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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:OUTGOING CORRESPONDENCE
MONTHYEARML20217G1191999-10-0808 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 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 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) 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 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 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 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 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 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 ML20210P2031999-08-0505 August 1999 Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2 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 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 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 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 ML20195H6931999-06-0707 June 1999 Forwards Insp Repts 50-324/99-03 & 50-325/99-03 on 990328-0508.Two Violations Noted & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20195E8721999-05-28028 May 1999 Informs That Meeting Re Recently Completed Plant Performance Review for Licensee Facility Scheduled for 990720 ML20207B6081999-05-27027 May 1999 Informs That Staff Finds That RWCU Sys Piping Outboard of Second CIV at Bsep,Units 1 & 2,meets Staff Criteria of Schedule a as Delineated in Encl.Licensee Proposal to Eliminate Augmented Insp Per GL 88-01,acceptable ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML20206G1811999-05-0404 May 1999 Forwards SE Approving Three of 25 Relief Requests Submitted by for Third 10-year ISI Program.Remaining Reliefs Will Be Evaluated in Separate SEs ML20206B9291999-04-26026 April 1999 Forwards Insp Repts 50-324/99-02 & 50-325/99-02 on 990214-0327.Three Violations Being Treated as non-cited Violations ML20206A1561999-04-0909 April 1999 Informs That on 990316,M Herrell of CP&L & Author Confirmed Initial Operator Licensing Exam Schedule for Y2K. Initial Exam Dates Will Be Wks of 000214 & 20 for Approx 16 Candidates.Nrc Will Write Exam ML20205J9121999-03-31031 March 1999 Informs That Effective 990328,A Hansen Became NRR Licensing Project Manager for Brunswick Steam Electric Plant,Units 1 & 2 ML20205F8681999-03-30030 March 1999 Discusses Approval of Change to EP Eliminating Incorporation of Technical Support Center Into Protected Area.Forwards SE Related to Location of Technical Support Center ML20205D5541999-03-30030 March 1999 Discusses Core Shroud Reinsp Plan Submitted by CP&L on 980828 & 981221 for BSEP Unit 2 Refueling Outage 13 (B214R1) Scheduled to Begin on 990417.Concludes That Proposed Reinsp Plan & Schedule for Reinsp of Weld H5 Acceptable ML20205D2931999-03-23023 March 1999 Advises of NRC Planned Insp Effort Resulting from Plant PPR Completed on 990204,to Develop Integrated Understanding of Safety Performance.Historical Listing of Plant Issues & Details of Insp Plan for Next Eight Months Encl ML20204J8071999-03-18018 March 1999 Forwards Insp Repts 50-324/98-14 & 50-325/99-14 on 990111-15,25 & 29.Violations Being Treated as non-cited Violations ML20204J7241999-03-15015 March 1999 Forwards Insp Repts 50-324/99-01 & 50-325/99-01 on 990103- 0212.No Violations Noted.Five Violation Being Treated as non-cited Violations ML20207H4291999-03-0202 March 1999 Discusses NRC OI Rept 2-1998-014 on 980429-990112.NRC Determined That There May Have Been Atmosphere at BSEP Such That Employees Were Reluctant to Report Safety Problems. Requests Written Response Re Position on Environ ML20203D5831999-02-10010 February 1999 Forwards Biological Opinion for CP&L Review & Comment Re Impact on Endangered Sea Turtles of Operation of Brunswick Steam Electric Plant ML20203D6871999-02-0909 February 1999 Forwards SER Accepting Licensee 980225 & 0806 Relief Requests PRR-02,VRR-02,VRR-03,VRR-05,VRR-11,VRR-12 & RFJ-03, Associated with Third 10-year Interval Inservice Testing Program for Brunswick Steam Electric Plant,Units 1 & 2 ML20203G5371999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20202J5761999-01-28028 January 1999 Forwards Insp Repts 50-324/98-11 & 50-325/98-11 on 981122-990102.No Violations Noted.Evaluated 990120 Response to NOV 50-325/98-10-03 & Found Response Meets Requirements of 10CFR2.201 ML20199K9921999-01-22022 January 1999 Ack Receipt of Util 990112 Withdrawal of Request for Exemption, from 10CFR70.24 Requirements for Criticality Monitoring Sys in Areas of Brunswick Steam Electric Plant ML20199G7621999-01-15015 January 1999 Responds to Util ,As Supplemented by 980225 & 0520 Ltrs,Describing Spring 1998 Core Shroud Reinspection Plan for Unit 1.NRC Found Plan Acceptable ML20199K3071999-01-14014 January 1999 Informs That on 990117,Region II Will Implement Staff Reorganization as Part of agency-wide Streamlining Effort. Copy of Organization Charts for Info Encl ML20198P0121998-12-28028 December 1998 Ltr Contract:Task Order 35, Brunswick Safety Sys Engineering Insp, Under Contract NRC-03-98-021 ML20206R8781998-12-23023 December 1998 Provides Summary of 981105 Training Managers Conference Held in Atlanta,Georgia.Conference Agenda,List of Conference Attendees,Presentation Slides & Preliminary Schedule for FY99 & FY00 Encl ML20198P4621998-12-21021 December 1998 First Partial Response to FOIA Request for Documents. Documents Listed in App A,Already Available in Pdr.Documents Listed in App B,Being Release in Their Entirety.Documents Listed in App C,Withheld in Part (Ref FOIA Exemption 6) ML20198P0211998-12-21021 December 1998 Forwards Insp Repts 50-324/98-10 & 50-325/98-10 on 981011- 1121 & Nov.Two Violations of NRC Requirements Identified. Violation a of Concern Because NRC Identified Two Standby Gas Treatment Sys Valves Out of Position ML20198C6641998-12-17017 December 1998 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, Issued on 980506 ML20196F5151998-12-0202 December 1998 Forwards RAI Re Extension of Balance of Plant & Emergency Electrical Bus Aot,Submitted as Part of Application for Converting to ITS for Plant,Units 1 & 2 Dtd 961101.Response Requested within 30 Days from Receipt of Ltr ML20196G2481998-11-25025 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting on 981102.Insp Plan for Next 4 Months & Historical Listing of Plant Issues,Called Plant Issues Matrix, Encl ML20196D4831998-11-24024 November 1998 Forwards Insp Repts 50-324/98-13 & 50-325/98-13 on 981026-30.No Violations Noted.Rept Partially Withheld Ref 10CFR73.21 ML20196D6481998-11-20020 November 1998 Informs That Ssei Repts 50-324/99-01 & 50-325/99-01 at Brunswick Facility Have Been Scheduled for 990111-15 & 25-29.Insp Objective Will Be to Evaluate Capability of Hpci& RCIC Sys to Perform Safety Functions Required ML20196C9921998-11-13013 November 1998 Informs That on 981007,NRC Administered Generic Fundamentals Exam Section of Written Operator Licensing Exam.Copy of Answer Key & Master Bwr/Pwr Encl,Even Though Util Did Not Participate in Exam.Without Encls ML20195G4121998-11-0909 November 1998 Forwards Insp Repts 50-324/98-09 & 50-325/98-09 on 980830-1010.NRC Concluded That Info Re Reasons for Violation & C/A Taken & Planned to Correct Violation & Prevent Recurrence,Already Adequately Addressed in Encl Insp Rept ML20155C6771998-10-27027 October 1998 Forwards Audit Rept on Year 2000 Program for Plant,Units 1 & 2,conducted on 981006-09 as Followup to NRC GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Issued on 980511 1999-08-05
[Table view] |
See also: IR 05000324/1997012
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February 13, 1998
EA 98 057
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Carolina Power .1d Light Company
ATTN: Mr. C; S, Hinnant
Vice President
Brunswick Steam Electric Plant
P._0. Box 10429
Southport, NC 28461
SUBJECT: NRC INSPECTION REPORT NOS. 50-325/97 ' .10 50-324/97-12
4
,
Dear Mr. Hinnant:
,
Thank you for your response of January 7,1998, to our Notice of Violation
,
-issued on December 8, 1997, concerning activities conducted at your Brunswick
' facility. We have examined your response and found that it meets the
requirements of 10 CFR 2.201.
>
In your response, you admitted Violations A-D and denied Violation E.
After careful consideration of the basis for your denial of Violation E, we
,
'have concluded.-for the reasons presented in the ^nclosure to this letter,
that the violation occurred as stated in'the Notice of Violation. Therefore,
in accordance with 10 CFR 2.201(a) please submit to this office within 30
days of the date of this letter a written statement describing steps which
'
have been taken to correct Violation E and the results achieved, corrective
-
steps which will be taken to avoid further violations, and the date when full
compliance will be achieved.
We will examine the implementation of your actions to correct Violations A-D
during future-inspections.
We appreciate your cooperation.in this matter.
Sincerely.
( Original signed by B. Mallett )
Bruce-S. Mallett
Deputy Regional Administrator
Docket Nos. 50-323 50-324
License Nos. 'DPR-71. DPR-62
Er.alosure: Evaluat' ns and Conclusions
c cc w/ encl: _'(Seepage 2)l
-
E ADS $ o E S2
G PDR t
, __ _ -- .- _ _ _ _
8'b
.. . - . ._. .- - . .
.
CP&L 2
cc w/ enc 1:
Director
Site Operations
Brunswick Steam Electric Plant
Carolina Power & Light Company
P. O. Box 10429
Southport, NC 28461
J. J. Lyash, Plant Manager
Brunswick Steam Electric Plant
Carolina Power & Light Company
P. O. Box 10429
Southport. NC 28461
D. B. Alexander. Manager
Performance Evaluation and
- .atory Affairs OHS 7
Carolina Power & Light Company
412 S. Wilmington Street
Raleigh. NC 27601
K. R. Jury, Manager
Regulatory Affairs
Carolina Power & Light Company
'
Brunswick Steam Electric Plant
P. O. Box 10429
Southport. NC 28461-0429
Wtiliam D. Johnson
Vice President & Senior Counsel
Carolina Power and Light Company
P. O. Box-1551
Raleigh, NC 27602
Mel Fry, Acting Director
Division of_ Radiation Protection
N.~C. Department of Environmental
Commerce & Natural Resources
3825 Barrett Drive
Raleigh NC 27609-7721
Karen E. Long
-Assistant Attorney General
State of North Carolina
P, 0. Box 629
Raleigh. NC 27602
(cc w/ encl-cont'd - See page 3)
, . - . - -. . . _ _ . .
4
.
CP&L 3
(cc w/ encl cont'd)
Robert P. Gruber
Executive Director
Public Staff NCUC
P. O. Box 29520
Raleigh NC 27626 0520
Public Service Commission
State of South Carolina
P. O. Box 11649
Columbia. SC 29211
Jerry W. Jones. Chairman
Brunswick County Board of
Commissioners
P. O. Box 249
Bolivia. NC 28422
Dan E. Summers
Emergency Management Coordinator
New Hanover County Department of
Emergency Management
P. O. Box 1525
Wilmington, NC 28402
William H. Crowe. Mayor
City of Southport
201 E. Moore Street
Southpor+, NC 28461
Distribution w/ encl:
M. Shymlock Rll
D. Trimble. NRR
J. Lieberman. OE
B. Summers. OE
J. Colev RII
R. Aiello. RII-
,
'J. Lenahan. RII
-
E. Testa. RII
D. Thompson RII
PUBLIC
NRC Resident Inspector
U. S. Nuclear Regulatory Conrission
8470 River Road. SE
Southport NC 28461- ,
0* ik ' .i
- 'See previous concurrence b
Ur t t CE - Wil:DNP Ell:DEP 211:DRP Ril:DRP Ril:EICS Ril:DRP D J)[:N
umK rE5 ream 'C9etterson "tElecDonald "N5hyistock "ABe, Land
Ibbh
_
"JJohnson_ gifTho@ son
DATE Z/ /95 Z/ /95 2/ /90 2/ /95 - 2/ /95 2/ /95 Z/ G /95 ,
Lurir YE5 ND YE5 ED YE5 ND YE5 ND YE5 ND YES NO YE5 NO l
0FFICIAL REOMD COPf DDrtsEmi umpE: G:\gau\9712DENI.917
I
. . - - - _ . - . . -
4
.
CP&L 3
(cc w/enci cont'd)
Robert P. Gruber /
[
Exec. tive Director /
Public Staff NCUC
P. O. Box 29520
Raleigh. NC 27626-0520
. Public Service Commission
State of South Carolina-
P. O. Box 11649
Columbia, SC 29211
Jerry W. Jones Chairman
Brunswick County Board of
Commissioners
P. O. Box 249
Bolivia, NC 28422
Dan E. Summers
Emergency Management Coordinator
New Hanover County Department of
Emergency Management
P. O. Box 1525
Wilmington, NC 28402
William H. Crowe, Mayor
City of Southport
201 E. Moore Street
Southport. NC 28461
Distribution w/ encl:
M. Shymlock, Ril
D. Trimble, NRR
J. Lieberman OE
B. Summers. OE
J. Coley, RII'
R. Aiello, RII
J. Lenahan RII
E. Testa, RII
D. Thompson, RII
PUBLIC
NRC Resident Inspector
U.- S. Nuclear Re'gulatory Commission-
8470 River Road. SE
Southport. NC- 28461
UFFICE RII DRP Ell:1N RII:DRP Ril:DRP Ril:CICS , ,, gy
51mTM gQ ,
.
MfWE "EBream "CPetterscri EL ld ,unyieloc* "A5oland *
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DATE- 2/ /95 2/ /95 2/ /95 2/ /95 2/ /95 2/ U /95 7/ /95
wri r TE5 ED TE5 E TEE .L9 TE5 ND TES ND TES 11 0 TE5 NO
OFFICIAL. RECORD COPY DOCL5ENT NAME: Ga\RPS4%BRU\9712DENI.917
.- -. . - -
.
6
CP&L 3
(cc w/ enc 1 cont'd)
Robert P. Gruber
Executive Director
Public Staff NCUC
P. O. Box 295c0
Raleigh, NC 27626-0520
Public Service Commission
State of South Carolina
P. O. Box 11649
Columbia. SC 29211
Jerry W. Jones. Chairman
Brunswick County Board of
Commissioners
P. O. Box 249
Bolivia, NC 28422
Dan E. Summers
Emergency Management Coordinator
New Hanover County Department of
Emergency Management
P. J. Box 1525
Wilmington, NC 28402
William H. Crowe, Mayor
City of Southport
201 E. Moore Street
Southport, NC 28461
Distribution w/ encl: Oh
Wb
M. Shymlock, RII
D. Trimole. NRR
J. Coley, RII
Md . bg gi j %
R. Aiello. RII
J. Lenahan RII
E. Testa. RII
D. Thompson. RII
PUBLIC
NRC Resident Insp ctor
U. S. Nuclear Re ulatory Commission n,
8470 River Road SE V
Southport. NC j28461 8
j g
UFFICE RII DRP Ell:DRP Ril'_DRP Ell:DRP pg
' ' ""E * * * wr (/ IR ) ,
NAK liBream CPatterson 134ecDonald N5hyur16ck g '
DATE 1/ /95 -1/ /95 1/ /95 1/ p(J /95 ' p /95 1/ /95 1/ /95
(IFY7 YE5 N0 YE5 ND YE5 NO YE5 NO (YE5 j NO YE5 NO YES NO
/ OFFICIAL RECORD COPY DOCISIEdI MAE : G:\BRU\9712DEh!,917 \,/ j
.. _ . _ . . . _ _ _ _ _ _ __ _. _ . . . _ _ . . _ . . . _ _ . _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
Jf44-29-1990 10:34 tRC BRUISJ!CK 19104379134 P.01
.
/
!
CPR
i
- (CC W/enCI cont'd)
Robert P. Gruber
- Executive Director
i Public Staff NCUC
i P. O. Box 29520
1
Raleigh NC 27626-0520
t
d
Public Service Comission
l State of South Carolin-
P. O. Box 11649
,
Coluncia. SC 29211
Jerry W. Jones. Cha an
rd of
Brunswick
Comissioners County /
'
F. O. Box 249 /
l
Bolivia. NC 2
Den E. Sume
Emergency Man gement Coordinator
New Hanover nty Department of
' Emergene nap
.'
P. O. kx 5
,
Wtimingt NC 28402
,
W1:11am . Crowe, Mayor '
- C1ty of outhport !
201 E. re Street
Sout . NC 28461
,
,
31Staihutim Wunc1;
i
(, 5 tymioc t. IL
D. Tflable. NRR
J. oley, RIl
R. tello, RII
" J. .enahan, Ril
. E. Testa. RII-
D Thompson, RII
,
LIC
!
,
Resident Inspector
u. S. Nuclear Regulatory Comission
8470 River Road. SE
Southport, NC 28461
.
,m Sh f
i 853545W
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TOTAL P.01
_. . ..
_ __ . _ _ . . . _ . _ . _ _ _ _ _ _ _ . . . . _ _ . _
'
w
,
EVALUATIONS AND CONCLUSION
On December 8, 1998, a Notice of Violation (Notice) was issued for five
violations identified during a routine NRC inspection. Carolina Power & Light
Company (CP&L) responded to the Notice on January 7. 1998. The licensee
admitted Violations A-0. but denied Violation E on the bases that the
- established procedural . controls, training, and qualifications of the security
personnel monitoring the Central Access Point at the time of the events were
adequate to detect unauthorized access into the protected area (PA). The
NRC's evaluations and conclusion regarding the licensee's arguments are as
follows:
Restatement of Violation
Technical Specification 6.8.1.d requires that written procedures shall be
established. implemented, and maintained covering implementation of the
Security Plan.
Physical Security Plan. Revision 1. August 1997, states that a Member of the
Security Force (MSF) located within a bullet resistant structure is
responsible for the final access control function.
Security Instruction. 0S1-05 Security Post Duties. Responsibilities and Patrol
Procedures, defines the responsibilities of the Access Control Person (ACP).
.
Contrary to the above, 0S1-05 failed to adequately define those actions
required for the ACP to control the final access function into the protected
area to prevent unauthorized access. Specifically. no guidance existed for
controlling a condition on October 3 and again on Octobar 7, 1997 wherein the
ACr> failed to lock down the Protected Area turnstiles or remove the second
,
individual from the area during a conditio1 which could have allowed an
unauthorized individual to gain access into the PA.
Summary of Licensee's Pesconse to Violation E
The licensee contends that the procedural controls training, and
qualifications of the security personnel monitoring the Central Access Point
'
(CAP) at the time of the events were adequate to detect unauthorized access
into the protected area, and that the security personnel would have responded
had an attempt been made. The licensee indicated that the procedures
controlling the CAP adequately defined the Final Access Control (FAC)
operator's responsibility in the event an unauthorized individual attem)ted to
gain access. The licensee interviewed the responsible FAC operators, w1o
-
attested that had an individual attempted to gain unauthorized access they
would have locked the full-length turnstiles or requested response from other
MSF. The licensee also credits training provided in November 1996 as
addressing the locking of the full-length turnstile when two individuals were
located between the half-length and full-length turnstiles.
Enclosure
. .. _ _
._
-- . . - - - - . . - - - - - - - - - - . - - -.
,
. o'
i
NRC Evaluation of Licensee's Resoonse
'
The NRC staff has carefully reviewed the licensee's response and determined
that the procedural requirements did not provide adeguate guidance for the
situation observed to prevent unauthorized acces3. Therefore, the Uritten
procedure OSI-5 did not adequately implement this Security Plan access
control function. The licensee's response did not provide any additional
information that changed the significance or validity of the violation.
The licensee maintains that the procedures were adequate and the FAC operators
acted in accordance with those procedures and training provided concerning
'
this type situation.. The NRC does agree that the personnel serving as FAC
operators were qualified to man that station, that training describing this
situation was provided in November 1996, and that 0S1-05 discusses the
'
,
responsibility of PA access control to the FAC operator. However 031-05 did
not contain actions for the FAC operator to intervene when more that one
i individual was in the area between the full-length and the half-length
turnstiles. In addition, the training provided was prior to the completion
and site-wide utilizaticn of the Central Access Point in August 1997 and did
not address this situation for the different configuration of the new access
building, Therefore, considering the failure to address the configuration
change during training and by observations of the situation on October 3, and
- 7.- 1997 the inspector determined the training provided and procedure were not
adequate to address this event.
NRC's review of the subsequent licensee's root cause analysis, the procedure
revised as a result of the situation identified, and the PNSC meeting notes,
'
support a finding that the procedural controls and training at the time of the
event were inadequate. The licensee's Root Cause Condition Report 97-3964.
Plant Access Turnsti a Area, dated January 6, 1998, for this event stated that
,
'the one-half turnsta ies were introduced to enhance access control: however,
this process change was not formally documented in plant procedures Security
personnel instructions or site personnel training guides. Failure to update
these documents prior to introducing the onc-half turnstiles resulted in plant
4
personnel not understanding management ex3ectations." The corrective actions
reviewed by the NRC do not support that t1e procedures or training were.
edequate. Corrective actions for this event included revision of the FAC
operators lesson plan.and additional training on that plan, revision to
051-05, and an evaluation of the need to change the Initial / Retraining program
E to incorporate instructions for half-length turnstiles in the Central Access
Building. . A review of OSI-05 revised January 1998 added unauthorized access
c 'to those situations required for FAC operator action. Additionally, the Root
Cause investigator when questioned by the Brunswick Plant Nuclear Safety
Committee-(PNSC) during the December 18, 1997 meeting stated, as recorded in
the PNSC minutes, that the security guards actions were not "what they were
supposed to have done-their training had not been adequate to have them
-control the situation in the right way."
Enclosure
- _ - -. . .
-
.- - . - - - . . - - - - -= . -.-.. - - . -
,.
.
3
The violation was issued based on inadequacies in a security procedure as
evidenced by observed security personnel performance. The NRC is in agreement
with the licensee that no attempt at unauthorized access was made hv the
individuals observed. The security force had the responsibility tv determine
the individuals authorization prior to the individuals gaining access to the
facility, when confronted with two individuals inappropriately between the
half-length turnstiles and the full-length turnstiles as required by Technical
Specification 6.8.1 of the Security Plan. The NRC ins)ection observed that
neither the applicable procedure nor the training on tie procedure adequately
addressed the actual situation where two individuals were between the
turnstiles. Therefore, the NRC has determined that procedural controls were
not adequate to implement the Security Plan when two individuals were in the
area between the half-length and full-length turnstiles.
NRC Conclusion
For the above reasons, the NRC staff concludes that ',ae violation occurred as
stated.
!
Enclosure
..