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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
Carchna Power & Light Company February 20, 1979 FILE: NG 3514(B) SERIAL: GD-79-454 Office of Nuclear Reactor Regulation ATTENTION: Mr. T. A. Ippolito, Chief Operating Reactors Branch No. 3 United States Nuclear Regulatory Commission Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 HYDRAULIC SNUBBERS REQUEST FOR TECHNICAL SPECIFICATION CHANGE
Dear Mr. Ippolito:
In accordance with the Code of Federal Regulations Title 10, Part 50.90 and Part 2.101, Carolina Power & Light Company hereby requests revisions to the Technical Specifications for its Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. These revisions concern the hydraulic snubber inspection program.
The hydraulic snubber program required by Section 4.7.5.2 of the Technical Specifications for BSEP Unit Nos. 1 and 2 consists of performing a visual inspection to determine operability of all of the snubbers. One of the visual inspections required is to check the fluid levels in the hydraulic reser-voirs. Based on design input from the snubber manufacturer and the plant architect / engineer, a recommended fluid level was determined. Snubbers that do not contain their recommended fluid levels are removed from service and functionally tested to determine physical operability. It has been BSEP's
. experience that a low fluid level does not necessarily constitute an inoperable snubber; i.e., a large percentage of snubbers with low fluid levels have been demonstrated to be operable by performing their design functions of stroking, locking up, and bleeding off in the prescribed manner. The proposed revision to the Technical Specifications will allow the plant to perform functional tests to verify operability of all snubbers as required by Section 4.7.5.2 of the Technical Specifications.
The revisions to Table 3.7.5-1 were necessitated by a reclassification of the Reactor Water Cleanup System (RWCU). This reclassification downgraded the portions of the system beyond the outboard containment isolation valve as non-safety. Other revisions to the table are corrections to clerical and typographical errors.
790za7o37,7 m ,m +,t ~**g& w ?_ _ -v1 411 Fayattev'lle Street e P, O Box 1551 + Rafergh, N. C. 27602
"""*"m-C_maa ru . n%C3
Mr. T. A. Ippolito February 20, 1979 Changes to the Technical Specifications are indicated by a vertical bar in the right-hand margin of the affected pages which are attached.
In accordance with 10CFR170.12(c), we have determined that this request constitutes one Class III Amendment because it involves a single technical issue and a duplicate Class I Amendment. Our check for $4,400 is enclosed as payment for these amendment fees.
Should you have any questions concerning this request, please contact our staff.
Yours very truly,
/ /s r
,f WYh>
E. E. Utley n< '4)
Senior Vice President Power Supply JAM /LRH/mf Attachments Sworn to and subscribed before me this 20th day of February,1979 5 W WDAAltli ,
Notary'Public My Commission Expires: October 4, 1981 #""""%
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i PLANT SYSTEMS 3/4.7.5 HYDRAULIC SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.5 All hydraulic snubbers shown in Table 3.7.5-1 shall be OPERABLE.
APPLICABILITY: CONDITIONS 1, 2 and 3 ACTION:
With one or more hydraulic snubbers inoperable, restore the inoperable snubber (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.5.1 Hydraulic snubbers shown in Table 3.7.5-1 shall be demonstrated OPERABLE by the performance of the following augmented inservice inspec-tion program and the requirements of Specification 4.0.5.
4.7.5.2 Each hydraulic snubber with seal material fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment and approved as such by the NRC, shall be deter-mined OPERABLE at least once after not less than 4 months but within 6 months of initial criticality and in accordance with the inspection schedule of Table 4.7.5-1 thereafter, by a visual inspection of the snubber or functional operability test. Visual inspections of the l
snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid reservoirs, fluid connections, and linkage con-nections to the piping and anchors. Initiation of the Table 4.7.5-1 inspection schedule shall be made assuming the unit was previously at the 6 month inspection interval.
4.7.5.3 Each hydraulic snubber with seal material not fabricated from ethylene propylene or other materials demopstrated compatible with the operating environment shall be determined OPERABLE at least once per 31 days by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid reservoirs, fluid connections, and lir.kage connections to the piping and anchors.
BRUNSWICK - UNIT 1 3/4 7-9
TABLE 3.7.5-1 E
@ SAFETY RELATED llYDR\ULIC SNUBBERS
W IIIGli ESPECIALLY
' SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO ret 10VE Q (A or I) (Yes or No) (Yes or No) 1E21-2SS16 Core Spray O' A No No 2SS17 13' A No No 2SS18 14' A No No 15SS19 -3' A No No R 15SS20 -3' A No No
- 6SS21 13' A No No y 6SS22 A 14' A No No
,L 6SS22B 14' A No No
~
28SS23 -4' A No No '
2SS31 68' A No No 2SS31 66' A No No 6SS41 70' A No No 6SS42 69' A No No 25SS91 -6' A No No 25SS96 -6' A No No 40SS106 -12' A No No 40SS107 -12' A No No 39SS108 -12' A No No 39SS109 -12' A No No 3SS46 Drywe11 63 I No No 3SS47 63' I No No 3SS48 65' I No No 3SS49 66' I No No 7SS53 63' I No Mo 7SS54 63' I No No 7SSS3 63' I No No
TABLE 3.7.5-1 E
E SAFETY RELATED llYDRAULIC SNUBBERS
M
' lilGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEtt LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE O [4 or I) (Yes or No) [Yes or No)
~
7SS54 63' 1 No No 7SS55 65' I No No 7SS56 66' I No No u 1G31-ISS3 Reactor Water Cleanup Drywell 54' I No No 3 1B21-51SS103 Condensate Drain Drywell 29' I No No 51SS105 29' I No No Y 51SS106 26' I No No i3 50SS109 18' I No No 50SS111 31' I No No 51SS113 28' I No No 51SS115 23' I No No 51SS118 24' I No No IC11-16SSI Control Rod Drive Drywell 69' I No No 16SS6 63' I No No 16SS7 69' I No No 16SS8 70' I No No 16SS10 72' I No No 16SS11 72' I No No 16SS12 72' I No No IE41-4SS44 liigh Press. Coolant Inj. Drywell 40' I No No 4SS45 35' I No No 4SS47 40' I No No 4SS49 37' I No No 4SS50 50' I No No 4SS51 30' I No No 60SS9 Reactor Bldg. 4' A No No
TABLE 3.7.5-1
!s
] SAFETY RELATED IfYDRAULIC SNUBBERS *
=c E
' ilIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEtt LOCATION ~ ELEVATION ~ INACCESSIBLE ZONE ** TO ret!OVE M (A or I) (Yes or No) (Yes or No) 6SS27 -5 A No No 6SS28 l' A No No 6SS30 -l' A No No u 6SS32 -5' A No No
) 6SS33 1' A No No 6SS35 -l' A No No Y 6SS36 -5 A No No C, 6SS37 0' A No No 6SS38 l' A No No 6SS40 2' A No No 6SS42 -4' A No No 60SS52 41' A No No 6SS64 -1 A No No 61SS71 -4 A No No 61SS72 -1 A No No 61SS73 -2 A No No 61SS76 37' A No No 61SS77 37' A No No 44SS84 14' A No No 44SS86 14' A No No 44SS98 12' A No No 61SS99 22' A No No 61SS100 17' A No No 60SS101 42' A No No 60SS102 42' A No No 19SS103 -3' A No No
m 'lABLE 3.7.5-1
- o SAFETY RELATED IIYDRAULIC SNUBBERS
, IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT h
H NO. SYSTEtt LOCATION ELEVATION INACCESSIBLE ZONE ** TO ret 10VE (A or I) (Yes or Nd) [Yes or fio) 2SS104 12' A No No 2SS105 -17' A No No 2SS106 -12' A No No R 22SS178 -11' A No No e 20SS195 4' A No No y 20SS196 4' A No No
,', 22SS197 13' A No No e ISGT-8SS17 Standby Gas Treatm. Reactor Bldg. 69' A No No IB21-701SS164 Instrument Sensing Drywell 104' I No No 701SS167 104' I No No 70lSS169 100' I No No 701SS170 103' I No No 701SS171 99' I No No 701SS172 101' I No No 70lSS175 100' I No No 70lSS177 94' I No No 70lSS178 97' I No No 70lSS179 96' I No No 70lSS184 88' I No No IRCC-32SS30 RX Closed Cooling Wtr. Reactor Bldg. 55' A No No 32SS45 60' A No No 36SS78 54' A No No 37SS79 54' A No No 39SS80 59' A No No 38SS81 54' A No No 7SS112 57' A No No
TABLE 3.7.5-1 E
E SAFETY RELATED IIYDRAULIC SNUBBERS
HIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE O (A or I) (Yes or No) (Yes or No) 47SS167 59' A No No 47SS168 58' A No No 48SS169 60' A No No t' 50SS272 4' A ho No 60SS121 Drywell 17' I No No y 60SS122 16' I Nr No 65SS128 7' I No No 62SS129 9' I No No 71SS139 9' I No No 73SS145 5' I No No 19SS157 21' I No No 19SS160 29' I No No IPSN-A2SS30 Primary Steam Drywell 65' I No No A2SS31 64' I No No A3SS32 40' I No No A3SS33 35' I No No A3SS34 35' I No No A3SS35 41' I No No A5SS38 22' I No No B2SS40 63' I No No B2SS41 64' I No No B3SS42 40' I No No B3SS43 35' I No No B3SS44 40' I No No B3SS46 46' I No No B3SS47 35' I No No
m TABLE 3.7.5-1
- o E SAFETY RELATED llYDRAULIC SNUBBERS
7 IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE U (A or I) (Yes or No) [Yes or No) '
~
B3SS48 40' I No No B5SS50 18' I No No B5SSSI 22' I No No u C2SS54 63' I No No 3 C2SS55 64' I No No C3SS56 40' I No No Y C3SS57 35' I No No 5 C3SS58 40' I No No C3SS60 38' I No No C3SS61 35' I No No C3SS62 39' I No No C5SS64 18' I No No CSSS65 22' I No No D2SS68 65' I No No D2SS69 65' I No No D3SS70 40' I No No D3SS71 35' I No No D3SS72 35' I No No D3SS73 41' I No No D5SS76 22' I No No B3SS190 42' I No No C3SS272 42' I No No A3SS292 42' I No No IE51-4SS45 RCIC Drywell 31' I No No 3SS46 39' I No No 3SS47 39' I No No
TABLE 3.7.5-1 E
@ SAFETY RELATED IIYDRAULIC SNUBBERS
- IIIGII ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ --NO. SYSTEli LOCATION ELEVATION -INACCESSIBLE ZONE ** TO REMOVE N (A or I F (Yes or No) {Yes or No) 4SS66 39' I No No 4SS68 40' I No No 4SS69 40' I No No u 4SS70 39' I No No
) 4SS71 36' I No No 4SS72 31' I No No 7 4SS73 30' I No No G 42SS74 20' A No No 41SSSI Reactor Bldg. 40' A No No 42SS75 20' A No No '
42SS76 18' A No No 42SS77 5' A No No 42SS78 0' A No No 42SS79 4' A No No 42SS80 -13' A No No 42SS81 -16' A No No 42SS82 -9' A No No 40SS83 -9' A No No 40SS84 -9' A No No 40SS85 -12' A No No 40SS86 -9 A No No 40SS87 -15' A No No 40SS88 -13' A No No 41SS89 41' A No No 41SS95 41' A No No l
19SSil3 -17' A No No
, TABLE 3.7.5-1 SAFETY RELATED llYDRAULIC SNUBBERS
' IIIGil ESPECIAT.LY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE U (A or 1) (Yes or No) (Yes or No) 19SS114 -16' A No No 19SS129 0' A No No IB21-44SS129 Nuclear Steam Vent Drywell 104' I No No E
44SS131 93' I No No 44SS134 99' I No No u 44SS136 97' I No No
.'. 44SS137 96' I No No 44SS138 95' I No No 44SS141 87' I No No 44SS142 87' I No No 44SS143 87' I No No 44SS146 87' I No No 44SS147 82' I No No 44SS149 85' I No No 44SS150 83' I No No 47SS155 75' I No No 47SS156 78' J No No 47SS157 75 I No No IC41-9SS4 Standby Liquid Cont. Drywell 63' I No No 9SS5 47' I No No 9SS8 42' I No No 9SS10 38' I No No 9SS11 39' I No No 9SS12 69' I No No 9SS13 52' I No No 9SS26 Reactor Bldg. 72' A No No
TABLE 3.7.5-1 E
@ SAFETY RELATED IIYDRAULIC SNUBBERS
M ilIGli ESPECIALLY
' SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE y (A or I) (Yes or No) [Yes or No)
~
9SS27 72' A No No 6SS34 84 A No No IG41-ISS22 Fuel Pool Cooling Reactor Bldg. 12' A No !!o t' ISS24 38' A No No
- 1SS30 38' A No No y 12SS32 9' A No No
', 12SS33 9' A No No u) 15SS37 111' A No No 20SS76 108' A No No 19SS79 89' A No No 22SS85 108' A No No 12SS98 88' A No No 6SS111 88' A No No 7SS121 87 A No No SSS152 82 A No No IB32-SSA1 Reactor Recirculation Drywell 8' I No No 22B1 81' I No No SSA2 11' I No No SSB2 11' I No No SSA3 11' I No No SSB3 11' I No No SSA4 21' I No No SSB4 21' I No No SSA5 21' I No No SSB5 21' I No No SSA6 27' I No No
TABLE 3.7.5-1
- o h SAFETY RELATED IIYDRAULIC SNUBBERS
, HIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE U (A or I) (Yes or No) TYes or No)
SSB6 27' I No , No SSB9A 30' I No No g SSB9B 30' I No No 1 g SSA10 24' I No No SSAll 11' I No No u
SSB11 11' I No No to SSAl2A 30' I No No SSA12B 30' I No No SSB12A 30' I No No SSB12B 30' I No No IPS-3553 32' I No No 3554 32' I No No 3558 32' I No No 3561 32' I No No 3570 32' I No No 3613 32' I No No 3617 32' I No No IB21-2SS3 Reactor Feedwater Drywell 38' I No No 2SS4 56' I No No 3SS6 41' I No No 3SS9 39' I No No 3SSil 41' I No No 3SSI? 40' I No No 3SS13 61' I No No SSS17 38' I No No SSS18 56' I No No
TABLE 3.7.5-1 SAFETY RELATED llYDRAULIC SNUBBERS
IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEV/. TION INACCESSIBLE ZONE ** TO ret 10VE U (A or I) (Yes or No) (Yes or No) 6SS20 41' I No No 6SS23 39' I No No 6SS25 41' I No No t' 6SS26 40' I No No
- 6SS27 63' I No No y ISS227 34' I No No
,3 ISS228 38' I No No
~
ISS229 53' I No No 2SS230 62' I No No 2SS231 40' I No No 2SS232 36' I No No 3SS233 40' I No No 3SS234 48' I No No 3SS235 63' I No No 4SS236 34' I No No 4SS237 3f. ' I No No 5SS238 53' I No No SSS239 61' I No No 6SS240 41' I No No 6SS241 36' I No No 6SS242 39' I No No 6SS243 48' I No No 6SS244 61' I No No IEI1-90SS267 Residua 1 Ileat. Remova1 Drywel1 79' I No No 90SS268 86' I No No 90SS271 86' I No No
m TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS *
=
, 111G11 ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT h NG. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE H
(A or I) (Yes or No) (Yes or No) 90SS274 93' I No No 90SS275 93' I No No
, 90SS277 96' I No No y 90SS278 96' I No No 90SS280 101' I No No
~J 90SS281 93' I No No w 90SS282 101' I No No 90SS283 93' I No No 90SS284 101' I No No 90SS285 100' I No No ISS302 35' I No No ISS303 34' I No No ISS305 20' I No No ISS306 19' I No No 84SS308 34' I No No 84SS309 33' I No No 84SS311 35' I No No 84SS312 35' I No No 87SS314 34' I No No 87SS315 33' I No No 87SS317 35' I No No 87SS318 35' I No No 90SS388 79' I No No 90SS389 96' I No No 90SS390 96' I No No 90SS391 93' I No No
TABLL 3.7.5-1 E
@ SAFETY RELATED IIYDRAULIC SNUBBERS
- HIGil ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** T6 REMOVE y - (A or 1) (Yes or No) (Yes or Nn)
~
90SS392 99' I No No 1E11-17SS3 N etor Bldg. 3' A No No 17SS4 -l' A No No t' 46SS7 12' A No No 46SS9 12' A No No y 56SS13 5' A No No
,' 3 56SS15 4' A No No 20SS19 -3' A No No 95SS20 -3' A No No 95SS22 9' A No No 95SS23 9' A No No 20SS28 -3' A No No 58SS32 3' A No No 58SS33 -4' A No No 58SS35 8' A No No 58SS36 8' A No No 18SS40 8' A No No 18SS47 12' A No No 18SS48 13' A No No 68SS59 15' A No No 1E11-21SS63 Reactor Bldg. 8' A No No 21SS70 13' A No No 21SS71 10' A No No 37SS95 -3' A No No 61SS110 6' A No No 116SS143 -11' A No No
, TABLE 3.7.5-1 SAFETY RELATED HYDRAULIC SNUBBERS
' HIGil ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEtt LOCATION ELEVATION INACCESSIBLE ZONE ** TO ret 10VE M (A or 1) (Yes or No) (Yes or No) 113SS157 -11' A No No 37SS184 9' A No No 53SS192 78' A No No R*
53SS195 14' A No No 53SS197 14' A No No u 53SS200 14' A No No h
50SS201 14' A No No 89SS208 5' A No No 46SS216 28' A No No 46SS217 31' A No No 46SS218 30' A No No 47SS223 33' A No No 47SS224 36' A No No 47SS225 36' A No No 47SS227 39' A No No 47SS228 39' A No No 95SS233 20' A No No 95SS234 24' A No No 95SS235 31' A No No 131SS255 42' A No No 131SS257 22' A No No 132SS263 30' A No No 132SS264 31' A No No 21SS296 39' A No No 21SS297 39' A No No 47SS323 42' A No No
TABLE 3.7.5-1
- o
@ SAFETY RELATED HYDRAULIC SNUBBERS
- IIIGli ESPECIALLY SNUBBER , "CESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEr! LOCATION ELEVATION INACCESSIBLE ZONE ** TO REff0VE M (A or I) (Yes or No) (Yes or No) 47SS326 42' A No No 47SS328 42' A No No 49SS330 42' A No No R
49SS331 42' A No No 49SS333 42' A No No y 49SS334 43' A No No L
49SS336 40' A No No 128SS355 42' A No No 49SS359 42' A No No 127SS376 59' A No No 128SS387 43' A No No 2SS396 5 A No No 2SS397 3 A No No i 5SS398 -14' A No No 2SS399 -3' A No No SSS400 -3' A No No 4SS401 -12' A No No SSS402 -12' A No No 3SS403 -11' A No No 6SS404 -12' A No No 8SS405 -14' A No No 6SS406 -14' A No No 8SS407 -15' A No No 12SS408 -14' A No No 16SS409 -9' A No No 113SS410 -9' A No No
, TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS
IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION ~ INACCESSIBLE ZONE ** TO REll0VE M (A or 1) (Yes or No) (Yes or No) 9SS411 -14' A No No 109SS412 -14' A No No 2SS413 0' A No No U
132SS414 43' A No No 20SS415 -4 A No No u 20SS416 -4' A No No E 95SS417 0' A No No 95SS418 -4' A No No 45SS422 -2' A No No 60SS423 -4: A No No 60SS425 -2' A No No 127SS426 43' A No No 128SS427 21' A No No 128SS428 28' A No No 128SS429 39' A No No 128SS430 31' A No No ,
128SS431 23' A No No 127SS433 14' A No No 127SS434 37' A No No 127SS435 15' A No No 60SS437 12' A No No 60SS438 12' A No No 60SS440 13' A No No 65SS441 3' A No No 65SS442 3' A No No 60SS443 11' A No No
TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS
- IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATIOU ELEVATION INACCESSIBLE ZONE ** TO REMOVE M (A or I) (Yes or No) TYes or No)
~
73SS444 21' A No No 21SS445 5' A No No 83SS446 10' A No No t' 18SS447 5' A No No
- 68SS448 13' A No No y 75SS449 7' A No No 4 61SS450 2' A No No
" 60SS451 13' A No No 60SS452 13' A No No 60SS453 10' A No No 60SS454 10' A No No 89SS459 11' A No No 89SS460 10' A No No 89SS461 6' A No No 53SS462 15' A No No 53SS463 14' A No No 53SS464 14' A No No 53SS465 14' A No No 53SS466 14' A No No 50SS467 14' A No No 50SS468 17' A No No 18SS469 53' A No No 18SS470 43' A No No 89SS480 67' A No No 89SS487 67' A No No 89SS489 67' A No No
g TABLE 3.7.5-1 SAFETY RELATED HYDRAULIC SNUBBERS
M IIIGH ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTE!! LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE U (A or I) (Yes or No) [Yes or No)
~
89SS491 67' A No No 91SS499 69' A No No
, 91SS500 57' A No No y 56SS504 14' A No No 56SS505 7' A No No N 56SS506 3' A No No O
- 56SS507 3' A No No 56SS508 4' A No No 46SS509 8' A No No 46SS510 11' A No No 46SS511 10' A No No 46SS512 -l' A No No 58SS514 14' A No No 49SS515 37' A No No 49SS516 37' A No No 56SS517 -5' A No No SISS546 32' A No No 5ISS547 28' A No No 115SS549 31' A No No 54SS551 31' A No No 54SS552 28' A No No 98SS554 32' A No No 58SS563 7' A No No 58SS565 13' A No No 58SS566 6' A No No 107SS573 15' A No No
, TABLE 3.7.5-1 SAFETY RELATED llVDRAULIC SNUBBERS
- IIIGI! ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE O (A or I) (Yes or No) (Yes or No)
~
69SS574 6' A No No 91SS575 53' A No No 68SS577 8' A No No R
53SS596 14' A No No 50SS597 26' A No No u ISW-133SS22 Service Water Reactor Bldg. -6' A No No 0
110SS35 -5' A No No 174SS70 42' A No No 173SS72 14' '-
No No 142SS74 40' No No 142SS75 40' n No No 140SS80 40' A No No 142SS82 70' A Nc No 140SS86 45' A No No 153SS102 44' A No No 153SS109 44' A No No 173SS110 48' A No No 173SS114 70' A No No 153SS115 44' A No No 103SS121 38' A No No 103SS123 51' A No No 103SS126 60' A No No 103SS127 57' A No No 106SS131 60' A No No 100SS145 59' A No No 100SS149 60' A No No
, TABLE 3.7.5-1 E SAFETY RELATED llYDRAULIC SNUBBERS
' llIG11 ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE M (A or I) (Yes or No) TYes or No; 106SS151 59 A No No 106SS156 60' A No No 142SS164 8' A No No R
142SS165 8' A No No 140SS167 42' A No No u 142SS168 58' A No No 0 142SS169 71' A No No 128SS170 55' A No No 140SS171 58' A No No 173SS175 30' A No No 133SS177 -5' A No No 100SS193 62' A No No 106SS211 60' A No No 106SS212 60' A No No 106SS213 59' A No No 106SS214 60 A No No IB21-19SS192 Steam Relief Discharge Drywell 43' I No No 19SS193 44' I No No 19SS194 37' I No No 19SS195 37' I No No 19SS196 32' I No No 19SS198 18' I ho No 19SS199 18' I No No 26SS201 42' I No No 26SS203 36' I No No 26SS204 36' I No No
, TABLE 3.7.5-1
- o E SAFETY RELATED llYDRAULIC SNU13BERS*
2 M
' lilGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESS!"LE ZONE ** TO REMOVE E (A or I) (Yes or No) (Yes or No) 26SS206 18' I No No 26SS307 18' I No No 26SS208 11' I No No U
18SS211 42' I No No 18SS212 37' I No No
-a 18SS213 37' I No No 0
18SS215 18' I No No 18SS216 17' I No No 18SS218 5' I No No 11SS220 38' I No No 11SS221 37' I No No 11SS222 36' I No No 11SS223 34' I No No 11SS224 34' I No No 33SS245 43' I No No 33SS246 43' I No No 33SS248 45' I No No 33SS249 36' I No No 33SS250 36' I No No 33SS251 32' I No No 20SS256 44' I No No 20SS257 37' I No No 20SS258 36' I No No 1B21-20SS260 18' I No No 20SS261 20' I No No 20SS262 15' I No No
o
, TABLE 3.7.5-1
- o E SAFETY RELATED INDRAULIC SNUBBERS
' IIIGII ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E (A or I) (Yes or No) (Yes or No) 27SS264 10' I No No 27SS266 17' I No No 27SS267 18' I No No R
27SS269 36' I No No 27SS270 44' I No No
-a 58SS275 18' I No No O 58SS276 30' I No No 58SS277 31' I No No 58SS279 36' I No No 58SS280 37' I No No 58SS281 38' I No No 12SS286 39' I No No 12SS287 39' I No No 12SS288 44' I No No 12SS289 39' I No No 12SS290 43' I No No 34SS296 35' I No No 34SS297 35' I No No 34SS298 44' I No No 34SS299 59' I No No 34SS300 44' I No No 26SS302 11' I No No 26SS303 5' I No No 58SS304 10' I No No 58SS305 5' I No No 58SS306 15' I No No
m TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS
, llIGil ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT h NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO RE. MOVE
] (A or I) (Yes or No) {Yes or No) 58SS307 16' I No No 12SS308 28' I No No u 12SS309 29' I No No 3 12SS310 17' I No No 12SS311 11' I No No
? 12SS312 11' I No No
$ 11SS313 16' I No No 11SS314 11' I No No 1ISS315 7' I No No 19SS316 11' I No No 19SS317 17' I No No 18SS318 11' I No No 20SS319 10' I No No 59SS320 11' I No No 59SS325 34' I No No 59SS326 35' I No No 59SS327 36' I No No 59SS329 38' I No No 59SS330 44' I No 'io 33SS332 26' I No No 33SS333 7' I No No 33SS334 11' I No Na 33SS335 29' I No No 34SS336 27' I No No 34SS337 18' I No No 34SS338 18' I No No
, TABLE 3.7.5-1
- o E SAFETY RELATED IIYDRAULIC SNUBBERS
llIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE **
TO REMOVE CI (A or I) (Yes r.,r }To) (Yes or No) 34SS339 11' I No No 34SS340 7' I No No to u
PLAf1T SYSTEMS 3/4./.5 HYDRAULIC SMUBBERS LIMITING CONDITION FOR OPERATION 3./.5 All hydrc .lic snubbers shown in Table 3.7.5-1 shall be OPERABLE.
APPLICABILITY: C0fiDITIONS 1, 2 and 3 ACTION:
With one or more hydraulic snubbers auperable, restore the inoperable snub br(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the tollowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.5.1 Hydraulic snubbers shown in Table 3.7.5-1 shall be demonstrated OPERABLE by the performance of the following augmented inservice inspec-tion program and the requirements of Specification 4.0.5.
4.7.5.2 Each hydraulic snubber with seal material fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment and approved as such by the NRC, shall be deter-mined OPERABLE at least once after not less than 4 months but within 6 months of initial criticality and in accordance with the inspection schedule of Table 4.7.5-1 thereaf ter, by a visual inspection of the snubber or functional operability test. Visual inspections of the l
snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid reservoirs, fluid connections, and linkage con-nections to the piping and anchors. Initiation of the Table 4.7.5-1 inspection schedule shall be made assuming the unit was previously at the 6 month inspection interval.
4.7.5.3 Lach hydraulic snubber with seal material not tabricated from ethylene propylene or other materials demonstrated compatible with the operating environment shall be determined OPERABLE at least once per 31 days by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid reservoirs, fluid connections, and linkage connections to the piping and anchors.
BRUNSWICK - UNIT 2 3/47-9
9 TABLE 3.7.5-1 E
E SAFETY RELATED !!YDRAULIC SNUBBERS
' IIIGil ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E (A or 1) (Yes or No) [Yes or No) w 2E21-2SS32 Core Spray Reactor Bldg. 66' A No No 26SS91 -6' A No No 2SS16 0' A No No Y
2SS17 13' A No No 15SS19 -3' A No No
~4 15SS20 -3' A No No E
6SS21 13' A No No 6SS22A 14' A No No 6SS22H 14' A No No 28SS23 -4' A No No 25SS96 -6' A No No 40SS106 -12' A No No 40SS107 -12' A No No 39SS100 -12' A No No 39SS109 -12' A No No 2SS31 68' A No No 6SS41 70' A No No 6SS42 69' A No No 2SS18 14' A No No 2E21-3SS46 Drywell 63' I No No 3SS47 63' I No No 3SS48 65' I No No 3SS49 66' I No No 7SS53 63' I No No 7SS54 63' I No No 7SS55 65' I No No
m TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS
, IIIGII ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT h
H NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE n
(A or 1) (Yes or No) TYes or No) 7SS56 66' I No No 2G31-1SS3 Reactor Water Cleanup Drywell 54' I No No u 2B21-51SS103 Condensate Drain Sys. Drywell 29' I No No ,
3 51SS105 26' I No No 51SS106 18' I No No
? 51SS109 31' I No No C 51SS111 28' I No No 51SS113 23' I No No 51SS115 24' I No No 51SS118 24' I No No 2C12-16SSI Control Rod Drive Drywell 69' I No No 16SS6 68' I No No 16SS7 69' I No No 16SS8 70' I No No 16SS10 72' I No No 16SS11 72' I No No 16SS12 72' I No No 2E41-4SS44 Iligh Press. Coolant Inj. Drywell 40' I No No 4SS45 35' I No No 4SS47 40' I No No 4SS49 37' I No No 4SS50 40' I No No 4SS51 30' I No No 2E41-2SS5 Reactor Bldg. -7' A No No 61SS73 -2' A No No 60SS9 4' A No No
m TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS
, IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT h NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE H
(A or I) (Yes or No) (Yes or No) 20SS15 -5' A No No 44SS84 14' A No No 44SS86 14' A No No U 44SS98 12' A No No 19SS103 -3' A No No u 2SS104 12' A No No O
" 2SS105 -17' A No No 2SS106 -12' A No No 60SS52 41' A No No 21SS76 37' A No No 21SS17 37' A No No 61SS99 22' A No No 61SS100 17' A No No 60SS101 42' A No No 60SS102 42' A No No 22SS178 -11' A No No 6SS27 -5' A No No 6SS28 l' A No No 6SS30 -l' A No No 6SS32 -5' A No No 6SS33 l' A No No 6SS35 -l' A No No 6SS36 -5' A No No 6SS37 0 A No No 6SS38 l' A No No 6SS40 2' A No No
m TABLE 3.7.5-1
- o E SAFETY RELATED IIYDRAULIC SNUBBERS
' lilGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO ret!0VE O (A or I) (Yes or No) (Yes or No) w 6SS42 -4' A No No 6SS64 -l' A No No 61SS71 -4' A No No U
61SS72 -1' A No No 2-SGT85S17 Standby Gas Treatment Reactor Bldg. 69' A No No u 2B21-70lSS164 Instrument Sensing Drywell 104' I No No O
70lSS167 104' I No No 701SS169 100' I No No 702SS170 103' I No No 701SS171 99' I No No 70lSS172 101' I No No 701SS175 100' I No No 761SSl?7 94' I No No 701SS178 97' I No No 701SS179 96' I No No 701SS184 88' I No No 2RCC-58SS11 Rx Bldg. Clsd. Cool. Wtr. Reactor Bldg. 39' A No No 50SS33 48' A No No 50SS34 48' A No No 10SS56 48' A No No 17SS74 38' A No No 17SS75 48' A No No 17SS76 39' A No No 32SS30 55' A No No 32SS52 64' A No No 36SS78 54' A No No
, TABLE 3.7.5-1 E SAFETY RELATED IIYDRAULIC SNUBBERS *
'd M
' 1:lGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE M (A or 1) (Yes or No) [Yes or No) w 37SS79 54' A No No 39SS80 59' A No No 38SS81 54' A No No R
34SS82 57' A No No 35SS83 57' A No No y 6SS107 60' A No No
,'. 7SS112 57' A No No 47SS168 58' A No No 48SS169 60' A No No 32SS45 60' A No No SISS58 88' A No No 47SS167 59' A No No 2RCC-60SS121 Drywell 17' I No No '
60SS122 16' I No No 65SS128 7' I No No 65SS129 7' I No No 71SS139 9' I No No 71SS139 9' I No No 73SS145 5' I No No 19SS157 21' I No No 19SS160 29' I No No 2PSN-A2SS30 Primary Steam Drywell 65' I No No A2SS31 64' I No No A3SS32 40' I No No A3SS33 35' I No No A3SS34 35' I No No
TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS
- llIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E! NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE 4 (A or i) (Yes or No) (Yes or No) w A3SS38 22' I No No B2SS40 63' I No No B2SS41 64' I No No if B3SS43
. 35' I No No B3SS44 40' I No No si B3SS4' 38' I No No O '
B3SS47 35' I No No +
B3SS48 40' I No No B5SS50 18' 1 No No B5SS51 22' I No No C2SS54 63' I No No C2SS55 64' I No No C3SS56 40' I No No C3SS57 35' I No No C3SS58 40' I No No C3SS60 38' I No No C3SS61 35' I No No C3SS62 39' I No No CSSS64 18' I No No CSSS65 22' I No No D2SS68 65' I No No D2SS69 65' I No No D3SS70 40' I No No D3SS71 35' I No No D3SS72 35' I No No D3SS73 41' I No No
g TABLE 3.7.5-1
- n E SAFETY RELATEI) IIYDRAULIC SNUBBERS
' IllGil ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONF# TO REMOVE (A or I) (Yes or No) TYes or No)
D5SS76 22' I No No A3SS35 4i' I No No B3SS42 40' I No No R
2E51-4SS45 RCIC Drywell 31' I No No 3SS46 39' I No No
-4 3SS47 39' I No No
,. 4SS66 39' I No No 4SS100 40' 1 No No 4SS101 40' I No No 4SS102 39' I No No 4SS103 36' I No No 4SS104 31' I No No 4SS105 30' I No No 2E51-42SS76 Reactor Bldg. 18' A No No 42SS77 5' A No No 42SS79 4' A No No 42SS81 A No No 42SS82 -9' A No No 40SS83 -9' A No No 40SS84 -9' A No No 40SS85 -12' A No No i 40SS86 -15' A No No 40SS87 -15' A No No l 40SS88 -13' A No No 41SS51 40' A No No 42SS74 20' A No No
TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS
IIIGH ESPECIALLY SNUBBFR ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE O (A or I) (Yes or No) (Yes or No) w 42SS75 20' A No No 41SS89 41' A No No 419c45 41' A No No U
" 19SS113 -17' A No No 19SS114 -16' A No No u 16SS91 -6' A No No 1
- 17SS94 -6' A No No 42SS78 0 A No No 49SS129 0 A No No 2B21-44SS129 Nuclear Stec:n v'ent Dry 5 ell 104' I No No 44SS131 93' I No No 44SS134 99' I No No 44SS136 97' I No No 44SS137 96' I No No 44SS138 95' I No No 44SS141 87' I No No 44SS142 87' I No No 44SS143 87' I No No 44SS146 87' I No No 44SS147 82' I No No 44SS149 85' I No No 44SS150 83' I No No 44SS155 75' I No No 44SS156 78' I No No 44SS157 75' 1 No No 2C41-9SS4 Standby Liquid Control Drywel l 63' 1 No No
TABLE 3.7.5-1 E
@ SAFETY RELATED llYDRAULIC SNUBBERS
' IIIG!! ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE s (A or I) (Yes or No) [Yes or No) w 9SS5 47' I No No 9SS8 42' I No No 9SS10 38' I No No R
9SS11 39' I No No 9SS12 69' I No No y 9SS13 52' I No No
, 2C41-9SS26 Reactor Bldg. 72' A No No
- 9SS27 72' A No No 9SS34 84' A No No 2G41-ISS22 Fuel Pool Cooling Reactor Bldg. 12' A No No 12SS32 9' A No No 12SS33 9' A No No ISS24 38' A No No ISS30 38' A No No 15SS37 111' A No No 11SS54 88' A No No 10SS67 89' A No No 20SS76 108' A No No 11SS79 89' A No No 22SS85 108' A No No 12SS98 88 A No No 6SS111 88 A No No 7SS121 87' A No No SSS152 82' A No No SSS159 84' A No No 2B32-SSAI Reactor Recirculation Drywell 8' I No No
TABLE 3.7.5-!
E
@ SAFETY RELATED llYDRAULIC SNUBBERS
M lilGli ESPECIALLY
' SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE Q (A or 1) (Yes or No) [Yes or No) w SSBl 8' I No No SSA2 11' I No No SSB2 11' I No No t'* SSA3 11' I No No SSB3 11' I No No y SSA4 21' I No No L SSB4 21' I No No SSA5 21' I No No SSA6 27' I No No SSB6 27' I No No SSB9A 30' I No No SSB98 30' I No No SSA10 24' I No No SSAll 11' I No No SSB11 4' I No No SSA12A 30' I No No SSA12B 30' I No No SSB12A 30' I No No SSB12D 30' I No No 2-PS-3705 Recircu. Sample Lines 32' I No No 3706 32' I No No 3707 32' I No No 3708 32' I No No 3709 32' I No No 3110 32' I No No 2B21-2SS3 Reactor Feetlwater Drywell 38' I No No
, TABLE 3.7.5-1 E SAFETY RELATED IIYDRAULIC SNUBBERS
' IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E (A or I) (Yes or No) Wes or No) w 2SS4 56' I No No 3SS6 41' I No No 3SS9 39' I No No R
3SS11 41' I No No 3SS12 40' I No No
-a 3SS13 61' I No No O SSS17 38' I No No SSS18 56' I No No j 2821-6SS20 Reactor Feedwater Drywell 41' I No No A
6SS23 39' I No No 6SS25 41' I No No 6SS26 40' I No No 6SS27 63' I No No 6SS227 34' I No No 6SS228 38' I No No 2SS229 53' I No do 2SS230 62' I No No 3SS231 40' I No No 3SS232 36' 1 No No 3SS233 40' I No No 3SS234 48' I No No 3SS235 63' I No No 4SS236 34' I No No 4SS237 38' I No No SSS238 53' I No No SSS239 61' I No No
TABLE 3.7.5-1 E
@ SAFETY RELATED IIYDRAULIC SNUBBERS
M IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE M (A or I) (Yes or No) (Yes or No) w 6SS240 41' I No No 6SS241 36' I No No 6SS242 39' I No No 10 6SS243 48' I No No 6SS244 61' I No No
-i 2 Ell-90SS267 Residual liest Removal 79' I No No O 90SS268 86' I No No 90SS271 86' I No No 90SS274 93' I No No 90SS275 93' I No No 90SS277 96' I No No 90SS278 96' I No No 90SS280 101' I No No 90SS281 93' I No No 90SS232 101' I No No 90SS283 93' I No No 90SS284 101' I No No 90SS285 100' I No No ISS302 35' I No No ISS303 34' I No No ISS305 20' 1 No No ISS306 19' I No No 84SS30h 34' I No No 84SS309 33' I No No 84SS311 35' I No No 84SS312 35', I No No
m TABLE 3.7.5-1
- o E SAFETY RELATED IIYDRAULIC SNUBBERS
' IIIGH ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E (A or 1) (Yes or No) (Yes or No) ra 87SS314 34' I No No 87SS315 33' I No No 87SS317 35' I No No Y
87SS318 35' I No No 90SS388 79' I No No u 90SS389 96' I No Na r'o 90SS390 96' I No No 90SS391 93' I No No 90SS392 99 I No No 2E11-121SS255 Reactor Bldg. 42' A No No 131SS257 22' A No No 132SS263 30' A No No 132SS264 31' A No No 128SS355 42' A No No 128SS387 43' A No No 132SS414 43' A No No 237SS426 43' A No No 128SS427 21' A No No 128SS428 28' A No No 128SS429 39' A No No 128SS430 31' A No No 128SS431 23' A No No 127SS376 59' A No No 107SS573 15' A No No 127SS433 14' A No No 127SS435 15' A No No
TABLE 3.7,5-1
!E
@ SAFETY RELATED llYDRAULIC SNUBBERS
F' IIIGIl ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT g NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE e (A or I) (Yes or No) {Yes or No) w 17SS3 -3' A No No 17SS4 -l' A No No 20SS19 -3' A No No Y
95SS20 -3' A No No 95SS22 9' A No No u 95SS23 9' A No No 0*
20SS28 -3' A No No 37SS95 -3' A No No 35SS360 -8' A No No 35SS361 -16' A No No 2SS397 -3' A No No SSS398 -4' A No No 2SS399 -3' A No No SSS400 -3' A No No 4SS401 -12' A No No SSS402 -12' A No No 3SS403 -11' A No No 6SS404 -12' A No No 8SS405 -14' A No No 6SS406 -14' A No No 8SS407 -15' A No No 12SS408 -14' A No No 9SS411 -14' A No No 109SS412 -14' A No No 20SS415 -4' A No No 20SS416 -4' A No No
TABLE 3.7.5-1 SAFETY RELATED llVDRAULIC SNUBBERS
- sn IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEfl LOCATION ELEVATION INACCESSIBLE ZONE ** TO REr!OVE y (A or I) (Yes or No) (Yes or No) w 95SS417 0' A No No 95SS418 -4' A No No 45SS422 -2' A No No ld 56SS517 -5' A No No 91SS575 53' A No No y 92SS500 57' A No No 4 91SS*99 60' A No No 89SS491 6/' A No No l 89SS489 67' A No No 89SS487 67' A No No j 89SS480 67' A No No 18SS469 53' A No No 46SS216 28' A No No 46SS217 31' A No No 46SS218 30' A No No 47SS223 33' A No No 47SS224 36' A No No 47SS225 36' A No No 47SS227 39' A No No 47SS228 39' A No No 95SS233 20' A No No 95SS234 24' A No No 95SS235 31' A No No 21SS296 39' A No No 21SS297 39' A No No 47SS326 42' A No No
, TABLE 3.7.5-1 E SAFETY RELATED IIYDRAULIC SNUBBERS
' llIGil ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E (A or I) (Yes or No) (Yes or No) w 47SS328 42' A No No 49SS330 42' A No No 49SS331 42' A No No M
49SS333 42' A No No 49SS334 43' A No No u 49SS336 40' A No No r' >
49SS359 42' A No No 17SS470 <e 3 ' A No No 58SS514 14' A No No 49SS515 37' A No No 49SS516 3/' A No No 50SS597 20' A No No 46SS7 12' A No No 46SS9 12' A No No 56SS13 5' A No No 56SS15 4' A No No 58SE32 3' A No No 58SS33 -4' A No No 58SS35 8' A No No 58SS36 8' A No No 18SS40 8' A No No 18SS48 13' A No No 68SS59 15' A No No 21SS63 8' A No No 21SS70 13' A No No 21SS71 10' A No No .
, TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERS 4 sa
' ll1Gli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE U (A or 1) (I5 or No) (Yes or No) w 61SS110 6' A No No 53SS192 18' A No No 53SS195 14' A No No Y"
53SS197 14' A No No 53SS200 14' A No No u 50SS201 14' A No No O 89SS208 5' A No No 60SS438 12' A No No 60SS440 13' A No No 65SS441 3' A No No 65SS442 3' A No No 60SS443 11' A No No 73SS444 2' A No No 21SS445 5' A No No 68SS448 13' A No No 75SS449 2' A hv No ,
61SS450 7' A No No 60SS451 13' A No No I 60SS452 13' A No No 60SS453 10' A No No 60SS454 10' A No No 89SS459 11' A No No 89SS460 10' A No No 89SS461 6' A No No 53SS462 15' A No No 53SS463 14' A No No
TABLE 3.7.5-1 N
@ SAFETY RELATED llYDRAULIC SNUBBERS
M
!!IGli ESPECIALLY
' SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM LOCATION INACCESSIBLE ZONE ** TO REMOVE ELEVATION ~
tj (A or 1) ( es or No) TYes or No) ,
w 53SS464 14' A No No 53SS465 14' A No No 53SS466 14' A No No R
53Sc.67 14' A No No 50SS468 17' A No No
-2 56SS504 14' A No No h 56SS505 7' A No No 56SS506 3' A No No 56sS507 3' A No No 56SS508 4' A No No 46SS509 8' A No No 46SS510 11' A No No 46SS511 10' A No No 46SS512 -l' A No No 68SS577 8' A No No 53SS596 14 A No No 116SS143 -11' A No No 113SS157 -11' A No No 37SS184 9' A No No 2SS396 5' A No No 116SS409 -9' A No No 113SS410 17' A No No 2SS413 0' A No No I 60SS423 -4' A No No 60SS425 -2' A No No 47SS323 42' A No No
9
, TABLE 3.7.5-1 SAFETY RELATED IIYDRAULIC SNUBBERSA s
S
' IIIGil ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
$ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E (A or I) (Yes or No) (Yes or No) w 71SS393 9' A No No 127SS434 37' A No No 60SS437 13' A No No R
83SS446 10' A No No 18SS447 5' A No No y 51SS546 32' A No No a
51SS547 28' A No No 115SS549 31' A No No 18SS47 12' A No No 71SS176 9' A No No 54SS551 31' A No No 54SS552 28' A No No 98SS554 32' A No No 58SS563 7' A No No 58SS565 13' A No No 58SS566 6' A No No 69SS574 6' A No No 2SW-133SS22 Service Water Reactor Bldg. -6' A No No 110SS35 -5' A No No 173SS72 14' A No No 142SS164 8' A No No 142SS165 8' A No No 133SS176 14' A No No 133SS177 -5' A No No 142SS74 40' A No No 142SS75 40' A No No
s I
TABLE 3.7.5-1 E
@ SAFETY RELATED !!YDRAULIC SNUllllERS*
2 M
W llIGli ESPECIALLY
' SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEN LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE y (A or I) (Yes or No) (Yes or No) w 140SS80 40' A No No 140SS86 45' A No No 153SS102 44' A No No R
153SS109 44' A No No 173SS110 48' A No No u 153SS115 44' A No No a 103SS121 38' A No No 140SS167 42' A No No 173SS175 30' A No No 142SS82 70' A No No 173SS114 70' A No No 103SS123 51' A No No 103SS126 60' A No No 103SS127 57' A No No 106SS131 60' A No No 100SS145 59' A No No 100SS149 60' A No No 106SS151 59' A No No 174SS70 42' A No No 106SS156 60' A No No 142SS168 58' A No No 142SS169 71' A No No 138SS170 55' A No No 140SS171 58' A No No 100SS193 62' A No No 106SS211 60' A No No
F
, TABLE 3.7.5-1
- o E SAFETY RELATED llYDRAULIC SNUBBERS
' HIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
$ NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E (A or I) (Yes or No) (Yes or No) to 106SS212 60' A No No 106SS213 59' A No No 106SS214 60' A No No R
103SS117 41' A No No 142SSi63 0 A No No y 175SS166 42' A No No a
~
139SS172 58' A No No 109SS173 14' A No No 174SS174 43' A No No 139SS209 56' A No No 138SS210 56' A No No 2B21-19SS190 Steam Relief Discharge Drywell 42' I No No 19SS192 43' I No No 19SS193 44' I No No 19SS194 37' I No No 19SS195 37' I No No 19SS196 32' I No No 19SS198 18' I No No 19SS199 18' I No No 26SS201 42' I No No 26SS203 36 I No No 26SS204 36' 1 No No 26SS206 18' I No No 26SS207 18' I No No 26SS208 11' I No No 18SS211 42' I No No
4 9
, TABLE 3.7.5-1 w
E SAFETY RELATED IlYDRAULIC SNUBBERS
' IIIGH ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT
@ NO. SYSTEM -
LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E (A or I) (Yes or No) (Yes or No) w 18SS212 37' I No No 18SS213 37' I No No 18SS215 18' I No No Y
" 18SS216 17' I No No 18SS218 5' I No No u 11SS220 38' I No No 0
11SS221 37' I No No 11SS222 36' I No No 11SS223 34' I No No 11SS224 34' I No No 33SS245 43' I No No 33SS246 43' I No No 33SS248 45' I No No 33SS249 36' I No No 33SS250 36' I No No 33SS251 32' I No No 33SS256 44' I No No 20SS257 37' I No No 20SS258 36' I No Nc 20SS260 18' I No No 20SS261 20' I No No 20SS262 15' I No No 27SS264 10' I No No 27SS266 17' I No No 27SS267 18' I No No 27SS269 36' I No No
e L
w TABLE 3.7.5-1
- n E SAFETY RELATED llYDRAULIC SNUBBERS
7:
, IIIGli ESPECIALLY SNUBBER ACCESSIBLE OR RADIATION DIFFICULT E NO. SYSTEM LOCATION ELEVATION INACCESSIBLE ZONE ** TO REMOVE E
ra (A or I) (Yes or No) (Yes or No) 27SS270 44' I No No 27SS272 42' I No No 58SS275 18' '
No No R
58SS276 30' I No No 58SS277 31' I No No
~4 58SS279 36' I No No d>
" 58SS280 37' I No No 58SS281 38' I No No 12SS286 39' I No No 12SS287 39' I No No 12S.'3288 44' I No No 12SS289 39' I No No 12SS290 43' I No No 12SS292 42' I No No 34SS296 35' I No No 34SS297 35' I No No 34SS298 44' I No No 34SS299 39' I No No 34SS300 44' I No No 26SS302 11' I No No 26SS303 5' I No No 58SS304 10' I No No 58SS305 5' I No No 58SS306 15' I No No
'8SS307 16' I No No 12SS308 28' I No No