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Category:CORRESPONDENCE-LETTERS
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 ML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl ML20211K9001999-08-27027 August 1999 Forwards Insp Repts 50-324/99-05 & 50-325/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl ML20210S9061999-08-11011 August 1999 Informs That GE Document Entitled, Addl Info Regarding 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant ML20210S9121999-08-11011 August 1999 Informs That Document NEDC-31624P,Suppl 2,Rev 6,entitled, Loss-Of-Coolant Accident Analysis Rept for Brunswick Steam Electric Plant Unit 2,Reload 13,Cycle 14 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) ML20210P8221999-08-11011 August 1999 Advises That Info Contained in Which Submitted Document,Prepared by Siemens Power Corp,EMF-2168(P) Rev 0, Marked Proprietary,Will Be Withheld from Public Disclosure, Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20210P9381999-08-10010 August 1999 Forwards SE Accepting Licensee & Suppls & 0517,which Submitted Assessment of Impact on Operation of Unit 1 with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P8911999-08-10010 August 1999 Forwards SE Authorizing Relief Requests CIP-01,02,06,07,08, 09,10,11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Requests CIP-04 & 05 Would Result in Hardship,Relief CIP-03 Not Required & CIP-11 Denied in Part BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 ML20210Q4581999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section to Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit List of Individuals to Take exam,30 Days Before Exam Date ML20210P2031999-08-0505 August 1999 Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2 ML20210N2041999-08-0505 August 1999 Forwards SE Accepting Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46, & Suppl 1 BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld ML20210G2941999-07-28028 July 1999 Discusses Public Meeting Conducted on 990720 to Present Results of Periodic Plant Performance Review for Brunswick Facility for Period of May 1997 to January 1999.List of Attendees Encl BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR ML20210E1181999-07-19019 July 1999 Forwards Insp Repts 50-324/99-04 & 50-325/99-04 on 990509- 0619.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl ML20196H8191999-06-21021 June 1999 Informs That on 980915,Commission Suspended SALP Program for an Interim Period Until NRC Completes Review of Process for Assessing Performance at NPPs ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20196A8111999-06-14014 June 1999 Ack Receipt of 990401 Response to NRC Ltr Issued on 990302 Re OI Investigation to Determine Whether Former BSEP Manager Threatened to Fire Employees Who Brought Safety Concerns to Nrc.Concluded That No Violation Occurred ML20195J1971999-06-14014 June 1999 Advises That GE-NE-523-B13-01920-56,Rev 1,submitted with 990202 Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 BSEP-99-0092, Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld1999-06-0808 June 1999 Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld BSEP-99-0085, Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld1999-05-27027 May 1999 Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld BSEP-99-0078, Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT1999-05-17017 May 1999 Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT BSEP-99-0080, Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval1999-05-17017 May 1999 Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval BSEP-99-0083, Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6)1999-05-14014 May 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6) BSEP-99-0056, Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively1999-05-13013 May 1999 Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively BSEP-99-0073, Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by1999-05-12012 May 1999 Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by BSEP-99-0062, Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.171999-05-11011 May 1999 Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.17 BSEP-99-0079, Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-05-0707 May 1999 Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0066, Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided1999-05-0404 May 1999 Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided ML20195D6301999-04-30030 April 1999 Forwards Natl Marine Fisheries Svc Biological Opinion Based on Review of Continued Use of Cooling Water Intake Sys at Bsep.Rept Reviews Effects of Activity on Loggerhead,Kemps Ridley,Green,Hawksbill & Leatherback Sea Turtles BSEP-99-0071, Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6)1999-04-27027 April 1999 Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6) BSEP-99-0069, Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-171999-04-26026 April 1999 Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-17 BSEP-99-0063, Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link1999-04-21021 April 1999 Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link BSEP-99-0050, Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping,1999-04-0606 April 1999 Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, BSEP-99-0051, Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 21999-04-0101 April 1999 Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 2 BSEP-99-0015, Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-03-31031 March 1999 Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves 1999-09-08
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Text
9 CP&L '
. Carolina Power & Ught Company Brunswick S'eam Electr c P:aot P O Bot 104 '9
- Soumport. N C N461 September 10,1991 nussttu a. sTAnncy, s n.
SERIAL: NLS-91-233 vice Presideni m U R grg 1
Brunswick Nuclear Proinct TSC 91TSB14 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50425/UCENSE NO. DPR-71 REQUEST FOR UCENSE AMENDMENT ONE TIME EXTENSION OF ALLOWED OUT-OF-SERVICE TIME FOR DIESEL GENERATORS NUMBER 3 & 4 Gentlemen:
By letter dated August 22,1991 (Serial: NLS-91207), Carolina Power & Light Company (CP&L) requested a one-time revision to the Technical Specifications for the Brunswick Steam Electric Plant, Unit 1. The proposed revision would allow a one-time-only extension of the 7 day allowed out of-service time (AOT) for one inoperable diesel generator for each of Diesel Generators Number 3 and 4, to a 14 day AOT for one inoperable diesel generator for each of Diesel Generators Number 3 and 4 during the upcoming Unit 2 refueling wtage.
On August 30,1991, a conference call was conducted with members of the NRC Staff to discuss Staff questions concoming the request. Enclosure 1 summarizes the Staff's questions and CP&L's responses.
Enclosure 2 provides the typed Technical Specification pages for the Staff's convenience in issuing the proposed request.
The Company has reviewed the 10 CFR 50.92 evaluation provided in our August 22,1991 license amendment request and has determined that the evaluation is not affected by the information provided in the enclosed responses.
Please refer any questions regarding this submittal to Mr. M. R. Oates at (919) 546-6063.
Yours very truly, R. B. Starkey, Jr.
JCP/WRM/wrm (edg-ral.wpf)
Enclosures:
- 1. Summary of Staff Questions and CP&L Responses
- 2. Technical Specification Pages - Unit 1 9109270114 910910 ;( &
POR ADOCK 0500G?25 \ '\\
P PDR
cc: Mr. Dayne H. Brown Mr. S. D. Ebneter Mr. N. B. Le Mr. R. L Prevatte R. B. Starkey, Jr., 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.
MA c w k k Nota'ty (Seal) 'd My commission expires: b ja)li %
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ENCLOSURE 1 CRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET NO. 50-325 OPERATING LICENSE NO. DPR-71 REQUEST FOR UCENSE AMENDMENT ONE-TIME EXTENSION OF ALLOWED OUT-OF-SERVICE TIME FOR DIESEL GENERATORS NUMBER 3 & 4
SUMMARY
OF STAFF QUESTIONS AND CP&L RESPONSES NRC Ouestion 1:
Enclosure 1 Table 2 lists the equipment available to safely shut down Unit 1 during a worst case LOCA.
Please clarify the conditions assumed for this worst case LOCA.
CP&L Resoonse 1:
The worst caso LOCA discussed in Enclosure 1 of our August 22,1991 submittal assumes a loss of coolant accident coincident with a loss of offsite power along with an assumed single falture.
NRC Ouestion 2:
Surveillance tests satisfying Technical Specifications 4.8.1.1.2.d.2 through 4.8.1.1.2.d.7 were performed during the recent diesel generator outage. Since the requirements of Technical Specification 4.8.1.1.2.d will be satisfied through the performance of ihe planned diesel generator maintenance, will a mid-cycle outage be necessary to re-perform these surveillances?
CP&L Resoonse 2:
Technical Specifications 4.8.1.1.2.d.2 through 4.8.1.1.2.d.7 will be re-performed to demonstrate the operability of Diesel Generators Number 3 and 4 following the planned maintenance activities.
Therefore, the 18 month surveillance interval will be reset during this outage and thus will not be required to be performed again until the next Unit 2 Refueling Outage.
NRC Ouestion 3:
Provide a revised schedule for the maintenance work planned for Diesel Generators Number 3 and 4 during the outage based on a 14 day LCO.
CP&L Resoonse 3:
A revised schedule for tlie maintenance work planned for Diesel Generators Number 3 and 4 during the outage, based on a 14 day LCO is provided as Attachment 1 to this enclosure. ,
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4 NRC Ouestion 4:
Please revise the footnote proposed for Technical Specification 3.8.1.1,- Actions b.3, c.3, and e.3 to indicate that only one diesel generator (i.e., Diesel Generator Number 3 g Diesel Generator Number 4) will be removed from service at the same time for planned maintenance work.
CP&L Resoonse 4:
The typed Technical Specification pages enclosed include a revisicn to the subject footnote to clearly Indicate that only one diesel generator at a time will be removed from service for the malntenance work.
NRC Ouestion 5:
In the August 22,1991 submittal. CP&L stated that unless required by Technical Specifications, testing and maintenance that would increase the likelihood of a plant transient during the period of diesel generator ma!ntenance would be avoided. Please identify any surveillance tests scheduled for performance during the time periods that Diesel Gencntors Number 3 and 4 will be out of service for maintenance.
CPSL Responsel:
Attachment 2 to this enclosure lists those periodic tests required by Technical Specifications to be completed during periods of time that Diesel Generators Number 3 and 4 are scheduled to be out of service during Unit 2, Refueling Outage Number 9. These periodic tests will be performed as scheduled with the exception of those listed in Attachment 3 to tbJs enclosure.
NRC Ouestion 6:
l Provide the estimated man-hours required to perform suiveillance procedure OMST-DG500.
CP&L Retoonse 6:
! OMST-DG500, " Emergency Diesel Generators inspection
- is the Brunswick Plant procedure which satisfies the inspection requirements of Technical Specification 4.8.1.1.2.d.1. This procedure requires the tear down of the diesel generator for inspection in order to ensure that the diesel generators are functioning properly and to inspect for any potential problems. Approximately ") man-hours are l necessary to perform OMST-DG500, requiring two 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> e uver a time period of l
approximately six days.
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NRC Ouestion 7:
Provide a clarification with respect to the overlapping of the transformer work (l. e., bushing replacement) with the planned diesel generator work scheduled to be performed during the outage.
. CP&L Resnonse 7:
1 Per the current Ur F 2 outage schedule, the Unit Auxillary Transformer (UAT) work (1. e., bushing replacement) wi8 ue completed prior to entering the first 14 day AOT for diesel generator maintenance.
Additional Clarifications:
During the August 30,1991, conference call CP&L provided the following clarifications to the August 22, 1991 license amendment request:
- 1. During the first 14 day diesel ge 1erator maintenance outage (Diesel Generator Number 3), the reactor vessel will be defueled. During the second 14 day diesel generator maintenance outage (Diesel Generator Number 4), the reactor vessel will have been refueled; however, a!i emergency core cooling systems required by Technical Specifications to be operable during this p; ant state will be operable.
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A'ITACHMENT 1 TO ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET NO. 50-325 OPERATING UCENSE NO. DPR-71 REQUEST FOR UCENSE AMENDMENT
, ONE-TIME EXTENSION OF ALLOWED OUT-OF-SERVICE TIME FOR DIESEL GENERATORS NUMBER 3 & 4 Revised Schedule for Maintenance Work Planned for DG # 3 & #4 Based on 14 Day Allowed Out of Service Time for One Inoperable Diesel Generator DIESEL GENERATOR NUMBER 3 October 2,1991 through Octob3r 13,1991 Hang Clearance for Diesel Generator Number 3, Start 14 Day LCO Take Crankshaft Deflection Readings on Diesel Generator Number 3 Hang Electrical Clearance for Overload Relay for DG Building Supply Fan Perform Preventatlve Maintenance on DG Engine Pump Add Oil to and Calibrate Engine Crankcase Vacuum Pressure indicator Check Water B% ster Pump Light inspect /Peplace Isolation Amplifier of Exciter Current Transducer Replace Fuel Oil Discharge Strainer Differential Pressure Switch Replace Fuel Oil Duplex Filter Differential Pressure Switch Install Flex Conduit Connector Perform OMST-DG500, Crankcase 7.2.1 Perform OMST DG500, Valve Gear and Injectors 7.2.2 Remove / Rework / Replace the Overload Relay for DG Building Supply Fan inspect Jacket Water Cooler Perform Preventative Maintenanca on Starting and Control Air Filters Perform OMST-DG500 for DG Traps and Strainers 7.2.3 Perform OMST-DG500 Lubrication for DG 7.2.4 Change Oil for DG Engine Air intake Filter inspect Check Valves for Service Water Inlet to DG Jacket Water Cooler Perform OMST-DG500 Generator 7.2.5 Perform OMST-DG500 Turbocharger 7.2.6 Perform OMST-DG500 Cooling Water 7.2.7 Perform OMST-DG500 Jacket Water Heat Exchanger 7.2.8 Remove Electrical Cimrance for Overload Relay for DG Building Supply Fan Perform Acceptance . act for Overload Relay for DG Building Supply Fan Perform OMST-DG500 crankcase & Bedplate 7.3.1 Perform 0MST-DG500 Cam Shaft & Drive Adjustments 7,3.2 Perform OMST-DG500 System Checks 7.4 Change Oil in DG#3 Perform 2MST-DG21R (Diesei Generator Trip Logic Test)
Replace DG Housing Bolt inspect and Raplace Cam Shaft Bearings E1 -4
l Repair Leaking Pipe Union Replace Test Valve at Engine Jacket Water Heater Circulating Pump Suction Replace Filter and Pre lube Pump Outlet Flow Control Valve Pilot Solenoid Valve Replace Filter & Pre-lube Pump Outlet Flow Control Valve Pilot Solenoid Valve investigate Chattering DG Engine Jet Assist Right Header Check Va ve Replace Run in DG Engine Control Panel Calibrate DG Engine Start Air Pressure Switch, Right Header Repair Crank Case Blower Leak Repair DG 3 Jacket Watar Cooler Outlet Temperature Control Valve Remove & Reinstall DG 3 Starting Air Tank B Pressure Relief Valve Calibrate DG Engine Start Air Pressure Switch, Left Header Repair DG 3 Lube Oil Line Union Leak Repair DG 3 Lube Oil Automatic Temperature Control Valve Trouble Shoot Auxiliary Lube Oil Pump Replace Pre-Lube Solenoid Valve in Engine Control Panet Calibrate DG Engine Lube Oil Filter Differential Pressure Switch Process Required Operability for DG#3 Repair left Bank Air Distributor Rebuild Right Bank Air Distributor Repair Jacket Water Leak Repair Union Leak Remove Clearance DG #3 Perform Valve and Electrical Uneup Fill and Vent the System Perform OPT 12.2C (No. 3 Diesel Generator Monthly Load Test) and Place DG #3 in Service DIESEL GENERATOR NUMBER 4 November 4,1991 through November 15,1991 Hang Clearance for Overload Relay for Lube Oil Filter Heater Remove / Rework / Replace Overload Relay for DG Lube Oil Filter Heater Harg Clearance for DG 4 Outage - Start 14 Day LCO Take Crankshaft Deflections on DG 4 Hang Clearance for Overload Relay for Fuel Oil Transfer Pump Perform OMST-DG500 Crankcase 7.2.1 Inspect Jacket Water Cooler Change Oil in DG 4 Add Oil to DG Engine Control Panel 1 and Calibrate Replace Panel Heater Strip Calibrate DC Timing Relay (Auxiliary Relay to DG Starter)
Calibrate DG Exciter Field Shorting Relay Replace DG Exciter Current Transducer Replace DG Fuel Oil Discharge Strainer Differential Pressure Switch Replace DG Fuel Oil Duplex Filter Pressure Switch Check Wiring on DG Oil Booster Pump Perform OMST-DG500 Valve and Gear Injectors 7.2.2 Remove / Rework / Replace Overload Relay for DG Fuel Oil Transfer Pump Perform Preventative Maintenance on Starting and Control Air Filters Perform Preventative Maintenance on Engine Pumps E l-5 I
Repair Lube Oil Cooler Flange Leak Check Vale Disassembly Test on Check Valve for Service Water inlet to Jacket Water Cooler Check Valve Inspections on Check Valve for Service Water Inlet to Jacket Water Cooler Perform OMST-DG500 Traps & Strainers 7.2.3 Perform OMST-DG500 Lubrication 7.2.4 Perform OMST-DG500 Generator 7.2.5 Perform OMST-DG500 Turbocharger 7.2.6 Remove Clearance from Overioad Relay for DG Lube Oil Filter Heater Perform OMST-DG500, Cooling Water 7.2.7 Perform OMST-DG500, Jacket Water Heat Exchanger,7.2.8 Perform Acceptance Test on Overload Relay for DG Lube Oil Filter Heater Remove Clearance from Overload Relay for DG Fuel Oil Transfer Pump Perform Acceptance Test on Overload Relay for DG Fuel Oil Transfer Pump Perform OMST-DG500, Crankcase and Bedplate,7.3.1 Perform OMST-DG500, Cam Shaft and Drive Train Adjustments,7.3.2 Perform 0MST-DG500, System Checks,7.4 Change DG Engine Air intake Filter Perform 2-MST-DG22R (DG #4 Trip Bypass Logic Test)
Inspoet/ Replace Cam Shaft Bearings Repair / Replace DG 4 Jacket Water Cooler Outlet Temperature Control Vane Replace Test Valve at DG Engine Jacket Water Heatar Check Engine Lube Oil Filter Heater Temperature Switch Flush Engine Lube Oil inlet Pressure Indicator Test Connection Replace Temperature Indicator for Engine Jacket Water Outlet Header Replace and Calibrate Pressure Switch for Service Water Engino Jacket Water Cooler Replace Run/ Shutdown Solenoid Valve on DG 4 Trouble Shoot DG 4 Engine Jet Assist Solenoid Valve Repalt 3/4" Conduit Clamp on inlet Supply Une to DG 4 Excess Fuel Oil Return To Day Tank Line Replace Handle on DG 4 Lube Oil Automatic Temperature Control Valve Repair Oil Leak on DG 4 Crankcase Vacuum Blower Calibrate Volt Meter for 4160 V Bus E4 Replace Defective Relay for DG 4 Four Day Tank Fuel Oil Inlet Replace Pre-lube Solenoid Valve in Engine Control Panel Repair DG 4 Engine Jacket Water Head Tank Demineralizer Water Fill Valve .
Evaluate Set Point Tolerance on DG Lube Oil Differential Pressure Switch Remove and Replace the Auxiliary Lube Oil Pump Remove and Replace the Jacket Water Pump Process Operability for DG #4 Pull Clearance for DG #4 Perform Valve and Electrical Lineups Fill and Vent the System Perform OPT.12.2D (No. 4 Diesel Generator Monthly Load Test) and Place DG #4 in Service Ele
a ATTACHMENT 2 TO ENCLOSURE 1 i
BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET NO. 50-325
- OPERATING LICENSE NO. DPR-71.
REQUEST FOR LICENSE AMENDMENT ONE-TIME EXTENSION OF ALLOWED OlJT-OF-SERVICE TIME FOR DIESEL GENERATORS NUMBER 3 & 4 Surveillance Tests Required by Technical Specifications To Be Completed During AOT for DG # 3 and
- 4 During Unit 2 Refueling Outage Number 9 DIESEL GENERATOR NUMBER 3 OUTAGE SCHEDULE OVERDUE' PROCEDURE TITLE DATE DATE OPT-21.1 A - Control Room Emergency Filters Weekly Run Time Check 10/7/91 10/8/91 OE&RC-2003 - Reporting of Radioactive Airborne Effluent Releases 10/7/91 10/14/91 OE&RC-2009 - Radioactive Uquid Effluent Releases & Reports 10/2/91 10/9/91
~ OE&RC-3101 - Radiological Environmental Tech Spec Monitoring 10/7/91 10/8/91 OMST-BATT12W - Batteries Fire Pump Diesel Start Weekly Operability Test 10/8/91 10/9/91 P
OMST-DG24M - Emergency Bus Degraded Voltage Channel Functional Test 10/5/91 10/12/91 OPT-23.1 - Control Room Emergency Filtration Systems Operability Test 10/8/91 10/15/91 OPT-34.1.1.0 - Fire Pump Test (Motor Driven & Engine Driven) 10/5/91 10/6/91 OPT 34.2.2.2 - Reactor Buildings 1 & 2, AOG and Service Water Buildings Fire Barrier Visual Inspection 10/4/91 10/11/91 OPT-34 2.3.3'- Hose Station Inspection Control Building & Radwaste - 10/4/91 10/11/91 0FT-34.2.3.4 - Hose Station inspection Diesel Generator Building 10/4/91 10/11/91 OPT-34.2.3.5 - Hose Station Inspection AOG & Service Water Buildings 10/5/91 10/12/91 OPT-34.2.4.3 - Fire Detection System Nonsupervised Circuit Testing
_ Control Building 10/5/91 10/12/91
- OPT-34.2.4.4 Fire Detection System Nonsupervised Circuit Teating l Diesel Generator Building 10/5/91 10/12/91 i
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' j OPT-34.2.4.5 - Fire Detection System Nonsupervised Circuit Testing AOG Building 10/5/91 10/12/91 OPT-15.1 - Standby Gas Treatment System Filter Test - 10/9/91 2/23/92 -
OPT-15.1 A Standby Gas Treatment Filters Week 1y Run Check 10/7/91 10/8/91
- j. and 10/14/91 10/15/91 OE&RC-1000 Sampling & Analysis Schedule for Tech Specs 10/7/91 10/8/91 and 10/14/91 10/15/91 OE&RC-1221 - Sampling & Analysis Procedure for Routine Swam Jet Air Elector Off Gas 10/9/91 10/16/91 OE&RC-2002 - Sampling of Radioactive Airborne Effluent Releases 10/8/91 10/9/91 and 10/15/91 10/16/91 OE&RC-2009 - Radioactive Liquid Effluent Releases and Reports 10/9/91 10/10$1 and 10/16/91 10/17/91 OE&RC-2019 - Main Condenser Steam Jet Air Ejector
( Radioactivity Monitor 10/9/91 10/16/91 l
l- 1MST-BATT11W - Batteries 125VDC Weekly Operability Test 10/9/91 10/10/91 and 10/16/91 10/17/91 1MST-APRM11W & -APRM12W - APRM Channel Functional Test 10/8/91 10/9/91 and 10/15/91 10/16/91 1MST APRM21W - APRM $5% Trip and Inoperable Channel Functional Test / Calibration 10/3/91 10/4/91 and 10/10/91 10/11S1 1MST-HPCl240 & HPCl250 - HPCI Steam Leak Detection Channel Calibration 10/2/91 10/23/91 1MST-IRM11W & -IRM12W - lRM Channel Functional Test 10/3/91 10/4/91 and 10/10/91 10/11/91 1MST-PCIS21M & -PCIS29M - PCIS Reactor Water Low Level 2 and Low Level 3 Division 1 and Division 2 Trip Logic - Channel Functional Test and Channel Calibration 10/5/91 10/12/91 1MST-PCIS24M - PCIS Low Main Steam Line Pressure Channel 10/5/91 10/12/91 Calibration l
1MST-RCIC13M, -RCIC14M & -RCIC15M - RCIC Steam Leak Detection
- Channel Functional Test 10/6/91 10/7/91 l
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9 1MST-RCIC21M - RCIC Steam Line Break High Delta / Pressure Trip Logic Channel Calibration 10/5/91 10/12/91
- 1MST-RCIC22M - RCIC Steam Line Low Pressure Channel Calibration 10/8/91 10/15S1 1MST-RCIC23M - RCIC Turbine Diaphragm High Pressure Channel Calibration 10/5/91 10/12/91 1MST RCIC24Q - RCIC Steam Leak Detection Channel Calibration 10/7/91 10/28/91 1MST-RCIC26M - RCIC Reactor High Water Level Trip Logic Channel Calibration -10/5/91 10/12/91 1MST-RPS11W - Main Steam Line High Radiation Channel Functional Test 10/8/91 10/9/91 and 10/15/91 10/16/91 1MST-RPS24M RPS Reactor Vessel Water Low Level 1 Trip Logic Channel Calibration 10/7/91 10/14/91 1MST-RSDP21Q - Remote Shut Down Panel Reactor Vessel Water Level Channel Calibration 10/5/91 10/26/91 1MST-SRM11W - SRM Channel functional Test 10/3/91 10/4/91 and 10/10/91 10/11/91 CPLO3.1.22 - Reactor Coolant Recirculation System Valve Operability Test 10/5/91 10/6/91 and 10/12/91 10/13/91 OPT-08.2.4 - RHR Cervice Water System Component Test 10/6/91 10/13/91 OPT /J9.2 - HPCI System Operability Test 10/3/91 10#4/91 OPT-09.3A - HPCI System Component Test 10/3/91 10/10/91 f
OPT 10.1.1 A - RCIC System Component Test 10/9/91 10/16/91 OPT-11.3 - Drywell Drains System Valve Operability Test 10/5/91 10/6/91 and 10/12/91 10/13/91 OPT-14.0 - Control Rod Drive System Valve Operability Test 10/5/91 10/6/91 l and 10/12/91 10/13/91 OPT-15.6 - Standby Gas Treatment System Operability Test 10/3/91 10/10/91
- OPT-16.1.1 - Containment Atmosphere Control System l Operability Test 10/5/91 10/6/91 l and 10/12/91 10/13/91 OPT-24.1.2 - Service Water Miscellaneous Service Water Valve Operability Test 10/7/91 10/30/91 and 10/12/91 10/13/91 l
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1PT-24.1.1 Service Water Lube Water Pump and Valve Operability Test 10/8/91 10/31/91 1PT-34.2.4.1 - Fire Detection System Nonsupervised Circuit Test 10/5/91 10/12/91 OE&RC-1231 - Sampling & Analysis for Tritiated Water 10/16/91 10/23/91 1MST-AM127M - AMI Suppression Pool Temperature Monitor Channel Functional Test 10/13/91 10/20/91 1MST-APRM11M - APRM Rod Block Functional Test 10/15/91 10/22/91 1MST-CUNT 11M -CLINT12M - Chloride Intrusion Monitor 1MST-CUNT 13M -CUNT 14M - Channel Functional Test &
- & 1MST-CUNT 15M Setpoint Calibration 10/12/91 10/19/91 1MST-CS21M - Core Spray Pump Discharge ADS Permissive Channel Functional Test 10/12/91 10/19/91 1MST-HPCl26M - HPCI Suppression Pool High Level Channel Functional Test 10/13/91 10/20$1 1MST-PCIS22M - PCIS Low Main Steam Une Pressure Trip Logic Channel Calibration 10/12/91 10/19/91 1MST-PCIS25M, -PCIS26M - PCIS High Main Steam Une Flow Trip 1MST-PM27M & -PCIS28M - Logic Channel Calibration 10/12/91 10/19/91 l 1MST-RBM11M RBM Channel Functional Test 10/12/91 10/19/91 1MST-RGE21M - Radioactive Gaseous Effluent Monitoring for Main Condenser Off-Gas Treatment System Recombiner Hydrogen Monitors Channel Functional Test 10/12/91 10/19/91 1MST-RWCU21M - RWCU High Differential Flow Trip Logic Channel Functional Test 10/12/91 10/19/91 1MST-RWCU22M - RWCU Steam Leak Detection Channel Functional Test 10/12/91 10/19/91 OPT-02.1.22 - Primary Containment ;oolation System Main Steam Line Area High Temperature Channel Functional Test 10/11/91 10/18/91 OPT-06.1 - Standby Liquid Control Operability Test 10/10/91 10/17/91 OPT-07.1.0 - Core Spray System Component Test 10/15/91 10#2/91 OPT-08.1.4A - RHR Service Wr.ter Systern Operability Test Loop A 10/10/91 10/20/91 OPT-12.2A - Diesel Generator 1 Monthly Load Test 10/14/91 10/21/91 OPT-12.3.2A - DG 1 Starting Air Receiver Check Valve 10/14/91 1101/91 E1 -10
OPT-12.4A - DG 1 Fuel Oil Transfer Pump Test 10/14/91 11A1S1 ,
l OPT 24.0 - Service Water System Valve Uneup Verification 10/11/91 10/18/91 l
DIESEL GENERATOP NUMBER 4 OUTAGE SCHEDULED OVERDUE PROCEDURE TITLE DATE DATE OPT-21.1 A - Control Room Emergency Filters Weekly Run Time Check 11/4/91 11/5/91 OE&RC-200' Reporting of Radioactive Airborne Releases 11/7/91 11/14/91 OE&RC-3101 Radiological Environmental Tech Spec Monitoring 11/4/91 11/5/91 OMST-BATT120 - Batteries Fire Pump Diesel Start Quarterly Operability Test 11/12/91 12/3/91 OMST BATT12W - Batteries Fire Pump Diesel Start Operability Test 11/5/91 11/6/91 OPT-21.3 - Control Room Emergency Filtration Systems Operability Test 11/8/91 11/15/91 OPT-34.2.2.2 - Reactor Buildings 1 & 2, AOG and Service Water Buildings Fire Barrier Penetrations Visual inspection 11/4/91 11/11/91 OPT-34.2.3.3 - Hose Station inspection Control Building & Radwaste 11/4/91 11/11/91 OPT-34.2.3.4 - Hose Station inspection Diesel Generator Building 11/4/91 11/11/91 OPT-34.2.3.5 - Hose Station inspection AOG & Service Water Buildings 11/5/91 11/12/91 OPT-34.2.4.3 - Fire Detection System Nonsupervised Circuit Testing Control Building 11/5/91 11/12/91 OPT-34.2.4.4 Fire Detection System Nonsupervised Circuit Testing Diesel Generator Building 11/5/91 11/12/91 OPT-34.2.4.5 - Fire Detection System Nonsupervised Circuit Testing AOG Building 11/5/91 11/12/91 OPT-15.1 A - Standby Gas Treatment Filters Weekly Run Check 11/4/91 11/5/91 and 11/11/91 '1/12/91 OE&RC-1000 - Sampling & Analysis Schedule for Tech Specs 11/4/91 11/5/91 and 11/11/91 11/12/91 OE&RC-2002 - Sampling of Radioactive Airborne Effluent Releases 11/5/91 11/6/91 and 11/12/91 11/13/91 El-11
OE&RC-2009 Radioactive Liquid Effluent Releases and Reports 11/6/91 11/7/91 and 11/13/91 11/14/91 OPT-77.3 - Condensate Pump Discharge Chlorido intrusion Monitor Channel Calibration 11/7/91 12/23/91 1MST-BATT11W - Batteries 125VDC Weekly Operability Test 11/6/91 11/7/91 and 11/13/91 11/14/91 1MST-APRM11W & -APRM12W - APRM Channel Functional Test 11/5/91 11/6/91 and 11/12/91 11/13/91 1MST-APRM21W - APRM 15% Trip and inoperable Channel Functional Test / Calibration 11/7/91 11/8/91 and 11/14/91 11/15/91 1MST-APRM230, -APRM240 & -APRM260 - APRM Channel Calibration
& Functional Test 11/3/91 11/ES/91 1MST-APRM280 - APRF' Flow Bias Flow Units A & B Channel Calibration 11/3/91 11/26/91 1MST-CAC260 - CAC Division 1 Drywell Hydrogen & Oxygen Monitors Channel Calibration 11/5/91 11/28/91 1MST-CUNT 15M - Chlorido intrusion Monitor Channel Functional Test and Setpoint Calibration 11/8/91 11/15 S 1 1MST-IRM11W & -IRM12W - IRM Channel Functional Test 11/7/91 11/8/91 and 11/14/91 11/15/91 1MST-RCIC13M, -RCIC14M & -RCIC15M - RCIC Steam Leak Detection Channel Functional Test 11/3/91 11/10S1 ,
1MST-RCIC22M - RCIC Steam Lino Low P essure Channel Calibration 11/5/91 11/12/91 1MST-RGE110 - Radioactive Gaseous Eff. n: N1onitoring for AOG Effluent Nobic Gas Radiation Monitor Channel Functional Test 11/6/91 11/29/91 IMST-RPS11W - Main Steam Line High Radiation Channel Functional Test 11/5/91 1/6/91 and 11/12/91 11/13/91 1MST-RPS24M - RPS Reactor Vessel Water Low Level 1 Trip Logic Channel Calibration 11/4/91 11/11/91 1MST-SRM11W - SRM Channel Functional Test 11/7/91 11/8/91 and 11/14/91 11/15/91 El-12
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OPT-06.1 Standby IJquid Control Operability lest 11/7/91 11/14/91 OPT-08.2.4 RHR Service Water Fystem Component Test 11/0/91 11/13$1 OPT 49.2.3 HPCI System Short Operability Test 11/7/91 11A8/91 OPT 10.1.1 A RCIC System Component Test 11/0/91 11/13/91 1PT 34.2.4.1 Fire Detection System Nonsupervised Circuit Test 11/5/91 11/12/91 OE&RC 1221 Sampling & AnalyAocedure for Routine Steam Jet Air Ejector Off Gas 11/9/91 11/16/91 OE&RC-2019 Main Condenser Steam Jet Alr Ejector Radioactivity Monitor 11/9/91 11/10/91 IMST-AMl27M AM! Suppression Poni T^mporature Monitor Channel Functional * .!:,1 11/10/91 11/17/91 1MST-APAM11M APR' ~ Pod Bica : fr x:tional Test 11/12/91 11/19/91 1MST APRM290 APRI * .v Blat t ;ow Uni's C & D Channel 11/12/91 12S5/91 Calibration 1MST CLINT11M. -CUNT 12M. Chloride Intrusion Monitor Channel 1MST-CUNT 13M -CUNT 14M - Functional Test & Sotpoint Calibratio1 11/9/91 11/10/91 l
1MST-CS21M Coro Spray Pump Discharge ADS Permissive Channel Forctional Test 11/9/91 11/10/91 1 MST-CS21' Core Spray Sparpr High Differential Pressure Channel Calibration 11/10/91 12/1/91 l
l 1MST-HPCl; .1 HPCI St.opression Pool High Level Channel Functional Test 11/13/91 11/20S1 IMST-PCIS22M PCIS Low Main Steam Line Pressure Trip
! mic Channel Calibration 11/9/91 11/16/91 1MST-PCIS20V -PCIS2GM - PCIS High Main Steam Une Flow Trip l 1MST-PCIS27M & -PCIS28M - Logic Channel Calibration 11/9/91 11/10/91 l
-1MST-RBM11M - RBM Channel Functional Test 11/9/91 11/16/91 1MST-RGE21M Radioactive Gaseous Effluent Monitoring for Main Condenser Off-Gas Treatment System Explosive Gas Monitoring System Recombiner Hydrogen Monitors Channel Functional Test 11/9/91 11/16/91 l E1-13 i
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1MST.RWCluiM RWCU High Differential Flow Trip Logle Channel Functional Test 11/9/91- 11/10$1 1MST-RWCU22M - RWCU Steam Loak Detection Channel Functional 11/9/91 11/10/91 Test OPT-02.1.22 Primary Containment isolation System Main Steam Uno Arca High Temperature Channel Functional Test 11/11/91 11/18/91 OPT-03.1.22 Roactor Coolant Rocirculation System Valvo Operability Test 11/9/91 11/10/91 and 11/16/91 11/17S1 OPT 47.1.8 - Coro Spray System Component Test 11/12/91 11/19/91 OPT 11.3 - Drywell Drains System Valvo Operability Test 11/9/91 11/10/91 and 11/10/91 11/17/91 OPT 12.2A - Diosol Generator 1 Monthly Load Test 11/11/91 11/18/91 OPT 14.0 Control Rod Drive System Valve Operability Test 11/9/91 11/10/91-and 11/10/91 11/17S1 OPT 16.1.1 Containment Atmosphoto Control System Operability Test 11/9/91 12/2/91 OPT.::4.0 - Service Water System Valve Lineup Verification 11/11/91 11/18/91 OPT-24.1.2 - Service Water Miscellaneous Servico Water Valve Operab!4ty Test 11/9/91 11/10/91 and 11/16/91 11/17/91 OPT-40.2.8 - Main Steam Line isolation Valvo Closure Testing 11/9/91 11/16S1 OPT 40.2.9 Turbine Control Valve /Stop Valve Closuro Testing 11/9/91 11/10/91 i 1PT-24.11 Service Water t' ump and Discharge Valva l Operab;lity Test 11/10/91 11/13S1 l
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= 1 ATTACHMENT 3 TO ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET NO,50-325 OPERATING LICENSE NO. DPR 71 REQUEST FOR LICENSE AMENDMENT ONE TIME EXTENSION OF ALLOWED OUT-OF SERVICE TIME FOR DIESEL GENERATORS NUMBER 3 & 4 Surveillance Tests Listed in Attachmont 2 That Will Be Performed Outside Of The 14 Day Allowed Out-Of-Service Tirres (AOTs)For Diesel Generators Number 3 & 4 PROCEDURE TITLE 1MST-RSDP210 Remote Shut Down Panoi Reactor Water Level Channel Calibration 1MST-APRM230 APRM C Channel Calibration and Channel Functional Test 1MST APRM240 APRM D Channel Calibration and Channel Functional Test 1MST-APRM260 - APRM F Channel Calibratlon and Channel Functional Test 1MST APRM280 APRM Flow Blas Flow Units A and B Channel Calibration OMST-BATT120 - Batteries Fire Pump Diesel Start Quarterly Operability Test 1MST-APRM290 APRM Flow Blas Flow Units C and D Channel Calibration i
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ENCLOSURE 2 BPUNSWICK STEAM ELECTRIO PLANT, UNIT 1 NRC DOCKET NO. 50 325 OPERATING LICENSE NO. DPR 71 REQUEST FOR LICENSE AMENDMENT ONE TIME EXTENSION OF ALLOWED OUT-OF-SERVICE TIME FOR ,
DIESEL GENERATORS NUMBER 3 & 4 TECHNICAL SPECIFICATION PAGES - UNIT 1 i
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