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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] |
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n. ,
. . CD&L Carolina Power & t.lght Company SERIAL: NLS-86-448 REF: 10CFR50, Appendix R DEC 31 1986 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 'm-124/ LICENSE NOS. DPR-71 & DPR-62 FIRE BARRIER TRATION SEALS Gentlemen:
Carolina Power & Light Company (CP&L) hereby provides additional information regarding fire barrier penetration seals as requested in your letter dated November 18,1986. This request stems from the meeting with your staff on October 15,1986, where CP&L presented an evaluation of Fire Seal Selection Acceptance Criteria for Brunswick Steam Electric Plant fire barrier penetration seals.
This selection criteria is used for the various types of penetration seals in use at Brunswick Steam Electric Plant. Seal types include cellular concrete, insulating cement (both previously accepted via Safety Evaluation Report), silicon-based sealants, fire-rated link seals, fire-rated dampers, and grout.
As discussed in this meeting and recommended by your staff we are transmitting our evaluation as Enclosure 1 for your review. Enclosure 2 prov,i des the additional information regarding Nelson CLK requested in your Meeting Summary letter dated November 18,1986, and includes (1) a summary of the test report,(2) a discussion of the equivalence between the tested seal configuration and the installed configuration at the Brunswick facility and (3) sketches of the as-tested and as-installed seal configuration.
This transmittal documents the information which was presented in the subject meeting.
your staff generally agreed Based that CP&Lon should the information provided at not stop installation of the subject the seals meeting,he while t staff performed its review of the enclosed documentation. This was because the information presented by CP&L did not appear to be inconsistent with that accepted by the staff for penetration seats at other facilities, it is CP&L's belief that the proposed seal acce alternative to the guidance of BTP ASB and 9.5-1,ptance the Company criteria provides believes that youran acceptable review will come to the same conclusion.
Should you have any questions with regard to this request, please contact Mr. M. Ronald Oates at (919) 836-606J.
Yours very truly, R'*t88?i 8tb88bu PDR 4Vp S. R. Zimm rman Manager PS/bmc (5082PSA) Nuclear Licensing Section Enclosures cc: Mr. W. H. Ruland (NRC-BNP)
Dr. J. Nelson Grace (NRC-RII) f Mr. E. Sylvester (NRC) 0 411 Fayettevene street e P. o Dox 1551
pro.wpw a.mugsgm emu 2m.- 1 .
9 9
Enclosure I i
f i
I l
l I
(5082PSA/kts)
BRUNSWICK NUCLEAR PROJECT EVALUATION OF FIRE SEAL SELECTION ACCEPTANCE CRITERIA (5082PSA/kts)
Page 1-I. INTRODUCTION:
The purpose of this document is to establish Carolina Power A Light .
Company's (CPAL's) Licensing Basis for Fire Seal Selection Acceptance Criteria at the Brunswick Steam Electric Plant (BSEP). - l BSEP has been utilizing an NRC accepted seal design that meets the criteria of Appendix A to BTP APCSB 9.5-1. This design has been in use
>> since'1979. While this design meets Appendix A criteria, difficulties have been encountered with installation and maintenance. Consequently, CPAL investigated a broad spectrum of sealant materials, extensively reviewed test reports, evaluated the feasibility of installation and evaluated the cost-effectiveness of many seal designs. The objectives of this effort _were to identify seal designs that were:
Qualified for a fire resistance rating commensurate with.that required of the barrier in which fire seal is installed.
Suitable for a wide range of applications. _,
Relatively simple to install, utilizing cost-effective sealant materials and can be installed from one side of the fire barrier (thereby minimizing potential dual outage requirements).
CPAL has found suitable new candidate materials and designs, as identified in BSEP Specification 118-003, but has determined that some of these seals meet the industrially accepted 325*F temperature rise criterion rather than the 250*F temperature rise criterion specified in various NRC Staff guidance. It is CP&L's position, however, that the 325 F rise is a technically acceptable criterion for which justification has been provided in Section IV of this document.
A review of the fire seal test criteria in the Design Rasis Document (DBD)83219-1 demonstrates that Brunswick Steam Electric Plant (BSEP) meets the' intent of the NRC guideline (s).
II. NRC REQUIREMENTS / GUIDANCE:
Appendix A to BTP APCSB 9.5-1 incorporates by reference the specific test procedures outlined in ASTM Standard E119 (NFPA-251).
The ASTM E119 test was originally intended to determine the fire resisting capability of walls and floor assemblies. As such, it does /
not specifically address testing procedures for penetration seals.
The acceptance criteria of ASTM E119 states that the average temperature rise on the unexposed side of the test assembly should not exceed 250*F above ambient and that no single point should exceed 325*F above ambient. .
t i
Page 2 Further requirements for penetration seals are stated in paragraph III.M of Appendix R to 10CFR50, Appendix R. BSEP penetration seal designs were approved by SER under the Appendix A program, and as such requirements of Appendix R, paragraph III.M were not a backfit for BSEP. However, Appendix R paragraph III.M does establish the regulatory basis f or the NRC Staff guidance.
"III.M. Fire Barrier Cable Penetration Seal Qualification Penetration seal designs shall utilize only noncombustible materials and shall be qualified by tests that are comparable to tests used to rate fire barriers. The acceptance criteria for the test shall include:
- 1. The cable fire barrier penetration seal has withstood the fire endurance test without passage of flame or ignition of cables on the unexposed side for a period of time equivalent to the fire resistance rating required of the barrier;
- 2. The temperature levels recorded for the unexposed side are analyzed and demonstrate the maximum temperature is sufficiently below the cable insulation ignition temperature; and
- 3. The fire barrier penetration seal remains intact and does not allow projection of water beyond the unexposed surface during the hose stream test."
As can be seen, this requirement paraphrases the Appendix A guideline, but in very generalized terms. The acceptance criteria includes a limitation of temperature rise to a point "...sufficiently below the cable insulation ignition temperature..."
NUREG-0800 (BTP CMEB 9.5-1) Section C.S.a (3) states:
Penetration designs should utilize only noncombustible materials and should be qualified by tests. The penetration qualification tests should use the time-temperature exposure curve specified by ASTM E119, " Fire Test of Building Construction and Materials." The acceptance criteria for the test should require that:
- a. "The fire barrier penetration has withstood the fire endurance test without passage of flame or ignition of cables on the unexposed side for a period of time equivalent to the fire resistance rating required of the barrier."
- b. "The temperature levels recorded for the unexposed side are analyzed and demonstrate that the maximum temperature does not exceed 325'F."
- c. "The fire barrier penetration remains intact and does not allow projection of water beyond the unexposed surface during the hose stream test. The stream shall be delivered through L
T -
Page 3
- c. (Cont'd) a 1-1/2 inch nozzle set at a discharge angle of 30 with a nozzle pressure of 75 psi and a minimum discharge of 75 gpm with the tip of the nozzle a maximum of 5 ft. from the exposed face; or the stream shall be delivered through a 1-1/2 nozzle set at a discharge angle of 15 with a nozzle pressure of 75 psi and a minimum discharge of 75 gpm with the tip of the nozzle a maximum of 10 ft. from the exposed face; or the stream shall be delivered through a 2-1/2 inch national standard playpipe equipped with 1-1/8 inch tip, nozzle pressure of 30 psi, located 20 f t. from the exposed face."
Paragraph (b), above, states that the maximum temperature should not exceed 325 F.- It is generally accepted that this value is arrived at by considering a 250' rise above the ambient laboratory temperature of 75 F.
III. BSEP FIRE SEAL TESTING / ACCEPTANCE CRITERIA:
CPAL's fire seal testing / acceptance criteria for BSEP constitute a conservative, responsible approach, and is a position based on current BSEP Regulatory Commitments and criteria selected from several industry and regulatory standards.
l.. Fire Exposure Testing Criteria Fire exposure curve per ASTM E119-83, with monitoring of furnace performance as defined in ASTM E119-83, Section 4.
- 2. Hose-Stream Testing and Acceptance Criteria The imposition of hose-stream testing, the hose-stream specifications, and acceptance criteria shall be in accordance with ASTM E119-83, ASTM E814-83, UL 1479 or equivalent.
3 Unexposed Surface Temperature Measurement and Acceptance Criteria At least one thermocouple shall be located on the unexposed surface of the sealant material. Additional thermocouples to be placed to permit measurement of temperature at the interface between the fire seal and any penetrating components. These thermocouple location criteria are based on the guidance of ASTM E119-83 and IEEE 634-1978.
Page 4 3 .
The temperature rise should not exceed 325'F above ambient, consistent with ANI/MAERP temperature rise criteria -(Source:
ANI/MAERP Standard Method of Fire Tests of Cable and Pipe Penetration Fire Stops; February,1976). Any temperature exceeding 325 F above ambient shall be analyzed, and if justifiable, dispositioned by an engineering evaluation performed by a fire protection engineer.
IV. TECHNICAL JUSTIFICATION FOR PROPOSED .125'F TEMPERATURE RISE ACCEPTANCE CRITdRIA:
CPAL has determined that some of the new penetration seals identified in BSEP Specification 118-003, although tested per generally accepted industry practices, varies somewhat from the NRC Staff guidance. The seals have been tested in accordance with the provisions of IEEE-634 and ANI/MAERP. The primary differences between these test methods and the NRC Staff guidance are the acceptance criteria for the unexposed side temperature rise. The NRC Staff guidance generally limits the peak temperature to 325 F. ANI/MAERP test methods specify 325 F above ambient. IEEE-634 states that the penetration surface temperature should be sufficiently below the self ignition temperature of the cable (consistent with Section III.M of Appendix R).
Original fire testing, performed in the late 1970s for BSEP, was conducted in accordance with the testing and acceptance criteria of ASTM E119. As noted in the January 1,1977 Fire Protection Program Review, fire barrier penetration seals were qualified to 3-hour rating per ASTM E119.
Paragraph D.3.d of Appendix A to BTP APCSB 9.5-1 specifies that penetration seals should, as a minimum, meet the requirements of ASTM E119, " Fire Tests of Building Construction and Materials". The acceptance criteria of ASTM E119 states that the average temperature rise on the unexposed side of the test assembly should not exceed 250 F above ambient and that no single point should exceed 325'F above ambient. The ASTM E119 test is intended for wall and floor assemblies. Thermocouples are placed at a number of locations on the test assembly in order to record the average temperature rise. When testing penetration seals, insufficient surface area is present to mount a number of thermocouples. Specific criteria for location of penetration seal thermocouples is not addressed in ASTM E119. Other test methods specifically address this issue and have been used by BSEP. These test methods contain a single point maximum rise of 325'F above ambient temperature and, therefore, was used to qualify penetration seals. This concept is reflected in the ASTM E814 (UL 1479) test method. ANI/MAERP test methodology also specifies a single point maximum temperature of 325 F above ambient.
4 u*E E *4.h.+J- m. A a*4ah .is
' I Page 5
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-It was'further recognized that the influence of penetrating elements such as pipe or rigid steel conduit could adversely affect localized temperatures.on the unexposed side of the seal,.thus providing cause for rejection of an otherwise acceptable seal.. Further complexity is
. introduced.by the widely variable unexposed surface temperature rise criteria, ranging from 250*F above ambient ( ASTM E119) to 700'F (IEEE 634).
The issue of temperature rise on the unexposed surface of fire barrier penetration seals centers around the concern over possible ignition of
. combustible materials in contact with-or in the immediate vicinity of the " cold" side of the seal, thus causing a secondary fire in the the unexposed zone. This issue is of primary concern for electrical cable penetrations, in.that (combustible) cable-insulation is in contact with
! the seal, and the conductors are heated by the fire. The concern is mitigated by the acceptance criteria in the' test, which states that no flaming of cable insulation shall occur on the cold side.
The potential for combustibles other than cable insulation being located in.the vicinity of the penetration seals is.small. There'are two reasons.for this. First, areas where penetration are located tend
, to be congested due to the penetrants thems0lves, tending to preclude
! the accumulation of transient materials. Second, administrative i controls dictate which materials are acceptable inside plant structures, where they may be located and used, and how they are to be !
contained. These controls also provide for independent surveillance for procedure compliance.
Should' combustible materials encountered in the nuclear. plant l environment be present in the vicinity of a barrier, their ignition by .
~L exposure to the unexposed surface of a fire barrier is considered to be '
unlikely. The basis for this position is that in the first place, 4 .
material will never experience the unexposed surface temperature unless it is in direct contact with the barrier. Even a small amount of separation will preclude heat transfer by conduction and only slightly more distance will eliminate any convective heating. Thus, in most
-cases, the sole or predominant heat transfer mechanism is by radiation. This would preclude the exposed materials from even closely
[
approaching the barrier surface temperature.
' In the second place, for the type of material normally found in the plant, the additional 75'F temperature rise would not introduce a '
significant risk factor to material ignition.
Thus, even assuming an absence of administrative controls, a secondary fire resulting from a barrier unexposed side temperature rise of 325*F
. is not credible.
For mechanical (piping) penetrations, the BSEP design objective, per DBD 83219-1, is to limit the temperature rise on the unexposed surface
, to 325'F above ambient, the same limit imposed for electrical cable penetrations.
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The differential between the two acceptance temperatures (75 F) is inconsequential in light of the following reasons:
- 1. The margin of. safety afforded by the 325*F temperature rise
. limit is adequate. The IEEE 383 type cable at BSEP provides assurance that the self-ignition of cable insulation is not a credible occurrence, although a 75'F higher temperature rise is allowed by the BSEP acceptance criteria.
2 For each of the tested seal configurations, the maximum temperatures obtained on the unexposed surface of the seal remained well below the self-ignition temperature of the cable insulation, taken as a nominal 700'F as stated in IEEE-634 In the worst case cable-to-conduit seal temperatures measured, the highest temperature obtained was approximately 600*F (on 4
the conduit and on the cable), leaving a 100 F margin - below the auto-ignition, temperature of the cable insulation.
Additionally, this is not considered to be a failure due to the following statement in the ANI/MAERP test method:
"If a thermocouple on the fire stop material exceeds 325 F above ambient, the reason shall be investigated and if found to be high due to metal passing through the material, the reading shall be disregarded."
A survey of previously approved designs at other plants indicates that the NRC Staff position is consistent with ANI on this criteria.
' The current regulatory basis (though not applicable to BSEP per se) for the testing and qualification of fire barrier cable penetration seals is provided by 10CFR50, Appendix R, Section III.M. The criterion imposed for temperature rise on the unexposed side of the seal are stated in Section III.M.2: "The temperature levels recorded for the unexposed side are analyzed and demonstrate that the maximum temperature is sufficiently below the cable insulation ignition temperature".
Based on the above evaluation, CP&L concludes that the penetration seal design acceptance criteria for BSEP is technically acceptable as it will preclude the self ignition of combustibles on the unexposed side.
4
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Page 7 i
V. CONCLUSIONS:
The penetration seal DBD 83219-1 meets the intent of the NRC Guideline (s):
- 1. Fire Exposure Conditions NRC criteria specify the use of the ASTM - E119 fire exposure test.
RSEP DBD 83219-1 meets this NRC Guideline.
- 2. Hose-Stream Testing Conditions The ASTM E119 hose-stream test is consistent with the NRC hose-stream testing alternatives.
Therefore, BSEP DBD 83219-1 meets this NRC Guideline.
- 3. Unexposed Surface Temperature Measurement and Acceptance Criteria
- a. Location:
NRC criteria does not precisely specify the placement of thermocouples on the unexposed surface of the test sample. The criteria used by BSEP DBD 83219-1, which is based on IEEE-634 appropriately meet the intent of the NRC temperature measurement guideline,
- b. Temperature Rise:
Various industry criteria specify a maximum acceptable temperature rise of 325*F above ambient, and new seal designs have been selected accordingly.
Where localized temperatures (adjacent to metal masses) have subsequently exceeded this value for obvious and justifiable reasons, these temperatures have been dispositioned in the evaluation of the fire test results.
BSEP meets the guidelines set forth in various industry standards for penetration fire seal.
The BSEP acceptance temperature criterion of 400 F (325'F plus nominal 75'F ambient) ensures that a substantial thermal safety margin is maintained for the unexposed surface of BSEP fire seal designs, i.e., the maximum temperature remains sufficiently below the cable insulation ignition temperature.
i
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Page 8 In this context, the margin of safety afforded by a 250*F temperature rise limit is not significantly greater than:
that established by the 325*F limit. Accordingly, the BSEP
.. temperature rise criterion is consistent with the intent of the (nonspecific) temperature rise criterion of Appendix R,Section III.M.2.
Therefore, RSEP DBD 83219-1 meets the intent of the NRC guideline.
9 I
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Enclosure 2 i
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ADVANTAGES OF NELSON ELECTRIC SEALS Simple to install.
No specialized training required.
Tested for a wide range of applications, for example cable-to-conduit or pipe-to-sleeve seal designs.
No expensive equipment needed to install seals. No mixing or pouring required.
Utilizes cost-effectiv'e sealant material . '
Possesses desirable properties such as nonshrinking, waterproof, high adhesion, snoke and gas tight, easily repenetrated.
No cable derating required.
Can be installed from one side of the barrier.
l DESCRIPTION OF NELSON ELECTRIC SEAL COMPONENTS l (1) Nelson RSW - Rockwool treated with an intumescent material.
(2) Nelson CLK - Silicone rubber based fire sto'p caulk. Service temperatures: -49' to 284 *F 1
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' SKETCH A PI PE-TO-SLEEVE 4 CONDUIT-TO-SLEEVE -
This seal Figure 1).configuration was fire tested with a single layer of Nelson CLK on the " cold" side of the Nelson RSW (See No fire tests were conducted with the CLK on the fire side in the referenced fire tests. The BSEP seal design specifies a layer of CLK on both sides of the RSW (see Figure 2). This ensures that a seal design is provided consistent with the tested configuration regardless of which side of the barrier the fire originates.
(1) Sleeve 36 (3720F) _ SEAL INSTALLATION SIDE N (2) Nelson CLK 63-(2950F) " (0.5" thick)
_35 (2210F)
( ., M 2
6r [1 (3) Nelson RSW 3
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, . I} 3-Hour Rated l
' -^
e CF **.*
(8.0" thick) i'*
f ,* , ,
f g Concrete Wall ".1 (4) Conduit or Pipe 3 1 L or Floor , ,
2 1 (S) Back damming Material r 3 5 3-Hour Rated Nelson RSW c.; Kaowool Concrete Wall (see NOTE bick page)
, or Floor FIRE SIDE (6). Inner Layer of CLK (0.5" thick)
BSEP SEAL DESIGN FIRE TESTED CONFIGURATION INSTALLATION CONFIGURATION FIGURE 1 FIGURE 2 Maximum fesp. = 325 + 68 = 393*F Nelson Electric b
Nelson Test Report 057. Configuration P2
- Test conducted in accordance with CAN4-SilS, Standard Method of Fire Tests of Firestop Systems ( ASTM E814).
Time / temperature curve E119.
- Maxista annular space - 5" from pipe to sleeve (392 in.2 max.).
F rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as established by test).
- T rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as established from T/C readings on seal surface as defined in DBD) '
Passed hose stream (as established by E119 equivalent hose test). ,
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_ NELSON TEST REPORT NO. 057, JANUARY 1986 Test Report:
Type Seal: Nelson Test Report No. 0$7 (Nov.1985)
Cable-to-Conduit, Pipe to Sleeve (Sketches A, B, C)
Vendor:
GS Nelson Electric Testing Lab.: UL of Canada Witnesses: Nelson Electric, ANI, ULC Test Date: January 1986 Test conducted in accordance with CAN4-S115 Standard Firestop Systems.
J Standard time / temperature curve per ASTM E119.
Minimun of 3 T/C's on seal surface Hose stream intnediately in 3accordance after hour test. with CAN4-5115 applied to test assem NOTE:
This seal design is normally installed with work accomplished from both sides of the barrier. This enables accurate measurements and confidence that the Nelson CLK is of the proper depth. When installed from one side of a barrier, additional control is desirable to assure the proper depth of the internal (fBr side) Nelson CLK seal. This is assured by the use of a backdamming material. Af ter installing a tight fitting plug of mineral fiber in the penetration, measurements are taken. A layer of CLK is installed and nieasurements again taken to assure the minimum depth is present. The remainder of the seal can then be installed.
I
SKETCH B CABLE-TO-CONDUIT 4
sa( (1) Nelson CLK O.5"THK.
ff _3, 3 ,,y) (2) Nelson RSW f 20343*r)
(3) Conduit or Pipe
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4 .,.*.f. k ",f (4) Cables e
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2 3 -HOUk RATED 8.0"THK. % ) CONCRETE WALL
)j OR FLOOR .
FIRE SIDE Maximum Temp. = 325 + 68 = 393*F .
,
- Tested configuration similar to installed configuration. ~
Nelson Electric Nelson Test Report 057 Configuration P3 Test conducted in accordance with CAN4-S115 Standard Method of Fire Tests of Firestop Systems (ASTM E814).
Time / temperature curve E119.
F rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as established by test).
T rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as observed from T/C readings on seal surface as defined by the DBD) j Passed hose stream (as established by hose test).
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NELSON TEST REPORT NO. 057. JANUARY 1986 Test Report: Nelson Test Report No. 057 (Nov.1985) 1 Type Seal: l Vendor: Cable-to-Conduit, Pipe to Sleeve (Sketches A, B, C)
GS Nelson Electric Testing Lab.: UL of Canada Witnesses: Nelson Electric, ANI, ULC Test Date: January 1986 Test conducted Firestop Systems. in accordance with CAN4-S115. Standard Method of F Standard time / temperature curve per ASTM E119.
Minimum of 3 T/C's on seal surface.
Hose stream in immediately accordance after 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> test. with' CAN4-S115 applied to test assembly e
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SKETCH C CAB '.E-TO-CONDUIT s 4 So(soq J 2 8.0"THK. (1)
Nelson CLK s
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< -84399W (2) Nelson RSW mG (.3 beer) p f, ; ., ,- 'I , e, g. / (3)
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( 1
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1 3-HOUlt RATED' 0.S,,THK., w ) CONCRETE WALL OR FLOOR FIRE SIDE '
Maximun Temp. = 325 + 68 = 393*F
,
- Tested configuration similar to installed configuration.
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!
Nelson Test Report 057 Test conducted in accor Configuration P4
- of Firestop Systems (ASTM E814). dance with CAN-S115, Standard Method of F
- Time /tenperature curve E119.
l
- F rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as established by test).
' defined by the D80)T rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as observed from T/C readings o Passed hose stream (as established by hose test).
NELSON TEST REPORT 'NO. 057. JANUARY 1986 Test Repor't:
Type Seal: Nelson Test Report No. 057 (Nov.1985)
Vendor: Cable-to-Conduit, Pipe to Sleeve (Sketches A, B, C)
GS Nelson Electric Testing Lab.: UL of Canada Witnesses: Nelson Electric, ANI, ULC Test Date: January 1986 Test conducted Firestop Systems.in accordance with CAN4-S115, Standard Method of Fire Tests of Standard time / temperature curve per ASTM E119.
Minimum of 3 T/C's on seal surface.
Hose immediately streamafter in accordance 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> test.with CAN4-S115 applied to test assembly t
t s
O 6
i r- = a g4 - 9- --,yr-- w.-w-g+,--rw--w----+r-- -<,c w .- - . e,-s-em, - , - e e-,, em.,-e-,- - - - --- --- -* . * - --
SKETCH D CABLE-T0-CONDu!T This fiber seal (Seeconfiguration Figure 1). was fire tested with a single layer of Nelson CLK on the " cold" side of the Kaowool ceranic +
No fire tests have been conducted with the CLK on the fire side. The BSEP seal design specifies a layer of CLK on both sides of the Kaowool (see Figure 2). This ensures that a seal design is provided consistent with the tested configuration regardless of which side of the barrier the fire originates.
~
SEAL INSTALLATION SIDE 3 (1) Nelson CLK 38 (3340F) (0.5" thick) 33 (3470F) 32 (3430F) k h *
(2) Ceranic Fiber (Kaowoul)
(2.0" thick)
. I' 3-Hour Rated '
j '. \ . i Concrete Wall a
* ' 3-ilour
- Rated (3) Conduit or Pipe
! \~ i \ - Concrete Wall l or Floor i
- /Ea \
(4) Cables or floor (S) Back danning Material Nelson RSW or Kaowool (see NOTE back page)
FIRE SIDE (6) Inner Layer of CLK
- (0.b, thick)
! BSEP SEAL DESIGN FIRE TESTED CONFIGURATION INSTALLATION CONFIGURATION FIGURE 1 FIGURE 2 i
Maximum Temp. = 325 + 68 = 393*F Fire Protection Energy Ir$corporated/ Nelson Electric Report on Service Penetration Assemblies for Fire Protection Energy, Inc.
UL of Canada, File CR1644, Configuration P7.
- Test in accordance with CAN4-SilS, Standard Method of Fire Tests of Firestop Systems ( ASTM EB14).
- F rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as established by test).
- T rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as established froin T/C readings on seal surface).
Passed hose strean (as established by E119 equivalent hose test).
UNDERWRITERS LABORATORY OF CANADA, FILE CR1644, OCTOBER 1985 Test Report: UL of Canada, File CR 1644 Report on Service Penetration Assemblies for Fire Protection Energy, Inc.
Type Seal: Cable-to-Conduit (Sketch D)
Vendor: Fire Protection Energy, Inc.
Testing Lab.: UL of Canada Witnesses: Fire Protection Energy, Inc., ULC, ANI Test Date: October 1985 Test conducted in accordance with CAN4-S115, Standard Method of Fire Tests of Firestop Systems.
Standard time / temperature curve per ASTM E119. - -
Minimum of 3 T/C's on seal surface.
Hose stream in accordance with CAN4-5115 applied to test assembly inmediately after 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> test.
NOTE:
This seal design is normally installed with work accomplished from both sides of the barrier. This enables accurate measurements and confidence that the Nelson CLK is of the proper depth. When installed from one side of a barrier, additional control is desirable to assure the proper depth of the internal (far side) Nelson CLK seal. This is assured by the use of a backdenming material. Af ter installing a tight fitting plug of mineral fiber in the penetration, measurements are taken. A layer of CLK is installed and measurements again taken to assure the minimum depth is present. The remainder of the seal can then be installed.
e SKETCH E LIE SEAL W/ NELSON CLK.
SL(,29o*F)
- 5Ktf4*P) (1) Sl eeve 4
,9&od 3 2 0.5"THK. (2) Nelson CLK 1
(3) Conduit or Pipe a ** *. ~. "*}, *' ,M a . q . .; ,*
'. ",- Existing non-fire (4) 1;*-
- rated link seal mez a '
\
3-HOUR RATED 4 2 CONCRETE WALL 4 Od FLOOR 0.5"THK FIRE SIDE Maximum Temp. = 325 + 82 = 407'F
- Tested configuration similar to installed configuration.
Test in accordance with ASTM E814, Fire Tests of Through-Penetration Fire Stops.
F rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as established by test).
T rating - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as observed from T/C readings on seal surface as defined by the D8D)
Passed hose stream (as established by test). Subjected to all 3 hose streams of ANI/MAERP.
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SwRI PROJECT NO. 01-8821-0289 Test Report: SWRI Project No. 01-8821-0289
~
Type Seal: Link Seal with 1/2" CLK Both Sides (Sketch E)
Vendor: GS Nelson Electric Testing Lab.: Southwest Research Institute Witnesses: NUS, CP&L. ANI, Southwest Research Institute, Williams Electric Test Date: August 4, 1986 Test conducted in acccrdance with ASTM E814.
Standard time / temperature curve per ASTM E119.
Minimum of 3 T/C's on seal surface.
Hose streams in accordance with ANI/MAERP applied to test assembly, imediately after 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> test.
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