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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
. /s i
o Carolina Power & Light Company December 29, 1978 FILE: NG 3514(B) SERIAL: GD-78-4401 Office of Nuclear Reactor Regulation ATTENTION: Mr. T. A. .polito, Chief Operating heactors Branch No. 3 United States Nuclear Regulatory Commission Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NO. 50-325 LICENSE NO. DpR-71 FUEL CYCLE NO. 2 - RELOAD LICENSING SUBMITTAL
Dear Mr. Ippolito:
This letter is to transmit to the NRC Staff the General Electric (GF) supplemental reload licensing reports for Carolina Power & Light Company's Brunswick Steam Electric Plant (BSEP) Unit No. 1 for its upcoming refueling and Cycle 2 operation.
One attachment to this letter is GE's NEDO-24166 which is the
" Supplemental Reload Licensing Submittal for BSEP Unit 1 Reload 1.." GE's MEDO-24165 is also attached; this is the LOCA analysis for Cycle ^. Forty (40) copies of these attachments are provided for your use and review.
The reload and previous cycle exposures detailed on page 1, Section 3 of NED0-24166 are not intended to bound the exposures which may be achieved during these cycles, but rather are nominal estimates for these cycles.
On December 27, 1978, we received your letter dated December 21
- hich requests that additional information concerning our startup physics testing program be included in our reload submittal. However, in order not to delay the reload submittal, we are evaluating your request .or additional information and will provide our response as soon as possible.
The technical specification changes necessary for the refueling and Cycle 2 operation are being prepared and will be transmitted to the staff as a pplement to this reload submit, il by January 15, 1979. The appropriate license amendment fee will be included with the request for technical speci-fication changes.
At the present time, the Unit No. 1 refueling outage is scheduled to begin January 13, 1979, and ascent to power is scheduled to begin March 25, 1979. Because of the numerous security and fire protection modifications which must be made during this outage to comply with commission regulations, we are being forced to schedule overlapping outages for BSEP Unit 1 and BFrP Unit 2. Therefore, it is extremely important that the staff review be con-pleted and the appropriate license amendments be issued in a time period that allows us to return to power in accordance with the above schedule.
g D t\oW - -
b $
411 Fayettevste Street
- P. O Box 1}51 + Raleigh, N C. 27602 em m ;: h a :ramozm =zm.s' mmmen 3
l 1 d r> 6- , :
Mr. 20. A.11ppolito. -2 December.29,.1978 t
4 i
If your staff has any questions concerning the' attached information, lwe will be glad to discuss them either by telephone.or at a meeting with re- l presentatives of your staff. !
Yours very truly, f 60 !
, E. E.' Utley
. Senior Vice President j- . Power Supply DLB/ke.
Attachments-
! Sworn to and subscribed before.me'this 29th day of December, 1978 i
. A
.Y44GlO l & r Y l . Notary u-Public i'
My Commission Expiras: July 4, 1980 i
9 i
r i
+
5 4
b L-1 l
l
NEDO-24166
- 11. OPERATINC MCPR LIMIT (5.2)
O EOC2 - 1000 EOC2 - 2000 to BOC2 to to EOC2 mwd /t EOC2 - 1000 mwd /t EOC2 - 2000 mwd /t 1.28 (8x8/8x8R fuel) 1.23 (8x8/8x8R fuel) 1.12 (8x8/8x8R fuel)
- 12. OVERPRESSURIZATION ANALYSIS SUM 3fARY (5.3)
Power Core Flow si v Transient (%) (%) (psig) (psig) Plant Response MSIV Closure 104.1 100 1219 1250 Figure 7 (Flux Scram)
- 13. STABILITY ANALYSIS RESULTS (5.4)
Decay Ratio: Figure 8 Reactor Core Stability:
Decay Ratio, x2/*0 0.70 (105% Rod Line - Natural Circulation Power)
Channel Hydrodynamic Performance Decay Ratio, x2/x0 (105% Rod Line - Natural Circulation Power) 8x8/8x8R channel 0.56
- 14. LOSS-OF-COOLANT ACCIDENT RESULTS (5.5.2)
Reference:
NEDO-24165, "Lcss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 1," November 1978.
1 i
l 1
e .
NEDO-24166 8.
(u.)\ SELECTED MARGIN IMPROVEMENT OPTIONS (5.2.2)
None
- 9. CORE-WIDE TRANSIENT ANALYSIS RESULTS (5.2.1)
Power Flow $ Q/A sl v ACPR Plant Transient Exposure (%) (%) (%) (%) (psig) (psig) 8x8/8x8R Response Loul Rejection EOC 104.1 100 276.8 112.1 1171 1214 0.21 Figure 3a without Bypass Load Rejection EOC-1000 104.1 100 255.7 109.3 1168 1210 0.16 Figure 3b without Bypass-Load Rejection EOC-2000 104.1 100 146.8 100.0 1159 1201 0.03 Figure 3c without Bvpass Loss of 1000F -
104.1 100 118.9 116.8 1020 1066 0.14 Figure 4 Feedwater Heating Feedwater EOC 104.1 100 184.6 109.8 1146 1188 0.15 Figure Sa
()N
\- Controller Figure Feedwater EOC-1000 104.1 100 158.6 106.5 1144 1185 0.09 Figure 5b Controller Failure Feedwater EOC-2000 104.1 100 111.6 105.0 1139 1180 0.05 Figure Sc Controller Failure
- 10. LOCAL ROD WITHDRAWAL ERROR (WITH LIMITING INSTRUMENT FAILURE)
TRANSIENT
SUMMARY
(5.2.1)
Rod Rod Block Fe U "" "! E Limiting Reading Withdrawn) 8x8 8x8R 8x8 8x8R Rod Pattern 105 4.0 O!12 0.14 13.9 15.6 Figure 6 106* 4.0 0.12 _0.14 13.9 15.6 Figure 6 107 4.5 0.14 0.16 14.0 15.7 Figure 6 108 5.0 0.16 0.17 14.1 15.8 Figure 6 109 6.5 0.20 0.21 14.3 16.1 Figure 6
- s{-)j 110 7.0 0.21 0.22 14.3 16.2 Figure 6
- Indicates setpoint selected 3
NEDO-26166 l
1 52 8i8 5 9 8Y8 8i8 8 8 O so 8 8'8 8 8 8 8 BIS B 8 8
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- !l !IIi!IIIII 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 3 P. 41 39 41 43 45 47 49 51 i
FUEL TYPE A = INiilAL CORE CENTRAL E =
8 = INITIAL CORE PERIPHER AL F =
C =80R8265L G=
0 = 8DRB283 H
- Figure 1. Reference Core Loading Pattern O
6
NEDO-24166
- 15. LOADING ERROR RESULTS* (5.5.4) f O j Limiting Event: Rotated Bundle 8DRB283 MCPR: 1.07**
- 16. CONTROL ROD DROP ANALYSIS RESULTS (5.5.1)
) Doppler Reactivity Coefficient: Figure 9 Accident Pesarivity Shape Functions: Figures 10 and 11 Scram Reactivity Functions: Figures 12 and 13 Plant specific analysis results
! Parameter not bounded: Accident Reactivity (cold)
Resultant peak enthalpies: 208 cal /gm
. O i
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i l
l l
- Using new rotated bundle analysis procedures described in Appendix A
- Includes added penalty of 0.02 imposed by NRC 5
i
NEDO-24166 O 100 45 C- 678 CRO IN PERCENT
~ 1 - NOMINAL SCRAM CURVE IN (-$)
2 - SCRAM CURVE USED IN ANALYSIS -
40 80 -
s.
- 35 70 -
- 30 60 -
2 M$
o C C >
G 50 -
t 2 3 ti4 20e O 40 -
2 15 30 -
20 - -
10 10 - _ y O I I O 1 0 2 3 4 l TIME (see)
Figure 2a. Scram Reactivity and Control Rod Drive Specifications - EOC2 O
7
NEDO-24166 0
100 , 45 C - 678 CRD IN PERCENT 1 - NOMINAL SCRAM CURVE IN (~$)
90 -
2 - SCRAM CURVE USED IN ANALYSIS 40 80 -
35 C
70 -
l 30 60 -
2
- 25 E I- E 2 >
0 50 -
5 t 5 m u 2 0 20 e 40 -
15 30 -
l l
10 20 -
10 - -
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Figure 2b. Scram Reactivity and Control Rod Drive Specifications E02 - 1000 5'd/t G
8
. . i NED0-24166 0 100 45 i i
C - 678 CRD IN PERCENT i
l 1 - NOMINAL SCRAM CURVE IN (-$) 1 90 -
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Figure 2c. Scram Reactivity and Control Rod Drive Specifications EOC - 2000 Mid/t O
9
NEDO-24166
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Figure 3b. Plant Response to Generator Load Rejection, Without Bypass EOC2 - 1000 FMd/t
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\)-,G Figure Sa. Plant Response to Feedwater Controller Failure EOC2 O O O -
O A p U . b b '
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TIME ISECl Tilf (SECl Figure 5b. Plant Response to Feedwater Controller Failure EOC - 1000 mwd /t uh"k u
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. - . . _ . _ . . . . . . - ~ . . .. . . - - - . - . - ~ _ . . . - - _ . - - - .- . . . - - . . .
i NEDO-24166-i lO j
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- l NOTES
- 1. ROD PATTERN IS 1/4 CORE MIRROR SYMMETRIC UPPER LEFT l QUADRANT SHOWN ON MAP
- 2. NUM8ERS INDICATE NUMBER OF NOTCHES WITHDRAWN OUT OF 48. BLANK IS A WITHORAWN ROD
- 3. ERROR ROD IS(13.42) i l
Figure 6. Limiting RWE Rod Pattern '
17
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Figure 8. Decay Ratio l O 19
NEDO-26166 4
0
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- 254 g SOUNDING VALUE FCR 280 cal /g. COLO A BOUNDING VALUE FOR 280 cal /g, HSB
$ CALCULATED VALUE - COLD
$ CALCULATED VALUE - HS8
- 30 I I I I I
~0 400 000 1200 1600 2000 2400 FUEL TEMPER ATURE (*C) l l
l Figure 9. Doppler Reactivity Coefficient Comparison for RDA O
20
NEDO-24166 O
20 16 -
k 00 C
$12 -
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l 38 - '
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I e BOUNDING VALUE FOR 280 cal /g
& CALCULATED VALUE 4 -
I o__ l i I I O 4 8 12 16 20 ROD POSITION (ft OUT) l l
l l l
Figure 10. RDA Reactivity Shape Function at 200C O
21
0 NEDO-24166 O
16 -
3 -
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O 2 12 -
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9 BOUNDING VALUE FOR 280 cal /g 4 _ A CALCULATED VALUE f I f a_ l 0 4 6 12 16 20 ROD POSITION (ft OUT) l Figure 11. RDA Reactivity Shape Function at 286 C 22
V NED0-24166 O
70 G BOUNDING VALUE FOR 280 cal /g g _
A CALCULATED VALUE 50 -
G 1
o z
N 3
0 40 -
t w
l A
' i O 2 y 30 -
5 m
20 -
i l
I 10 -
l u k I I i 0 .
O 2 4 6 8 10 ELAPSED TIME (sec)
Figure 12. RDA Scram Reactivity Function at 20 C a 23
___J
w NEDO-24166 O
100 9 BOUNOING VALUE FOR 280 cal /g
& CALCULATED VALUE i
l G b
O z
g so -
8
_b g
i
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0 .
0 2 4 6 8 10 ELAPSED TIME (sec)
Figure 13. RDA Scram Reactivity Function at 286 C 24
r 4
4 l NEDO-24166 O
V APPENDIX A NEW BUNDLE LOADING ERROR EVENT ANALYSES PROCEDURES The bundle loading error analyses results presented in Section 15 in this supplement are based on new analyses procedures for both the rotated bundle and
.the mislocated bundle loading error events. The use of these new analyses pro-cedures is discussed below.
j A.1 NEW ANALYSES PROCEDURE FOR THE ROTATED BUNDLE LOADING ERROR EVENT The rotated bundle loading error event analyses results presented in this sup-plement are based on the new analyses procedure described in References A-1 and A-2. This new method of performing the analyses is based on a more detailed analysis model, which reflects more accurate analyses than that used in previous i analyses of this event.
The principle difference between the previous analyses procedure and the new g analyses procedure is the modeling of the water gap along the axial length of the bundle. The previous analyses used a uniform water gap, whereas the new analyses
- utilize a variable water gap which ie representative of the actual condition.
The effect of the variable water gap is to reduce the power peaking and the R-factor in the upper regions of the limiting fuel rod. This results in the cal-
! culation of a reduced aCPR for the rotated bundle. The calculation was performed using the same analytical models as were previously used. The only change is in the simulation of the water gap, which more accurately represents the actual geometry.
In the new analyses, the axial alignment of a 180* rotated bundle conserv teively ignores the presence of the channel fastener. The more limiting condition of assuming that the spacer buttons are in contact with the top guide is assumed.
There is no known loading that could bend or break the channel spacer button during the insertion of a 180* rotated bundle, sinca both the top guide and spacer button are chamfered to provide lead-in. For a properly assembled bundle, no mechanism exists which could invalidate the assumption that a 180* rotated bundle leans to one side.
O v
i i( A-1 f I
s NEDO-24166 It should be noted that proper orientation of bundles in the reactor core is gg readily verified by visual observation and assured by verification procedures during core loading. Five separate visual indications of proper bundle orientation exist:
(1) The channel fastener assemblies, including the spring and guard used to maintain clearances between channels, are located at one corner of each fuel assembly adjacent to the center of the control rod.
(2) The identification boss on the fuel assembly handle points toward the adjacent control rod.
(3) The channel spacing buttons are adjacent to the control rod passage area.
(4) The assembly identification numbers which are located on the fuel
{ assembly handles are all readable from the direction of the center of the cell.
(5) There is cell-to-cell replication.
9 Experience has demonstrated that these design features are clearly visible so that any misloaded bundle would be readily identifiable during core loading verification. Figures A-1, A-2 and A-3 denote a normally loaded bundle, a 180*
l rotated bundle, and a 90* rotated bundle, respectively. Actual experience
! (References A-1 and A-2) has demonstrated that the probability of a rotated l
bundle is low.
l The new analyses procedure results show that the minimum CPR for the most limit-ing rotated bundle in the core is greater than the safety limit.
O A-2
r 9 * 'f
.t NEDO-24166 O arrzar c s A-1 Letter, R. E. Engel (GE) to D. Eisenhut (NRC), " Fuel Assembly Loading Error," MFN-219-77, June 1, 1977.
A-2 Letter, R. E. Engel (GE) to D. Eisenhut (NRC), " Fuel Assembly Loading
, Error," MFN-457-77, November 30, 1977.
1 l
9 8
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l l
l t
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NEDO-24166 i O II l
l l
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l O 'O O' o x - JK x z ,
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/
O <
O NOTE: SUNCLE NUMBERS ARE FOR ILLUSTRATIVE PURPOSES ONLY Figure A-1. Normal Loading A-4
l , .
I NEDO-24166 O
I
- F
\
180* ROTATION - 8UND LE LJ 2348 %
/
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t
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8 O[lO ll NOTE: SUNOLE NUMBERS ARE FOR ILLUSTRATIVE PURPOSES ONLY (
t i
ngure A-2. aocated sundle, 180 negree accation A-5
NEDO-24166 O
O' O'\
90' ROTATION - BUNOLE LJ 2348
/ /
/ /
O 'O - O 'O
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j \ /
/ \ / \
O
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v O[lO NOTE: SUNOLE NUM8ERS ARE FOR ILLUSTRATIVE PURPOSES ONLY I
1 Figure A-3. locatt! Sandle, 90 Degree Rotation l
A-6 f
l NEDO-24166 i
O APPENDIX B l l
' Fuel Loading Error LHCR: 17.1 Kw/ft i
l t
i O
i f
O-B-1/B-2 l
I
_ ___
