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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
f ,,
e CD&L
~
Carolina Power & Light Company SERIAL: NLS-84-111 MAR 0 91984 Director of Nuclear Reactor Regulation Attention: Mr. D. B.-Vassallo, Chief
. Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory. Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 o LICENSE NOS. DPR-71 AND DPR-62
-RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION - NUREG-0737 ITEM II.F.1.4, CONTAINMENT PRESSURE MONITOR SYSTEM ITEM II.F.1.5, CONTAINMENT WATER LEVEL MONITOR SYSTEM ITEM II.F.1.6, CONTAINMENT HYDROGEN MONITOR SYSTEM
Dear Mr. Vassallo:
-In your letter dated February 2, 1984, Carolina Power & Light Company (CP&L) was requested to provide information regarding NUREG-0737, Items II.F.1.4, .5 cud .6. The two general subject areas were identified as Attachments 2 and 14 to that letter.
Attachment 2 requested identifleation of any exceptions taken to those NUREG requirements that are within the review scope of the Containment Systems Branch. In response, CP&L considers Brunswick's implementation of the three subject items to be in complete compliance with the requirements stated in NUREG-0737.
Attachment 14 requests presentation of information related to the accuracy and time response characteristics of the equipment installed on the three subject items. In response, Attachment 1 to this letter provides the requested data.
Should you have any questions concerning this letter, please do not hesitate to contact a member of our Licensing Staff.
Yours very truly, m
8403210061 840309 S. Zi erman PDR ADOCK 05000324 Man
.P PDR Nuclear Licensing Section PPC/ccc (9653PPC) a ec: Mr. D. O. Myers (NRC-BSEP) fe Mr. J. P. O'Reilly (NRC-RII) h Mr. M. Grotenhuis (NRC) J k g fg 411 Fayetteville Street
- P. O. Box 1551 e Raleigh. N. C. 27602
ATTACHMENT 1 Response to: Attachment 14 of NRC letter dated February 2,1984, titled:
" Request for Additional -Information on three NUREG-0737 Items II.F.1.4 Containment Pressure Monitor II.F.1.5 Containment Water Level Monitor II.F.1.6 Containment Hydrogen Monitor" (2) II.F.1.4 - PRESSURE MONITORING SYSTEM (PMS) - ACCURACY AND RESPONSE c.
The wide range containment pressure monitoring system consists of two independent instrument loops, one driving a recorder and the other providing indication only. Both loops are calibrated over the range of
(-)5 to (+)245 PSIG. Since the loop components vary, they are' treated separately in the following discussion.
LOOP # 1 (2al) BLOCK DIAGRAM I I I Calibration l_ _ CAC-PT-4175 CAC-PR-1257-1 X-Xf-4346 l Test l [ Power Supply l l Gauge g l__ __ __ __ __I S
- - - --e , , - - - . - , . - - , . , - , -
'(2b1) MODULE UNCERTAINTY PARAMETERS CALIBRATI0d TEST GAUGE: HEISE PRESSURE GAUGE (REFERENCE #1)
General Accuracy: t0.1% of full scale. Two gauges are used
- one to cover the vacuum range and the other for the positive pressure range (300 PSIG). .Therefore, the greater uncertainty introduced is = * (.001) (300) =
- 0.3 PSIG Sg1 = Standard Deviation = * (1/3) (0.3)
= t 0.1 PSIG Temperature Effects: Not significant since the installed instrument location is near the ambient temperature of the lab in which the test gauges are calibrated.
CAC-PT-4175: ROSEMOUNT MODEL 1152 PRESSURE TRANSMITTER (REFERENCE #2)
General Accuracy: t0.25% of calibrated span (250 PSIG)
=t (.0025) (250) =t .625 PSIG ST1 = Standard Deviation =t (1/3) (0.625)
= i .208 = i .21 PSIG ,
Random Error:
Stability)=
(300 PSIG i 0.25% of upper range limit
= (.0025) (300) = i .750 PSIG ST2 = Standard Deviation = t (1/3) (0.750)
= * .250 = * .25 PSIG .
Temperature Effects: Total temperature effect including span and zero errors:
-@ min span (0-50) =
- 3.5% span /1000F 0 max span (0-300)=
- 1.0% span /1000F Interpolating for calibrated span of 2500F,
. effect = 1 1.5% span /1000F Post-accident temperature at instrument location peaks at 210 F 0 (140 F 0 above normal
~
ambient); therefore, the maximum temperature effect = i (.0015) (250) (1.4)
= * .525 = t .53 PSIG ST3 = Standard Deviation = * (1/3) (0.53)
= t .177 = i .18 PSIG Power Supply Voltage: i 0.005% of span (250 PSIG) per volt
= i .00005 (250) = t .0125 PSIG/ Volt Negligible compared to other effects considered Hysteresis: Included in general accuracy statement
~
Deadband: None
r CAC-PR-1257-1: BAILEY CONTROLS SR-1310 RECORDER (REFERENCE #3)
General Accuracy:
* (.005) (250)
- 1.25 PSIG SR1 = Standard Deviation = i (1/3) (1.25)
* .42 PSIG Random Errors: Linearity
= * (.0025) (250) = i .63 PSIG Sap = Standard Deviation = * (1/3) (.63) = i
.21 PSIG Repeatability =
= i (.001)-(250) = i .25 PSIG SR3 = Standard Deviation = * (1/3) (.25) = *
.US PSIG Power Supply Voltage: <0.02% of span (250 PSIG) per volt over the normal supply range of 23-29 VDC = * (.0002)
(250) =
- 0.05 PSIG/ Volt Negligible compared to other effects considered Hysteresis: 0.15% of span (250 PSIG)
- = (.0015) (250) = .38 PSIG Hysteresis Loop Half Width = .19 PSIG Deadband
- 0.1% of span (250 PSIG)
= (.001) (250) = .25 PSIG Deadband Loop Half Width = .13 PSIG (2c1) OVERALL SYSTEM UNCERTAINTY NOTE: The techniques utilized here, and in subsequent sections of this report, for combination of the various module uncertainty parameters are based on the instructions
. presented on pages 6 and 7 of Attachment 14 of the February 2,1984 NRC letter.
Under normal plant ambient temperature conditions, the standard deviation
- of the total measurement error is bounded by:
S2 (total system) = S2 (s) = S2 (s,b) + H2 (s) + H(s)
- D(s) + D2 (s)/2 S(s,b) = /S GI +ST1 +ST2 +SR1 +SR2 2+S R3
=
/.102 + .212 + 252 + .422 + .212 + .082
=
/.344 = * .59 PSIG
=
H(s) .19 PSIG
=
D(s) .13 PSIG O
Then:
'S (total system) =/(.59)2-+(,19)2+(.19)(.13)+(.13)2/2
=
/.417
= i .65 PSIG Under maximum accident temperature conditions at the transmitter location, the standard deviation of the total measurement error increases as follows:
S(s,b) =
/S gi 2+ST1 2+ST2 2+ST3 2+3R1 2+SR22+SR3
=
/ .102 + .212 + .252 + .182 + ,422 + .212 + .082
=
/.376 =
S (total system) =/(.61)2+(,19)2+(.19)(.13)+(.13)2/2
=
/.441 = + .66 PSIG
-(2dl) MODULE TIME RESPONSES CAC-PT-4175: Time constant continuousl;, adjustable between 0.2~and 1.67 seconds. To be left at factory setting of 0.2 seconds.
CAC-PR-1257-1: Pen speed adjustable from less than 1 second-to greater than 15 seconds for 98% of span. To be left at minimum setting, assume
= 1 second for 98% of span.
(2el) OVERALL SYSTEM TIME RESPONSE To be completed by NRC.
LOOP # 2 (2a2) BLOCK' DIAGRAM c _- _- _ _ )
I
! alibration C L- - CAC-PT-4176 CAC-PI-4176 (-XY-4350 l Test l
[ Power Supply l Gauge I -_ __ _ - a, ..
O
- -m e ---v, e -w ww*- r <-*-~s *-w rw e4<v-- w w- v' ~~e>'r~evw-- rv-s'-Y -- "r+- ?~- "
~
(2b2) UNCERTAINTY PARAMETERS
~ CALIBRATION TEST GAUGE: HEISE PRESSURE GAUGE (REFERENCE #1)
Same range and uncertainty parameters as stated above for Loop #1.
Use:
SG1 =-t 0.1 PSIG CAC-PT-4176 : -ROSEMOUNT 1152 PRESSURE TRANSMITTER (REFERENCE #2)
Same range and uncertainty parameters as stated above for PT-4175.
Use:
ST1 = + .21 PSIG ST2 = t .25 PSIG ST3 = * .18 PSIG CAC-PT-4176: INTERNATIONAL INSTRUMENTS SERIES 1151 INDICATOR (REFERENCE #4)
General Accuracy:
i (.015) (250)
- 3.75 PSIG Sit = Standard Deviation = * (1/3) (3.75)
i 1.25 PSIG Random Error: Repeatability
- 2.0% full scale (250 PSIG)
= i (.02) (250) = i 5.0 PSIG SI Standard Deviation = * (1/3) (5.0) = i 1.2/ =PSIG Temperature Effects: Not stated
. Power Supply Voltage: Not applicable Hysteresis: Not stated
^
Deadband: Not stated O
r
~(2c2) OVERALL SYSTEM UNCERTAINTY Under normal plant ambient temperature conditions _, the standard dev1ation of the total measurement error is bounded by:
S 2 (total system) = S2 (s) = S2 (s,b) + ti2(s) + H(s)
- D(s) + D2 (s)/2 S(s,b) = / Sgt2+S T1 +ST2 +SIl +SI2
= . / .102 + .212.+ .252 + 1.252 + 1,72
=
/4.7 = i 2.14 PSIG Since both H(s).and D(s) = 0, S (total system) = S2 (s,b) =
- 2.14'PSIG Under-maximum accident temperature conditions at the transmitter location, the standard deviation of the total measurement error is calculated as follows:
S(s,b) =
]Sgi2+ST12+ST22+ST32+3 I12+S !22
=
/.102 + .212 + .252 +. 182 + 1.252 + 1.72
=
/4.60 =
- 2.15 PSIG since both H(s) and D(s) = 0, S (total system) = S2 (s,b)- = i 2.15 PSIG Note that due to the relative magnitude of Sri, inclusion of the temperature effect does not significantly increase the system standard deviation.
(2d2). MODULE TIME RESPONSES CAC-PT-4176: Time constant continuously adjustable between 0.2 and 1.67 seconds. To be left at factory setting of 0.2 seconds.
CAC-PI-4176: Response time: 2.5 seconds maximum (includes response to a 3/4 full scale step change, with settling to within 1.5% full scale of the step target)
Damping factor: 5 minimum (per ANSI C39.1)
O
~
'(2e%) ~ '0VERALL SYSTEM TIME RESPONSE To be computed.by NRC.
-(3) -II.F.1.5 - WATER LEVEL MONITORING SYSTEM (WLMS) - ACCURACY The wide range suppression pool water level monitoring system features independent instrument loops, each monitoring over a calibrated range of 192 inches. Since the loop components vary, the loops are treated
-separately in the following discussion.
LOOP # 1 (3al)- BL0cK DIAGRAM e - --
I l
I Calibration l-- CAC-LT-2601 CAC-LI-2601 X-XY-4374 l Test l l Gauge l L __ _- _. _ J l
I (3b1) UNCERTAINTY PARAMETERS CALIBRATION TEST GAUGE: WALLACE & TIERNAN SERIES65-120 PORTABLE PENUMATIC CALIBRATOR (REFERENCE #6), or better General Accuracy: *0.1% of full scale (950 inches)
* (.001) (950)
~~ Sg1 = Standard Deviation ~= t (1/3) (.95)
t 0.32 inches l Random Error: Repeatability
- 0.03% of full scale (950 l
inches)
= t (.0003) (950) = t 0.285 inches SG2 = Standard Deviation = i (1/3) (.285)
= i 0.10 inches l
l .
l
Temperature Effects: Maximum is 0.1% of full scale per 180F change from 770F. The instrument loop calibration task requires use of the pneumatic calibrator unit in a plant location where ambient temperatures are usually elevated. Assume ambient at approximately 950F. Therefore, the normal temperature effect = t. (.001) (950) =
- 0.95 inches SG3 = Standard Deviation = * (1/3) (0.95)
= i 0.32 inches Power Supply Voltage: Not applicable Hysteresis: 0.1%'of full scale
= (.001) (950) = 0.95 inches Hg (s) = Hysteresis Loop Half Width = 0.48 inches Deadband: Sensitivity = 0.01% of full scale
= (.0001) (950) = 0.095 inches DG (s) = Deadband Loop Half Width c 0.048 inches CAC-LT-2601: ROSEMOUNT 1153 DIFFERENTIAL PRESSURE TRANSMITTER (REFERENCE #5)
General Accuracy: i 0.25% of calibrated span (192 inc;ies)
t (.0025) (192)
- 0.48 inches ST1 = Standard Deviation = * (1/3) (0.48)
=
- 0.16 inches Random Error: Stability =
- 0.25% of upper range limit (750 inches)
= t (.0025) (750) = t 1.88 inches ST2 = Standard Deviation = * (1/3) (1.88)
=
- 0.63 inches Temperature Effects: For Rosemount range code 5 (0-125 to 0-750
- inches H2O):
i (0.75% Upper Range Limit + 0.5% span) per 1000 F ambient temperature change.
= * [(.0075) (750) + (.005) (192)]
t 6.59 inches /100 0F ambient temperature change Post-accident temperature at instrument location peaks at 295 F0 (2250F above normal ambient, therefore, the maximum temperature effect = i (6.59) (2.25)
T = Standard Deviation = i (1/3) (14.83)
=
- 4.94 inches g - ,--w--.r r- --ga- ~ - .- -, , - -
m - ,
Power Supply Voltage: <.005% of span (192 inches) per volt
= i (.00005) (192) = i .0096 inches / volt Negligible compared to other effects considered
-Hysteresis: Included in general accuracy statement
.Deadband: None CAC-LI-2601: INTERNATIONAL INSTRUMENTS SERIES 1151 INDICATOR (REFERENCE #4)
General Accuracy:
- 1.5% of span (192 inches)
* (0.15) (192)
- 2.88 inches Sri = Standard Deviation = i (1/3) (2.88)
=
- 0.96 inches Random Error: Repeatability = i 2.0 % full scale (192 in.)
i (.02) (192)
- 3.8 inches SI2 = Standard Deviation = i (1/3) (3.8)
=
- 1.27 inches Temperature Effect: Not stated Power Supply Voltage: Not applicable Hysteresis: Not stated Deadband: Not stated (3c1) OVERALL SYSTEM UNCERTAINTY Under normal plant ambient temperature conditions, the standard
._ deviation of the total measurement error is bounded by:
,, S 2 (total . system) = 2S (s) = S 2 (s,b) + H 2 (s) + H(s)
- 0(s) + D2 (s)/2 S(s,b) + SG2 +SG3 +STI + ST2 2+S Il +SI2
= ,/ SG1
~
= / .322 + ,102+ .322 +.162 + .632 + .962 + 1.272
=
/ 3.17 =
=
H(s) HG (s) = 0.48 inches
-D(s) =-
Og(s) = 0.048 inches S (total system) = /1.782 + .482 + (.48) (.048) + .0482 /2
=
/3.54 = i 1.88 inches e
,,,,~-,-%.., , . , , . , , , . - . , , --~ ---
s Under maximum accident temperature conditions,at the transmitter location, the. standard deviation of the total measurement error is
-calculated as'follows:
.S(s,b)-='/Sgg 2+3G22+SG32+ST12+ST22+ST32+S Il + S12 2
=:-/.322 + .102 +.322+ .162 + .632 + 4,942 + .962 + 1.272
=
/27.58 =
- 5.25 inches H(s) = Hg(s) = 0.48 inches
=
D(s) Og (s) = 0.048 inches S (total system) = /5.252 + ,482 + (,48) (.048) + .0482/2
/27.82
- (3a2) BLOCK DIAGRAM i i CAC-LT-2602 CAC-LR-2602 X-XY-4346 l Calibration Test l- -
! Gauge I l_. _ __ _.I
- (3b2) MODULE UNCERTAINTY PARAMETERS CALIBRATION TEST GAUGE: WALLACE & TIERNAN SERIES65-120 PORTABLE PNEUMATIC CAllBRATOR (REFERENCE #6), or better
~
Same range and uncertainty parameters as stated aboye for Loop #1.
Use:
Sgt = t 0.32 inches SG2 =
- 0.32 inches Hg(s) = 0.48 inches DG (s) = 0.048 inches. ,
l
--o,,- e y y- .-y-.- , - , ,---g-,r-..,,.-e em--- ,.e-s-----,--y,y,y- a,-ee - ,e,,
- c. ,
CAC-LT-2602: ROSEMOUNT 1153 DIFFERENTIAL PRESSURE TRANSMITTER (REFERENCE #5)
Same range and uncertainty parameters as stated above for LT-2601.
Use:
ST1 = f '6 inches
- ST2 =
- 4.94 inches CAC-LR-2602: BAILEY CONTROLS SR-1110 RECOR0ER (REFERENCE #3) sineral Accuracy: i 0.5% of span (192 inches)
= * (.005) (192) = 0.96 SR1 = Standard Deviation = * (1/3) (0.96)
= i .32 inches
^ Random Errors: Linearity:
- 0.25% of span (192 inches)
* (.0025) (192)
- 0.48 inches SR2 = Standard Deviation = * (1/3) (0.48)
=
- 0.1% of span (192 inches)
i (.001) (192)
- 0.19 inches SR3 = Standard Deviation = i (1/3) (0.19)
=
- 0.06 inches Power Supply Voltage: <0.02% of span (192 inches) per volt over the normal supply ran9e of 23-29 VDC = *
(.0002) (192) =
- 0.05 inches / volt Negligible compared to other effects considered.
Hysteresis: 0.15% of span (192 inches)
= ( 0015) (192) = 0.29 inches HR (s) = Hysteresis Loop Half Width = 0.15 inches Deadband: 0.1% of span (192 inches)
= (.001) (192) = 0.19 inches DR (s) = Deadband Loop Half Width = 0.10 inches 1
e
(3c2) DVERALL SYSTEM UNCERTAINTY Under normal plant ambient temperature conditions, the standard deviation of the total _ measurement error is bounded by:
S 2 (total systen) = S2(s) = S2(s,b) + H2(s) + H(s)
- D(s) + D2 (s)/2 S(s,b) = /Sg12 + 3g22+3 G3 +ST1 +ST2 +SR1 +SR2 2+S R3
=
/.322 + .102+ .322+ .162 + .632 + .322 + .162 + .062
=
/._769 =* .88 inches
=
H(s) H(s)+H{s)=0.48+0.15=0.63 g R inches 0(s) = Dg(s) + DR is) = .048 + 0.10 = 0.15 inches S (total system) = / .882 + .632 + (.63) (.15) + .152/2
=
/1.28 =
- 1.13 inches Under maximum accident temperature conditions at the transmitter location, the standard deviation of the total measurement error is calculated as follows: -
S(s,b)=/S gi 2+3 G22+S G3
+S T1 2+ST22+ST32+S R1 +S R2 2+S R3
=/.322 + .102 + .322+ .162 + .632 + 4,942 + .322 + .162 + .062
=/25.17
=
- 5.02 inches H(s) = 0.63 inches D(s) = 0.15 inches S(totalsystem)=)5.022 + .632 + (.63) (.15) + .152/2
= i 5.07 inches (4)'.II.F.1.6 - HYDR 0 GEN MONITORING SYSTEM (HMS) - ACCURACY & PLACEMENT The containment hydrogen (and oxygen) monitoring system consists of two independent, but identical, sampling and instrument systems. The range of the analyzers is 0-30% for hydrogen and 0-25% for oxygen. Only the hydrogen loop calculations are performed here; however, since the corresponding module uncertainties are identical for the hydrogen and oxygen loops in terms of percent of full scale, the oxygen standard deviation may be assumed at 25/30 of that calculated herein for the hydrogen.
m ,, . - . - . , - , ,-.y ,. --
=
-(4a) BLOCK DIAGRAM i l i I Calibration;__:AC-AT/Al-4409_, X-XY-4348 X-XY-4349 CAC-AR-4409 l Gases l l __ l (4b) MODULE UNCERTAINTY PARAMETERS CALIBRATION GASES: " UNION CARBIDE" PRIMARY STANDARD GRADE MIXTURES (REFERENCE #11)
General Accuracy: " Blended gravimetrically on sophisticated electronic balances. Each ' primary' grade mixture is subsequently analyzed by gas chromatography against a gravimetric UCRM, an "NBS" SRM or an "NBS Traceable" CRM. The concentrations determined analytically will agree with the concentrations calculated from the measured we)ghts of the component gases within i 1% relative uncertainty at the ninety-five percent confidence interval.
For the 30% span Hydrogen loop, the calibration span gases used are 9.5% H 2/N2 and 28.0% H 2 accounting f;/N . A conservative or loop uncertaintiesapproach due to to span gas mixture uncertainty is to utilize the higher gas tolerance = i (.01) (28.0) =
- .28% H2 The, S (1/3) (.28) =
- gt.09% = Standard H2 Deviation = i CAC-AT/AI-4409: TELEDYNE ANALYTICAL INSTRUMENTS CONTAINMENT MONITOR 225 CMA (REFERENCE #5)
General Accuracy: i 2.5% full scale (30% H9)
= * (0.25) (30) = t 0.75% H S
T1 = Standard Deviation = *2 (1/3) (0.70)
' i 0.25% ii 2 Random Error: Stability =
* (.02) (30)
- 0.60% H S T2 = Standard Deviation =2* (1/3) (0.60)
=
Temperature Effect: Effect of water vapor in sample on hydrogen indication: The water vapor left in the sample after passing through the analyzer cabinet cooler and dryer still has a minor effect on the hydrogen readings. It is a function of the ambient temperature in the reactor building adjacent to the analyzer cabinet. Refer to the following water vapor correction graph.
140 138 l
~
130 j 125 l 120
! 115 C ;
g( [ for Hydrogen i a *
k 100 j
.0 /
.o /
0 .1 .2 .3 .4 .5 .6 Requered Subtrocoon from Indstated H, Cone (%)
WaterVapor Correction In abnormal conditions where steam becomes a significant percentage of containment atmosphere (such as relief valves lifting or loss of coolant accident), a major correction factor must be applied to both the hydrogen and oxygen indicated values.
' Since the analyzer system conditions the sample via cooling and drying, the indicated concentrations are dry-basis values, which will be conservatively higher than the actual in containment wet-basis concentrations. The required correction can be calculated from the following instructions and must be applied to both the hydrogen and oxygen indicated concentrations.
- 1. Match the air / nitrogen expansion pressure with the containment temperature.
Example: At 3200F, the air / nitrogen =
21.6 psia.
O
, - , , ,-.. ,.-n- - - - - , . - . , -
- 2. Add 15 psi to the containment pressure to obtain the absolute pressure:
Example: If the containment pressure is 30 psig, the absolute pressure = 30
+ 15 = 45 psia.
- 3. To obtain the wet-basis value inside containment, multiply the dry-basis value obtained by the analyzer times the air expansion pressure found in 1.
divided by the total pressure found in
- 2. above.
Example: If the hydrogen monitor reads 3.0% hydrogen, the wet-basis reading would be 3.0 x (21.6/45) = 1.4%
hydrogen.
C6. .^ ... .. .; Temperature 'F e,o too 12o 14o iso iso zoo 22o 24o zoo 2so ,soo 32o 34o soo is.o i s.'o " ~ ilo Eo '~ do in n 2Eo "' 23.'o " 2$.o Air / Nitrogen Expansion (PSIA)
Wet-Basis (Steam) Correction .
The above corrections are published in the system Operating Procedure, OP-24, for application when necessary. On that basis, they will not be included in the calculations performed in this report on total system uncertainty parameters.
Poner Supply Voltage: No effect stated
.. Flow Measurement: Flow measurement does not effect the system accuracy. Flow rate, however, would be a factor in calculation of the system response time.
' Transducer / Transmitter Separate: The Teledyne system is conposed of a variety of sub-modules; however, all accuracy and performance specifications are stated by the vendor on a system-only basis. For purposes of this report, the entire Teledyne -
supplied system will be treated as a single module. Uncertainty parameters associated with the external recording loop are defined in the following section and are included in the system uncertainty calculations.
Hysteresis: Not. stated Deadband: - Not stated X-XY-4348: FOXBORO COMPANY SPEC 200 SERIES CURRENT-TO-VOLTAGE CONVERTER MODEL 7 2Al-12V_ (REFERENCE #8)
~
General Accuracy: i 0.25% of output span (30% H2 )
= * (.0025) (30) = * .075% H S y1 = Standard Deviation = *2(1/3) (.075)
= * .0 3% H2 Random Error: Not stated Temperature Effects: t0.5% of output span for
- 50 0F in ambient temperature 0
i (.005) (30)
- 0.15% H2 for i 50 F change. This instrument is located in the main control room and will not be subjected to significant temperature variation. This effect is then considered '-
negligible for purposes of these calcolations.
Power Supply Voltage: i 0.2% of span (30% H2 ) for a i 5% change within normal operating limits of + 15 and -
15 VOC supply. -Negligible compared to other factors considered.
Hysteresis: Not stated Deadband: Not stated X-XY-4349: FOXBOR0 COMPANY SPEC 200 SERIES VOLTAGE-TO-CURRENT CONVERTER MODEL 2AO-VAI (REFERENCE #9)
. General Accuracy:
- 0.5% of output span (30% H2 )
=
t (.005) (30) = * .15% H S
X1 - Standard Deviation =2* (1/3) (.15)
= i .05% H2 R.indom Error: Repeatability = < t 0.1% of input span (30% H2 )
=
=
X2 = Standard Deviation =2t (1/3) (.03)
- - - - ,. , . . , . , g , , . , ._c.,%we,%,m,,_% .,,..%, ,_er-, _ , _-.,, , - ,- , , , ~ , . , _ ,
E Temperature Effects: *0.5% of output span for
- 50 0F in ambient temperature 0
i (.005) (30)
- 50 F change. This instrument is located in the main control room and will not be subjected to significant temperature variation. This effect is then considered negligible for purposes of these calculations.
Power Supply Voltage: i 0.5% of span (30% H2 ) for a
- 5% change within normal operating limits of +15 and
-15 VDC supply. Negligible compared to other factors considered.
Hysdresis: Not stated Deadband: Not stated CAC-AR-4409: LEEDS & NORTHRUP SPEEDOMAX M MARK II MULTIPOINT RECORDER (REFERENCE #10)
General Accuracy: 10.5% of full scale (30% H 2 ) = * (.005) (30)
= * .15% H2 Sgt = Standard Deviation = * (1/3) (.15)
= * .05% H2 Deadband: 0.25% of full scale (30 % H2 )
= (.0025) (30) = .075% H 2 Deadband Loop Half Width =.038 = .04% H2 (4c) OVERALL SYSTEM UNCERTAINTY The standard deviation of the total measurement error is bounded by:
S 2 (total system) = S2 (s) = S2 (s,b) + H2 (s) + H(s)
/SG12+ST12+S T2 +S Y1 2+SX12+SX22+S R12
=
/ .092 + .252 + .20 2 + .032 + .052 + .012 + .052
=
/.117 =* .34 % H2 H(s) = 0 0(S) = .04% H 2 S(totalsystem)=/.342 + 0 + 0(.04) + .04 2/2
=
/.116 i .34% H2
(4d)LSAMPLING-CONSIDERATIONS Each of the two instrument systems is connected to four different sample points from the primary containment (General Electric Mark I). The sample sources are:
- 1) Suppression pool atmosphere
?.) Drywell lower (plant elevation (-) 6')
3)' Drywell mid (plant elevation 50')
- 4) Drywell head (above reactor well seal, plant elevation 100')
Normal sample lineup is for one system to draw off the suppression pool atmosphera and the other from a drywell source.
(4e) OBSTRUCTIONS Any hydrogen gas that escapes the core and is released from the primary coolant system boundary (either via steam relief valves or coolant system rupture) will become mixed in either the suppression pool or drywell general air space. There are no compartments or barriers in Brunswick's General Electric Mark I containment design that would prohibit or delay such mixing from taking place.
b 9
O
, , , , . , , ,..---ww w-e. ----- ----
m.
REFERENCES 1)' Heise Gauge Data obtained from CP&L Test Equipment Room
- 2) .Rosemount Product Data Sheet:2235, Revised 11/80
- 3) Bailey Controls Manual E12-10, CP&L Foreign Print F.P.-7550
- 4) International Instruments Series 1151/1251, Bulletin IC-158R-281-3M-S, and clarified via telecon with vendor
- 5) Rosemount Product Data Sheet 2388, Revised 9/82
- 6) Wallace & Tiernan Catalog File 650.120, Revised 11/76 17 ) Teledyne' Analytical Instruments, Model 225 CMA Instruction Manual, CP&L Foreign Print F.P.-9541
- 13) Foxboro Technical Information Bulletin TI 2Al-130, Oct.1977
~
- 9) Foxboro Technical Information Bulletin TI 2A0-130, Oct.1977
- 10) Information obtained via telecon with vendor
-11) Linde-Union Carbide Catalog L-3396E, Pg. 59, printed 1/82 '
W 0
0
. ~ . . _ . .
, - _ . - , _ . _ . _ - _ . _. _ ~
. _ _ - . _,.. ._ _ . . _ - .