 were re-examined and re-evaluated. Ten of the eleven welds were examined by " SMART UT" and manually sized. Weld 2-B32-RECIRC-28"-A-8 was examined manually due to elbow-valve configuration. Welds 2-B32-RECIRC-28"-A-14,2-B32-RECIRC-28"-B-9, and 2-Ell-RHR-20"-SUCT-A-2 were determined to have geometry indications not attributable to IGSCC and, therefore, not subject to repair. The remaining eight welds were confirmed to have IGSCC and were repaired by weld overlay.
Examinations of inconel butter welds as recommended by IE Notice 84-41, were performed on selected welds using 31' to 70' refracted longitudinal dual 1.0 - 2.25 MHz transducers with SMART UT. A " mock-up" calibration block, representative of materials and configuration of welds, was utilized. The initial inspection sample consisted of two 12-inch inlet nozzles and one 28-inch suction nozzle. The initial inspection sample is denoted by astericks in Table 4. A small axial IGSCC indication was detected in weld 2-B32-RECIRC-28"-A-1. The inconel butter of nozzle weld 2-B32-RECIRC-28"-B-1 was then examined and was found to have a small axial indication as well. These indications were sized using a 45' and 60* refracted longitudinal 1.0 MHz search unit.
Indication sizes are shown on Table 5. By use of a 45' shear wave, the indications were
Mr. Dan Muller NLS-86-158/Page 3 confirmed not to penetrate into the nozzle material. A fracture mechanics analysis, performed by General Electric Company, determined that continued operation for an additional fuel cycle without repair is justifiable. This analysis is included as Attachment 2. The examination was expanded to include the remaining inlet nozzle inconel butters shown in Table 4 and did not yield additional indications.
A selected weld sample was examined prior to IHSI based on Unit i experience. A post-IHSI examination was performed on each weld. Those welds with indications were overlayed and then re-examined. The remaining joints that did not receive IHS1 or overlay were also examined. UT examinations were performed on 100 percent of the susceptible weld population.
Examinations were performed in accordance with Generic Letter 84-11 using a 2.25 MHz, single element,45' shear wave transducer. Scanning was performed in eight directions (where geometry permitted); two perpendicular, two parallel, and four tangential. A minimum overlap of 50 percent was used in lieu of the ASME code required 10 percent.
Thirty welds were found to have IGSCC indications. Through wall leaks were found visually on three 4" by-pass weldolet to pipe configurations. The leaks were not detectable by UT because of the forging geometry and were determined by liquid penetrant examinations to be on the forging side. The remaining by-pass weldolet was overlayed as a preventative measure. Thirty-four new overlay repairs were performed and are listed in Table 1. The new overlay repairs were examined by the same technique as the five existing overlays. The Unit 2 overlays meet or exceed the EPRI-recommended surface finish requirements.
I Disposition of Indications Indications were present in seven 28-inch pipe weld joints. These seven joints were repaired with leakage barrier overlays. Full structural weld overlay repairs were applied to pipe weld joints less than 28-inches in diameter. The full structural overlay design is based on an assumed 360* through-wall crack. All overlay designs applied at Brunswick satisfy the requirements of the revised IWB-3640, ASME Code Section XI and Generic Letter 84-11. A complete design report, performed by NUTECH, on the weld overlay repairs is included as Attachment 1.
One shallow axial indication was found in each of the 28-inch suction nozzle inconel weld butters. General Electric Company performed a fracture mechanics analysis of these indications and determined that continued operation for an additional fuel cycle without repair is justifiable. The ASME Code Section XI safety margins will be maintained throughout this period. In addition, substantial leak-before-break margin against pipe as well as nozzle failure is assumed. The fracture mechanics analysis is included as Attachment 2.
Summary of Susceptible Weld Population The susceptible weld population at Brunswick Unit 2 consists of 107 welds. The current status of this weld population with respect to mitigative actions and repairs is summarized below:
i
r Mr. Dan Mul'ar NLS-86-158/Page 4 Mitigation / Repair No. of Weld Joints IHSI 58 Weld Overlay Repair 32 IHSI & Weld Overlay Repair 7 Solution Anneal 8 Unmitigated 2 Total 107 Table 1 provides a detailt J breakdown of the mitigations and repairs performed on each susceptible weld joint.
Yo{pcvaaro0u V$ttove The following special surveillance measures have been implemented at the Brunswick Plant:
- 1) As required by the Technical Specifications, plant shutdown shall be initiated for inspection and corrective action shall be taken when any leakage detection system indicates, within any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an increase in the rate of unidentified leakage in excess of 2 gpm. For sump lesel monitoring systems with fixed-measurement interval method, the level shall be monitored at 4-hour intervals or less.
- 2) At least one of the leakage measurement instruments associated with each sump shall be operable and the outage time for inoperable instruments shall be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, an orderly shutdown will be immediately initiated.
- 3) A visual examination for leakage of the reactor coolant piping shall be performed during each plant outage in which the containment is deinerted provided that such an inspection has not been made in the previous 92 days. The examination shall be performed consistent with the requirements of IWA-5241 and IWA-5242 of the 1980 Edition of Section XI of the ASME Boiler and Pressure Vessel Code. The system boundary subject to this examination shall contain the susceptible welds inside the primary containment.
These special surveillance measures are consistent with those given in Attachment I to Generic Letter 84-11 and CP&L's ALARA Program.
Yov$w(atou CP&L has completed IHS1 on 65 susceptible weld joints and has replaced the 6-inch, Class 1, Reactor Water Cleanup System piping with nuclear grade materials. Of a susceptible weld population of 107 welds,105 of these welds have been mitigated by either IHSI, weld overlay repair, or solution annealing. The two unmitigated weld joints are the 4-inch decontamination ports attached to the 28-inch suction piping.
UT examinations were performed on 100 percent of the susceptible stainless steel weld population using the fully automated GE SMART UT System where geometrically feasible.
Full structural overlays were applied to piping weld joints less than 28 inches in diameter with indications. Five existing weld overlays were upgraded to full structural requirements. Leak barrier overlays were applied to the seven 28-inch pipe weld joints with indications. The piping weld joints with indications have been repaired by weld overlay.
Mr. Dan Mullir NLS-86-158/Page 5 Five existing weld overlays were upgraded to full structural requirements. The overlay surface finishes meet the requirements for surface finish recommended by EPRI.
One shallow axial indication found in each of the 28-inch suction nozzle inconel butters has been analyzed by GE and found to meet the ASME Code Section XI safety margins for at least one additional 18-month fuel cycle.
Examination of seven recirculation inlet nozzle inconel botters did not reveal any indications.
As a result of the mitigative actions taken, the state of the art inspections performed on 100 percent of the susceptible weld population, and enhanced surveillance requirements for drywell leakage detection, CP&L believes that start-up and continued operation of Brunswick Unit 2 until the next refueling outage (presently scheduled for January 1988) is justified and will not adversely affect the health and safety of the public.
As inspection plan for the next refueling outage will be submitted 30 days prior to the start of that outage. Should you have any questions regarding this submittal, please contact Mr. S. D. Floyd at (919) 836-6901.
Yours very truly, scs/ctu~
S. R. Zim terman (d ger Nuclear Licensing Section g SRZ/ MAT /pgp (3839 MAT)
Attachments cc: Mr. W. H. Ruland (NRC-BNP)
Dr. J. Nelson Grace (NRC-Ril)
Mr. E. D. Sylvester (NRC)
)
p g
s s s s is s p
/
isy isy isy isy sy isy T A
S l l l l l N
E a a a a la a 9 T n n n n n n 3 O A A A A A A 8 N 3 3 3 3 3 3 3 (
8 8 8 8 8 8 V V V V V V O O O ,
O O O .
N N N 1 N N N 1 Y
A N B B B B B B B L G L L L L L L L R I E S V E OD 5 5 5 5 5 5 5 8 8 8 8 8 8 8 DE L T C C C C C C C E A E E E E E E E WD D D D D D D D 2
O N S T
N t
O I
i a
L T
A N N Y N N N Y N N N N Y N N N N N N Y Y Y N N N N N Y N N N C
P I E
S D
N B I T
A S
T I N S Y Y N Y Y Y N Y Y Y Y N Y Y Y Y Y Y N N Y Y Y Y Y Y Y Y Y Y I
I H
O I J
E L
B D L
A T E N 1
O L I A S T E N N N N N N N N N N N N N N N N N N N N N N N N N N N N N N S U N L N A
L OA S
C s
l l
e B
G N e r e O ip e ip I e w c e w T P w e w v e w p e o e u P w e w v e p a m e e o N P I
R C
S S
S o
b l
E o lo e e o la ip o mu pe P e S
T i P
p lb E
V P lb P S S E
S i
P la V
v b l
E S
i S
p P e o R S T
s d e s e S b lp r
C S o l
E o
e e T ip E P
l o
e e b la ip lv u p V P S S E
P S
i P V v b la E l
S E t S S S S S S S S S S S S S S t S yS S S S S S S S S D S S S S S S S S S S S S S S S S d o S o o o o o S o d o S o o o o T n o t o o t t o t o to t t o t n o t o o t t o t o o t N E t t o t t t t o E t t o t t t t I
w t w e w e w t s w t w e w e O e e o e e o v e o p e lv o e s e e o pe e o v pe o p e v J f p lb p e p lb la p
lb mu p b ip e o f ip b e p b l b m ip a i i e i i i a l e r a l i e i l a i l u la D S P E P T P E V P E P P V E P T C S P E P T P E V P E P P V L
E S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S W S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S E
Z I
S E
PI 0 1 2 3 4 5 6 7 8 0 1 2 3 4 P 2 3 4 5 6 7 8 9 1 1 1 1 1 1 1 1 1 2 3 4 5 6 7 8 9 1 1 1 1 1 O A A A A A A A A A A A A A A A A A B B B B B B B B B B B B B I
A = = a a = a a a a a a a a a a a a = a a a a a a * = a a 8 8 8 8" 8 8 8 8 8 8 8 8 8 8 8 8 8" 8 8 8 8 8 8 8 8 8 8 8 8 8 D 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 D 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 L 8 8 8 8 9 B 8 8 8 8 8- 8 8 8- 8 B 8 8 8 0 B 8 8 8 8 8 8 8 E - - - - - - - - - - - - - - - - - - - - - - - -
W 2 2 222 2 2 22 2 22 22 2 2 2 22 2 2 2 2 2 222 222
)
p g
s s p
/
isy isy T A
S l l M
E a a 9 T n n 3 O A A 8 N 3 3 3 (
8 8 V V O O N N
~
Y A N S S S S S S S S S S S S L G F F F F F F F F F F F F R I E S V E OD 5 5 5 5 5 5 5 5 5 5 5 5
' 8 8 8 8 8 8 8 8 8 8 8 8 DE L T C C C C C C C C C C C C E A E E E E E E E E E E E E WD D D D D D D D D D D D D 2
D N S N
T O I I N T U A N N N N N N N N Y N Y N N N N Y Y N N Y Y N Y Y Y Y Y N N Y C
P I E
S D
N B I T
)
A D
S T 1 T N S Y Y Y Y Y Y Y Y N Y N Y Y Y Y N N Y Y N N Y Y N N N Y Y Y N N H O OI I C
(
J I
D L
E E
L W N O L B I A
T S TI AE N N N N N N N N N N N N N N N N N N N N N N N N N N N N N N U N S L N ' .
A O A L S C
G N
l t
t f
O e p
e e e N r d p d ip d p K O e i n i n n i O I c P E P E P E P C T e u e e e s e s e e w e w e w e w e d N P p s d v p e s p s p v S o p e S o p e $ o p e S o p n O
N I i e s e ip a l i p o i e o i S
lb i f S b i f $
lb i f S b i E
R P e o R P P i r P p r P la P a l P a P a l P
C T r V P C i C V o E S o E S o E S o E e S S C S S S S P S t S t S t S t S f E S S S S S S S S S S S S S S S S S S S S S S S a D S S S S S S S S t S S t S S t S S t S S o S o o o o S o e o o o o T t o t t o t o o t o t o o t o le o t o le o t o le o t o N t o t t t o t t lo t t o t t o t t o t t I
w t s e e s t s p w p w p w p w O o pe s v e v e e s e s e e e o e e e o e e e o e e e o pe J b e o l p l p p o p p o ip e p b p e ip b ip e p b ip e p lb l i e r a i a i i r a i r w i l w l w i l w i i D E P T C V P V P P C C P C P S P E Pi S P E P S P E P S P E P L
E S S S S S S S S S $ S S S S S S S S S S S S S S S S S S S S W S S S S S S S S S $ S S S S S S S S S S S S S S S S S S S S E
Z I
S E 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 P - - - - - - - - - - - - - - - -
I 5 6 7 8 1 2 3 4 5 6 1 2 3 4 A A A A B B B B C C C C D D D D P 1 1 1 1 - - - - - - - - - - - - - - - - - - - - - - - - - -
- - - - M M M M H M M M M M R R R R R R R R R R R R R R R R D B B B B A A A A A A B B B B A A A A A A A A A A A A A A A A N - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
A a a a a a a a a a a a a a a a a a a a a a a a a a a a
- 8 8 8" 8 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2" 2 2 2 D 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 D 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 L 8 8 8 8 8 8 8 8 8 8 8 8 8 B 8 8 8 8 8 8 8 8 8 8 8 8 0 8 8 8 E - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
W 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2_ 2 2 2
[ t S S S S S )
F F F F F p g
5 5 5 5 5 p 8 8 8 8 8 /
T C C C C C A S E E E E N E
T D D D D M 9 3
O d d d d d 8 N e e e e e 3 d d d d d (
a r
a a a a g
r r r r g g g g p p p p p U U U U U Y
A N S S S S S S S S S S S S S S S L G F F F F F F F F F E F F E E E E F F F F R I E S V E OD 5 5 5 5 5 5 5 5 5 3 5 5 3 3 3 3 5 5 5 5 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 DE L T C C C C C C C C C V C C V V V V C C C C E A E E E E E E E E O E O O O O E E E E WD D D D D D D N D D N D N N N N N D D D D 2
O N S T N l
O I
e S T L A N Y Y Y N Y Y Y Y Y Y Y N Y N Y N Y Y N N Y Y N Y Y Y N N N C
P I E D S N B I T
)
A 0 S T
T' N 1
S Y N N N Y N N Y Y N N N Y N Y N Y N N Y Y N N Y Y N N N N Y N I H
O O I C
(
J 1
D L
E E I N L O L B 1 I A
A T E N N N N N N N N N N N N N N N N N N N N N N N N N N N N N N T S U N S L N A
L OA S
C C
t el B
G e e e e e e F N O ip d n
p d n 8?
d p d p d ip d t t t t B
P i
n i n i n n e te e e X I E P E P E P E P E P E E T w e w e w e w e w e w e lo o lo lo B P S o p e S o ip e S o p e S o p e S o ip fe S o ip fe d d d d S S b S S b S S M I R lb P i f a l P
f a lb P i f a l i
P a f
lb P a lb P a le le le le C o E S o E S o E S o E S o E S o E S W W W W S t S t S t S t S t S t S E S S S S S S S S S S S S S S S S S S S S $ S D t S S t S S t S S t S S t S S t S S S S $ S e o o o o o le o t o te o t o te o t o te o to o le o to o o o o o t
T o t e N lo p
t t o t p
t o p
t t o p
t t o p
t t o p
t t t t t t h I
w w w w w w c lo O e e o e e e o e e e o e e e o e e e o e e e o e e e e e n d J e ip b p e ip b ip e ip b p e ip b p e ip b p e p b o ip ip ip ip a w l i w l w l i w l i w l w i l l r le D S P E P S P E P S P E P S P E P S P E Ps S P E P P P P P B W L
E S S S S $ S S S S S S S S S S S S S S S S S S S S S S S S S W S S S S $ S S S S S S S S S S S S S S S S S S S S S S S S S E
Z 1 1 I
1 1 1 1 S - - - -
S S S S 1 E 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 S S S S - C P - - - - - - - - - - - - - - - - - - - - - - - - A A A A C B I
P E
E E
E F
F F
F A- G- G- G- H- H- H- H- J J J J K K K K P P P P B 2
- - - - - - - Y Y Y Y 9 1 R R R R R R R R R R R R R R ' R R R R R R R R R B B B B - -
D A A A A B B B B B B B B B B ~ B B B B B B B B B - - - - A A N - - - - - - - - - - - - - - - - - - - - - - - A A B B a- a-A 2
a a a a a a a a a a a *
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2" 2 2 a a a a 8 8 D 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 4 4 4 2 2 I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 L 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 '1 3 3 3 L 8 8 8 8 8 8 B 8 8 B 0 8 8 8 8 B 8 8 8 8 8 B 0 8 8 8 B 8 8 8 E - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
W 2 2 2 2 22 2 22 2 2 22 2 2 2 22 2 2 22 2 2 2 2 2 2 2 2
, , [
7 p
g p
/
T S
A M
E , 9 T 3 O 8 N 3
(
1 1
Y A N L G R I E S V E OD DE L T E A WD 2
D N S T N 1
O I
1 9 T 1 A N N N N N N N N N N N N N N N N N C
P I E O S P B I T o
)
A ,
t D
S T d T N I
e N S Y N Y Y N N N N N N N N Y Y Y Y Y n O
I O H C J I
, im
( r D e .
I t
L e e D g E W N a K
E 1 OL I A .tu A T E N N N N Y Y Y Y Y Y Y Y N N N N N eO T S UN g S L N a6 A
L OA t f S uR C O 5
s l
l 5 8 F
e R C g E l
o 3 D 8
F N O
g B V n X I nO T e igN iru N
I P
I e
v e e v v n s gd N R p la g en C i V la la i nDiC S '
P V V s g rC E _ S ei y uS D t t t t t t t t S t C S S D s ad G t t t le e e e e e e e S e C C el I T e le e o ic lo lo lo o yD rd N h lo io lo o lo t o o a e et I
to c o to p p p p p p p p t p t t l y vt o O ld n d ld ee e e e e e e e e e r aO c n e e e e e e
- e. ee ew e e J a p el e e r le e w w w w w w w i e Te v rl t d D
L W B W W S S S S S S S S T S P T ,O e a e n v r d a E S S S S S S S S S S S S S S S S 3 rO u W S S S S S S S S S S S S S S S S S e t s y d c n r ir r r ri e u ot a et t C
B 2
1 2
1 s B eS a k
a i n
gl d l ic m g
e n u n e E
Z '
1 T
1 T
2 T C C H H Ye%L E F I b
I C C C S S S 1 1 1 A 8 A 8 A B A D U U U i I E C C
C C C C C C C C C 3-
- - - - S S
D D P B C B B 0 0 0 0 B 3 0 0 A A A A B I 5 0 2 5 3 3 5 5 1 1 3 3 - - - - - B S .
P 1 9 1 1 - - - - - - - - a a a a a Y N L E F 1
- - - - M M M M M M M M 0 0 0 4 4 O A B B B A A A A B B B B 2 2 2 2 2 I - - - - - - - - - - - - - - - -
A a a a
- R R R R 8" 8 8 8 2 2 2"-7" 2 2 2 2 H 0 H H H 0 2 2 2 2 2 2 2 2_ 2 2 2 2 R 2 R R R 1 - - - - - - - - - - - - - - - - - :
2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 S D 3 3 3 3 3 3 3 3 3 3 3 3 1 1 1 1 1 E L 8 8 8 8 8 B B 8 8 B 8 8 E E E E E T E - - - - - - - - - - - - - - - - - O W 2 2 2 22 2 2 2 2 2 2 2 2 2 2 2 2 N
TABLE 2 FLAWED UNREPAIRED WELDS AT START OF RELOAD 6 OUTAGE 2-B32-28"-A-4 2-B32-28"-A-8 2-832-28"-A-13 2-B32-28"-A-14 2-B32-28"-B-3 2-B32-28"-B-4 2-B32-28"-B-5 2-B32-28"-B-9 2-B32-22"-AM-5 2-B32-22"-BM-1 2-El l-RHR-20"-A-SUCT-2
, (3839 MAT /pgp)
.--_. _ _- . _ _ _ . - . - . - . . - -. =- -- _. . . . - . . - . .-..
TABLE 3
. FIVE EXISTING WELD OVERLAY REPAIRS UPGRADED TO FULL STRUCTURAL 2-B32-12"-BR-G-4 2-B32-12"-BR-3-2
, 2-B32-12"-BR-3-3 4
2-B32-12"-BR-K-2 2-B32-12"-BR-K-3 i
t 1
i i
I t
1 1
1 a
{.
I 4
4 i
1 4
f r
i f l'
. (38394AT/pgo) .
e- -gn-- w--- er , -v -ws , y y,,n-e,-.wMrym e wy-,. ----w--v~,,-mw.wn-m-e,-er-, v n.s u mme. wv. ,-mmwww w w w w e m m, _,w w + v --o----n n e , ,enw- m y s v
TABLE 4 INCONEL BUTTER EXAMINATIONS 2-B32-RECIRC-12"-AR-A5 2-B32-RECIRC-12"-AR-B5 2-B32-RECIRC-12"-AR-C5 2-832-RECIRC-12"-AR-E5 2-B32-RECIRC-12"-BR-F5 2-B32-RECIRC-12"-BR-G5 2-B32-RECIRC-12"-BR-H5 2-B32-RECIRC-28"-Al 2-B32-RECIRC-28"-B1 Original Weld Sample
. (3839 MAT /pgp )
1
I TABLE 5 i
INCONEL BUTTER INDICATIONS 2-B32-RECIRC-28" Weld A-1 B-1 Distance From Reference 0" 10.1" Length 0.300" 0.250" Through Wall Depth 0.250" 0.250" Side UP/ Nozzle UP/ Nozzle Orientation Axial Axial
, (3839 MAT /pgp)
ATTACHMENT 1 TO SERIAL: NLS-86-158 (3839 MAT /pgp)