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Category:CORRESPONDENCE-LETTERS
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 ML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl ML20211K9001999-08-27027 August 1999 Forwards Insp Repts 50-324/99-05 & 50-325/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl ML20210S9061999-08-11011 August 1999 Informs That GE Document Entitled, Addl Info Regarding 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant ML20210S9121999-08-11011 August 1999 Informs That Document NEDC-31624P,Suppl 2,Rev 6,entitled, Loss-Of-Coolant Accident Analysis Rept for Brunswick Steam Electric Plant Unit 2,Reload 13,Cycle 14 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) ML20210P8221999-08-11011 August 1999 Advises That Info Contained in Which Submitted Document,Prepared by Siemens Power Corp,EMF-2168(P) Rev 0, Marked Proprietary,Will Be Withheld from Public Disclosure, Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20210P9381999-08-10010 August 1999 Forwards SE Accepting Licensee & Suppls & 0517,which Submitted Assessment of Impact on Operation of Unit 1 with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P8911999-08-10010 August 1999 Forwards SE Authorizing Relief Requests CIP-01,02,06,07,08, 09,10,11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Requests CIP-04 & 05 Would Result in Hardship,Relief CIP-03 Not Required & CIP-11 Denied in Part BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 ML20210Q4581999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section to Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit List of Individuals to Take exam,30 Days Before Exam Date ML20210P2031999-08-0505 August 1999 Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2 ML20210N2041999-08-0505 August 1999 Forwards SE Accepting Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46, & Suppl 1 BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld ML20210G2941999-07-28028 July 1999 Discusses Public Meeting Conducted on 990720 to Present Results of Periodic Plant Performance Review for Brunswick Facility for Period of May 1997 to January 1999.List of Attendees Encl BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR ML20210E1181999-07-19019 July 1999 Forwards Insp Repts 50-324/99-04 & 50-325/99-04 on 990509- 0619.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl ML20196H8191999-06-21021 June 1999 Informs That on 980915,Commission Suspended SALP Program for an Interim Period Until NRC Completes Review of Process for Assessing Performance at NPPs ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20196A8111999-06-14014 June 1999 Ack Receipt of 990401 Response to NRC Ltr Issued on 990302 Re OI Investigation to Determine Whether Former BSEP Manager Threatened to Fire Employees Who Brought Safety Concerns to Nrc.Concluded That No Violation Occurred ML20195J1971999-06-14014 June 1999 Advises That GE-NE-523-B13-01920-56,Rev 1,submitted with 990202 Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 BSEP-99-0092, Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld1999-06-0808 June 1999 Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld BSEP-99-0085, Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld1999-05-27027 May 1999 Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld BSEP-99-0078, Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT1999-05-17017 May 1999 Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT BSEP-99-0080, Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval1999-05-17017 May 1999 Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval BSEP-99-0083, Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6)1999-05-14014 May 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6) BSEP-99-0056, Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively1999-05-13013 May 1999 Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively BSEP-99-0073, Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by1999-05-12012 May 1999 Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by BSEP-99-0062, Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.171999-05-11011 May 1999 Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.17 BSEP-99-0079, Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-05-0707 May 1999 Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0066, Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided1999-05-0404 May 1999 Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided ML20195D6301999-04-30030 April 1999 Forwards Natl Marine Fisheries Svc Biological Opinion Based on Review of Continued Use of Cooling Water Intake Sys at Bsep.Rept Reviews Effects of Activity on Loggerhead,Kemps Ridley,Green,Hawksbill & Leatherback Sea Turtles BSEP-99-0071, Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6)1999-04-27027 April 1999 Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6) BSEP-99-0069, Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-171999-04-26026 April 1999 Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-17 BSEP-99-0063, Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link1999-04-21021 April 1999 Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link BSEP-99-0050, Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping,1999-04-0606 April 1999 Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, BSEP-99-0051, Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 21999-04-0101 April 1999 Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 2 BSEP-99-0015, Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-03-31031 March 1999 Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A8161990-09-14014 September 1990 Forwards Info Re Performance of NDE Exam of Feedwater Nozzles & Safe Ends During 1989/1990 Maint/Refueling Outage, Per NUREG-0619,Section 4.4.3.1(2) ML20059L0911990-09-12012 September 1990 Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML20059G2881990-09-0606 September 1990 Forwards Proprietary NEDC-31624P,Rev 2,Class III, Brunswick Steam Electric Plant Units 1 & 2 SAFER/GESTR-LOCA LOCA Loss of Coolant Accident Analysis, for NRC Approval.Rept Withheld ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty BSEP-90-0579, Informs That Util Plans to Replace Pilot Valve Assemblies on Listed Safety Relief Valves Prior to Startup1990-08-24024 August 1990 Informs That Util Plans to Replace Pilot Valve Assemblies on Listed Safety Relief Valves Prior to Startup BSEP-90-0564, Forwards Response to Violations Noted in Insp Repts 50-324/90-19 & 50-325/90-19.Corrective Actions:Procedures to Shutdown Reactor Feed Pump Using Manual Control Approved on 900627 & Real Time Training Provided to Operators1990-08-16016 August 1990 Forwards Response to Violations Noted in Insp Repts 50-324/90-19 & 50-325/90-19.Corrective Actions:Procedures to Shutdown Reactor Feed Pump Using Manual Control Approved on 900627 & Real Time Training Provided to Operators BSEP-90-0565, Responds to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06.Corrective Actions:Personnel Counseled on Closure of Locked High Radiation Area Doors & Preventive Maint Program Established for Reactor & Turbine Bldg Gates1990-08-16016 August 1990 Responds to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06.Corrective Actions:Personnel Counseled on Closure of Locked High Radiation Area Doors & Preventive Maint Program Established for Reactor & Turbine Bldg Gates ML20058N1671990-08-0909 August 1990 Forwards Updated Tech Spec Pages Re 900314 Application for Amends to Licenses DPR-71 & DPR-62.Amends Permit Removal of Rod Sequence Control Sys & Reduces Rod Worth Minimizer Cutoff Setpoint to 10%-rated Thermal Power BSEP-90-0535, Forwards Monthly Status Rept on Plant Integrated Action Plan.New Target Completion Date for D27 Will Be 9008151990-08-0707 August 1990 Forwards Monthly Status Rept on Plant Integrated Action Plan.New Target Completion Date for D27 Will Be 900815 ML20056A6931990-08-0707 August 1990 Advises of Plans to Complete Remaining Portions of Licensed Operator Requalification Exams During Oct-Dec 1990 BSEP-90-0545, Forwards Monthly Operating Rept for Jul 1990 for Brunswick Steam Electric Plant Units 1 & 2 & Corrected Operating Data Rept for June 1990,Unit 21990-08-0303 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Brunswick Steam Electric Plant Units 1 & 2 & Corrected Operating Data Rept for June 1990,Unit 2 ML20063Q0501990-08-0303 August 1990 Forwards Corrections to Plant Updated Fsar,Amend 8,per ML20056A0291990-07-30030 July 1990 Forwards Response to NRC 900206 Request for Addl Info Re Util 870817 License Amend Request,Extending Expiration Dates for OLs ML20056A0611990-07-27027 July 1990 Advises That Util Plans to Perform Next Integrated Leak Rate Test During Next Reload 8 Outage,Currently Scheduled for Sept 1991 ML20056A1801990-07-25025 July 1990 Forwards Info Re NPDES Permit Noncompliance Reported to Permit Agency for Month of Mar 1990,per 830426 Agreement BSEP-90-0524, Informs of Change to Info in NRC Insp Repts 50-324/90-01 & 50-325/90-01 Paragraph 3.b of Details1990-07-24024 July 1990 Informs of Change to Info in NRC Insp Repts 50-324/90-01 & 50-325/90-01 Paragraph 3.b of Details ML20055G6771990-07-20020 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.Corrective Actions:Event Included in Third Quarter Real Time Training for Personnel, Emphasizing Importance of Detection of Plant Deficiencies ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices BSEP-90-0459, Suppls Response to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06 Re Locked High Radiation Area Boundary.Three Options to Eliminate Design Problems W/Locked High Radiation Boundaries Will Be Submitted by 9008171990-06-29029 June 1990 Suppls Response to Violations Noted in Insp Repts 50-324/90-06 & 50-325/90-06 Re Locked High Radiation Area Boundary.Three Options to Eliminate Design Problems W/Locked High Radiation Boundaries Will Be Submitted by 900817 ML20058K3551990-06-28028 June 1990 Responds to NRC Confirmation of Actions Ltr Re Licensed Operator Training Program Review.Curriculum Development Unit of Nuclear Training Section Will Develop Self Assessment Criteria to Increase Effectiveness of Training Program ML20055D2751990-06-28028 June 1990 Informs That Senior Operator License SOP-20687 for Rj Zuffa No Longer Needed & Should Be Terminated Upon Receipt of Ltr ML20055D7881990-06-27027 June 1990 Forwards Updated Tech Spec Pages to 890329 Application for Amends to Licenses DPR-71 & DPR-62 to Permit Expanded Operating Domain for Facility ML20055C8201990-06-18018 June 1990 Forwards Rev 0 to Rept of 1989/90 Inservice Insp for Brunswick Steam Electric Plant Unit 2, Per ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA 6220(b) ML20055H5501990-06-14014 June 1990 Discusses Confirmation of Concurrence Re Qualification of Fifth Operating Shift.Util Determined That Crew C Will Be Prepared for NRC Testing by 900723 & 24 to Provide Fifth Crew ML20043G4711990-06-13013 June 1990 Forwards Tech Specs to Support 900228 License Amend Request Re Fuel Cycle 8 Reload ML20043G4671990-06-13013 June 1990 Forwards Proposed Tech Specs Re Turbine Control Valves & Fire Detectors,To Support 900315 License Amend Request ML20043G4701990-06-13013 June 1990 Withdraws 900419 Request for License Amend Re one-time Extension of Diesel Generator Surveillance Interval.Util Investigating Methods of Dealing W/Situation & Will Keep NRR Project Manager Informed of Plans ML20043F1921990-06-0606 June 1990 Advises of Intentions to Delay Submittal of Permanent Change to Tech Spec 3/4.8.1,pending Resolution of Lessons Learned from Incident at Plant ML20043F0431990-06-0606 June 1990 Advises That Correct Date for Remedial Exercise Is 900622, Per Insp Repts 50-324/90-13 & 50-325/90-13.Procedures Will Be Revised by 900706 to Ensure Adequate Accountability for All Personnel within Protected Area ML20043C9021990-06-0101 June 1990 Responds to Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.Corrective Actions:Box Cover Closed Following Notification of Discrepancy & Human Performance Evaluation Initiated to Ensure Proper Corrective Actions Initiated ML20043D1851990-05-30030 May 1990 Forwards Response to NRC 900206 Request for Addl Info Re Util 870817 Proposed Change to Expiration Dates of Ols. Responses to Remaining Questions Will Be Submitted by 900629 ML20043B7821990-05-25025 May 1990 Responds to Violations Noted in Insp Repts 50-324/88-36 & 50-325/88-36.Allowable Working Loads for 1/2-inch Hilti Anchor Bolts Currently Used at Facilities Adequate Per NRC Info Notice 86-094.No Further Action Planned ML20043A3941990-05-16016 May 1990 Forwards Tech Spec Re 900419 Amend Request for One Time Extension of Diesel Generator Surveillance Requirements ML20043G4991990-05-14014 May 1990 Forwards Corrected Graph for 900531 Integrated Action Plan Status Rept Illustrating Level 1 Items Projected as of 900331 ML20042G5411990-05-0909 May 1990 Forwards Response to Request for Addl Info Re 891010 License Amend Request to Raise Allowable Containment Leak Rate from 0.5 to 1.0 Vol Percent Per Day.Core Thermal Power Level to Be Used in Calculation Is 2,550 Mwt ML20042F6111990-05-0202 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' Plant Procedures Provide Adequate Guidance for Operation of Overfill Protection Sys ML20042E8531990-04-27027 April 1990 Discusses Relocation of Primary/Secondary Containment Isolation Valve Listings to Plant Procedures.Relocation Will Help Avoid Future Expenditure of NRC Resources for Review & Processing of License Amend Requests ML20042E7281990-04-27027 April 1990 Provides Tech Spec Interpretation Evaluation of Offsite/ Onsite Electrical Distribution Sys,Per NRC Request During 900123 Telcon.Submittal of Amend Request Will Be Made by 900531 ML20012F4871990-04-0606 April 1990 Forwards Response to Regulatory Effectiveness Review.Encl Withheld (Ref 10CFR73.21) ML20012F4701990-04-0404 April 1990 Forwards Addl Info to Support Util Finding of NSHC for 900228 Application for Amend to License DPR-71,revising MCPR Safety Limit Specified in Tech Spec 2.1.2 from 1.04 to 1.07 for Unit 1,Cycle 8 Operation ML20042E1421990-04-0303 April 1990 Forwards Monthly Status Rept on Plant Integrated Action Plan ML20012E8681990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Per NUMARC 900104 Request.One Change to Coping Assessment Calculation Was Necessary & Deviations from NUMARC 87-00 Methodology Identified ML20012E4621990-03-27027 March 1990 Discusses Licensee Response to NRC 891010 Request for Recirculation Pipe Welds.Ultrasonic Testing Records Package on Weld Samples Assembled & Given to BNL During 891206 Facility Visit.Requested Welds Shipped to BNL on 900301 ML20012D9761990-03-22022 March 1990 Responds to Insp Repts 50-324/88-36 & 50-325/88-36 Re Util Response to IE Bulletin 79-02.Verification That Pipe Support Base Plate Flexibility Accounted for in Calculation of Anchor Bolt Loads Addressed ML20012C4601990-03-15015 March 1990 Forwards Control Loop Voltage Drop Calculation Inadvertently Omitted from 900313 Ltr Providing Addl Info Re Ari/Rpt ML20012E1701990-03-13013 March 1990 Forwards Addl Info Re Ari/Rpt Sys Power Supply,Per NRC 900110 Request ML20012A4271990-02-28028 February 1990 Forwards Rev 0 to Brunswick Unit 2,Cycle 9,Core Operating Limits Rept. ML20012A2491990-02-28028 February 1990 Forwards Supplemental Response to Violations Noted in Insp Repts 50-324/89-26 & 50-325/89-26.Corrective Actions:Ncr S-89-089 Initiated on F075 Event & Involved Operations Personnel Counseled on Events ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20011F3371990-02-23023 February 1990 Forwards Corrected Pages to Amend 171 to License DPR-62 Issued on 900206.Amend Changes Tech Specs to Add Footnote to Tables 2.2.1-1 & 3.2.2-2 for Adjustment of Main Steam Line Radiation Monitors When Water Chemistry Sys in Svc 1990-09-06
[Table view] |
Text
caresine power a usht company P. O. Box 1551
- Raleigh N. C. 27602 AUG 0 51988 LYNN W. EUR!
Sensof Vice President Opershoas Support SERIAL: NLS-88-182 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PIANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324 / LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO NRC BULLETIN 88-04, "POTENTIAL SAFETY-RELATED PUMP LOSS '
3 Gentlemen:
The NRC issued NRC Bulletin 88-04, "Potential Safety Related Pump Loss,"
on May 5, 1988. The purpose of the bulletin is to request all licensees to investigate potential design concerns involving safety-related pumps.
The NRC concerns involve the potential for a pump to dead-head when it is operating in the minimum flow mode in parallel with another pump, and t.he adequacy of the minimum flow capacity.
The NRC requested that within 60 days of receipt of the bulletin, licensees provide a written response that (a) summarizes the problems and the systems affected, (b) identifies the short-term and long-term modifications to plant operating procedures or hardware that have been or are being implemented to ensure safe plant operations, (c) identifies an appropriate schedule for long-term resolution of this and/or other significant problems that are identified as a result of this bulletin, and (d) provides justification for continued operation particularly with regard to General Design Criterion 35 of Appendix A to 10CFRLO, "Emergency Core Cooling" and 10CFR50.46, "Acceptance Criteria for Emergency Core Cooling System for Light Water Nuclear Power Reacters."
On July 5,1988, Carolina Power & Light Company (CP&L) submitted a letter stating that the Company is participating in a BWR Owners' Group program to respond to NRC Bulletin 86-04, and that within 30 days of receipt of the Owners' Group evaluation, CP&L would submit a plant specific response based on the Owners' Group evaluation.
Carolina Power & Light Company received the Owners' Group evaluation on July 6, 1988. Attached is the Company's response to NRC Bulletin 88-04.
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. . Document Control Daak NLS-88 182 / Page'2 Please refer any questions regarding this submittal to Mr. Stephen D.
Floyd at'(919) 836-6901.
Yours very truly, M
L. W. Eury BAB/bab(\cor\8804)
Enclosure L. W. Eury, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power &
Light Company.
N" MO 490tary (Seal) ,,
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cc: Dr. J. Nelson Grace 5 f . ! !
Mr. W. H. Ruland Mr. B. C. Buckley i g., pggLgg ) G j i
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ENCLOSURE 1 i
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 AND 50-324 OPERATING LICENSES DPR-71'AND DPR-62 I.
SUMMARY
OF PROBLEM AND AFFECTED SYSTEMS A. Summary of Problem The original design basis for sizing the minimum flow lines for safety-related boiling water reactor (BWR) systems is to provida =ufficient flow to avoid overheating the pumps due to low iw. However, current pump vendor guidelines for minimum iF < are based on avoiding hydraulic instability in addition e avoiding pump overheating, leading to higher suggest- minimum flow values than those used in BWR design.
Hydraulic instabilities can occur at low flow rates due to flow separation across the impeller vane, which can lead to asymmetrical shaft and bearing loads in addition to pump and piping vibration. Since applicableforcontinuous{hepumpvendorggidelinesare-only or intermittent- low flow operation, thare are no guidelines for low flow limits for infrequent operation such as that experienced for only a limited postulated range of BWR loss-of-coolant accident (LOCA) events.
In addition, the pump minPaum flow rate can be reduced (possibly leading to a condition where the pump is being run dead-headed) if there is a single minimum flow line for a pair of pumps operating in parallel. If the pumps have different pump shutoff heads, the pump with the higher shutoff head will deliver a greater flow' rate; if there is a significant difference between the shutoff heads, the pump with the lower shutoff head may become dead-headed.
When the minimum flow discharge lines from two or more pumps join at some point to form a common line, there is a i potential for interaction between the pumps. If the piping l configuration is not controlled, the pump with the higher i discharge pressure could reduce the flow through the pump with lesser discharge pressure to the point where it is inadequate for long-term integrity.
1 Continuous operation is considered as more th e two cumulative hours at minimum flow in any 24-hour period.
2 Intermittent operation is less than two cumulative hours of minimum flow operation in any 24-hour period.
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If the pumps' minimum flow discharge lines are orificed (backloaded) in the individual pump discharge lines prior to the junction between the two pipes, and if the common line is large enough in flow area such that its resistance is a relatively small part of the overall hydraulic resistence, there should be little adverse pump-to-pump interaction.
They can be expected to operate individually or in unison with no problems.
However, if the minimum flow discharge lines are not individually orificed, but the common line is orificed or provides greater flow resistance than the individual lines, interaction between the two pumps may occur. The severity of the attenuation of minimum flow through any pump depends on tha shape of the head-flow curves of the pumps, and the magnitude of the mismatch between the pumps.
If the characteristic curve is such that a small change in flow resalts in a relatively large change in developed head, l it is probable that little operational difficulty would i result from an undesirable piping configuration. However, if a relatively large change in flow resulted in only a small change in developed head, some problems could occur.
Further, the rate of attenuation of minimum flow through the lesser pump would be expected to accelerate with time.
B. Affected Systems The BWR Owners' Group submittal identified several systems that may be affected by this problem, including the residual hear removal (RHR), core spray (CS), high pressure coolant injection (HPCI), reactor core isolation cooling (RCIC) and the feedwater coolant injection (FWCI) system. Each system has been reviewed by Carolina Power & Light Company, and it has been determined that the RHR, CS, and HPCI pumps fall within the scope of this bulletin for the Brunswick Steam Electric Plant, Units 1 and 2.
C. Potential for Dead-Heading The RHR pumps' minimum flow bypass piping is the only design that utilizes common discharge piping.
The BSEP RHR system consists of two loo,i of RRR with each loop containing two RHR pumps. The two pumps in each loop have separate three-inch minimum flow lines which tie into a common four-inch discharge line which ties into a I sixteen-inch discharge to the suppression pool, l i
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The three-inch minimum flow lines for the RHR pumps contain restricting orifices prior to connecting to the common four-inch discharge line. A piping resistance calculation was performed to show1that the line losses in'the common four-inch discharge piping are a small-part of the overall resistance, and therefore dual. pump. operation should not.
-present adverse pump-to-pump interaction. In addition,-this.
calculation also shows that if one of the RHR pumps is assumed to be "strong" based on the developed head, dual pump operation still should not present adverse pump-to-pump operation.
D. Adecuacy of Pumo Minimum Flow BWR operating experience does not indicate any excessive wear to pumps when operating under the currently specified minimum flow conditions. That is,-no such reported wear has resulted in indicated degradation in pump performance.
System operation in the minimum flow mode is limited to pump startup during surveillance testing, pump start for suppression pool cooling and during system start on a LOCA signal. The tctal expected time in'the minimu. flow mode over the plant life is at most one percenc of the guideline recommended by the pump vendors for intermittent opers*. ion.3 ,
Tharefore, the potential for excessive wear attributable to minimum flow operation is negligible.
Recent inspection of some BWR RHR pumps has indicated no-pump impeller damage due to minimum flow that could potentially degrade pump performance over the inspection period. It is estimated by GE that the punips had been intermittently operated in the minimum flow mode for up to 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> during this period. This further substantiates that short-term operation in the minimum flow mode has !
little or no impact on pump .ife.
Pump wear attributable to minimum flow operatun is not a significant contributor to total system ur. availability compared to other contributors, such as loss of emergency power, loss of cooling, etc. This is based on BWR operating history, which indicates no occurrences c,f system
, unavailability upon demand due to pump wear incurred in minimum flow operation.
J Some pump vendors recommend minimum flow guidelines for 1 intermittent operation, where intermittent opere. ion is defined as less -I than two cumulative hours of minimum flow in any 24-hour period. For a l plat design life of 40 years, this is equivalent to approximately ;
30,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Similar minimum flow limits have been suggested by other pump vendors. I i
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During the shutdown cooling mode of RHR operation, the minimum flow bypass line is isolated prior to RHR pump start to prevent undesirable changes in the reactor vessel and suppression pool levels. Administrative controls in the operating procedures ensure that during this mode of operation, the pump start and the establishment of the main flow path are done essentially simultaneously. Therefore,
"... damage resulting from operation and testing in the minlaum flow mode..." is not considered applicable during shutdown cooling.
Brunswick Plant Specific Information RHR Pumos: The BSEP RHR pump in-service testing, along with scheduled surveillance testing, has not revealed any signs of pump degradation that can be attributed to inadequate pump minimum flow.
It is estimated that the RHR pumps have operated in the minimum flow mode for less than ten hours total.
Core Soray Pumos: The BSEP core spray pump inservice
, testing, along with scheduled surveillance testing, has not revealed any signs of pump dagradation that can be attributed to inadequste pump minimum flow.
It is estimated that the core spray pumps have operated in y
the minimum flow mode for less than five hours total.
Hinh Pressure Coolant Iniection (HPCI) Fumo: The BSEP HPCI pump inservice testing, along with scheduleu surveillance testing, has not revealed any signs of pump degradation that can be attributed to inadequate pump minimum flow.
It is estimated that the HPCI pump has operated in the minimum flow mode for less than two hours.
II. Short-Term and Lone-Term Modifications Operation in the minimum flow mode, which includes the potential for dead-head operation, is already minimized to the short periods of pump startup during routine testing and to system startup upon a LOCA signal. Based on pump vendor guideliner and operating experience, operation in the minimum flow mode, including dead-heading, is not expected to adversely affect pump op6:stion.
In addition, pumps within the industry have been inadvertently operated in the minimum flow and dead headed conditions foi -
significant periods of time. These pumps continue to operate satisfactorily with no indications of adverse consequences.
Inspections of pumps that have been normally operated, including testing, indicate no significant wear from operating at the low flow rates.
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In order to best ensure that the applicable safety-related' pumps are operated in the minimum flow mode lfor the-least possible duration, applicable operating and test procedures will be revised incorporating precautionary statements to limit minimum flow operation to the least possible duration.
III. Echedule The revisions dascribed in Item II, above, will be completed by February 1, 1989.
IV. Justification for Continued Ooeration The concerns stated in NRC Bulletin 88-04 are summarized as follows:
- 1. With two pumps operating in parallel in the minimum flow mode, one of the pumps ~may be dead. headed resulting in pump damage or failure.
- 2. Installed minimum pump flows may not be adequate to preclude pump damage or failures.
These concerns are addressed by the responses below which provide the basis for concluding that continued operation of BSEP is justified.
A. All Class 1, 2, and 3 centrifugal and displacement-type pumps installed in BWRs which are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident, and provided 2 with an emergency power source, must undergo routine in-service inspection per ASME Boiler and Pressure Vessel i Code,Section XI. Article IWP-1000. These quarterly tests are in addition to.the Technical Specification survetllance requirements intended to demonstrate compliance with the plant safety analyses. The Section XI tests are intended to detect changes in pump' performance. Article IWP-1500, "Detection of Change, ' states:
"The hydraulic and mechanical condition of a purp, relative to a previous condition, can be j determined by attempting to duplicate, by test, i a set of basic reference parameters. Deviations detected are symptoms of changes and, depending upon the degree of deviation, indicate need for further tests or corrective action."
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The in-service tests measure-speed, if variable speed, inlet pressure, differential pressure,1 flow rate .and vibration amplitude.. Alert ranges _and required action ~ ranges'are strictly defined and require either increased frequency of testing.or declaring'the pump as inoperative, respectively.
Performance outside of the required action range would place the affected system in a Limiting-Condition for Operation. _.
Although these tests themselves would not detect pump
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dead-heading or inadequate'ainimum flow (since'these are
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intended to be full flow tests), any deleterious effects of operat?ng with inadequate flow would be detected in advance of significant pump performance degradation. Therefore, any changes in pump performance would be detected and corrected per routine pump testing in advance of pump degradation due '
to cumulative low flow effects from pump surveillance testing and normal system starts.
B. The potential for pump excessive wear attributable to minimum flow operation and/or dead-heading is negligible, since system operation in the minimum flow mode is' limited to surveillance testing and during system start on a LOCA.
signal.
C. BWR operating experience indicates that short term operation in the minimum flow mode and/or dead heading has little or no impact on pump life. Pumps continue to function normally after such operations.
D. Puap wear attributable to minimum flow and/or. dead-heading' is not a significant contributor to. total system q unavailability. Other factors (such as loss of emergency I power, loss of cooling, etc.) are more significant. BWR operating history indicates no occurrences'of system unavailability due to pump excessive wear attributable to low flow operation.
, E. For the LPCI/RHR and core spray pumps, the only design basis events that would lead to pumps running in the minimum flow mode and/or dead heading are events that result in an ECCS
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initiation signal while the reactor is at high pressure (above the pump shutor'f head). These events are normally small break LOCAs and loss of drywell cooling isolation
, events. -Of these, only certain small break LOCAs actually l require ECCS injection from LPCI/RHR or core spray after ;
running at low flow.
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Once initiated, the maximum duration that a LPCI/RHR or core spray pump may operate in the minimum flow mode for the spectrum of hypothetical LOCAs is less than 30 minutes.
This is derived from postulated small break LOCAs, wherein reactor depressurization to below the shut-off head of these pumps is delayed. For large break LOCAs, where the full complement of ECC systems is more fully utilized, the reactor inherently depressurizes through the break. The present minimum flow bypass line is expected to provide adequate protection for these pumps for the short durations postulated during both the small and large break LOCAs.
For other scenarios, there is adequate time to secure the RHR and core spray pumps, and restart them as necessary, precluding extended operation in the minimum flow mode.
F. As discussed in Item E above, only certain small break LOCAs actually require ECCS injection for LPCI or core spray where the pumps may be operated in the minimum flow mode.
However, because of the excess ECCS capacity that is available, limiting LOCA scenarios do not depend on both pumps of a pair of parallel pumps to operate in order to satisfy 10 CFT 50.46 requirements and General Design Criterion 35 of 10CFR50, Appendix A. In fact, a realistic LOCA analysis would show that only one low pressure ECCS pump is typically necessary to satisfy core cooling requirements during and following a LOCA.
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