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Category:CORRESPONDENCE-LETTERS
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 ML20217G1191999-10-0808 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Brunswick NPP & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next Five Months ML20217C6931999-10-0606 October 1999 Forwards Insp Repts 50-324/99-06 & 50-325/99-06 on 990801- 0911 at Brunswick Reactor Facility.No Violations Were Identified BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl ML20211K9001999-08-27027 August 1999 Forwards Insp Repts 50-324/99-05 & 50-325/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl ML20210S9061999-08-11011 August 1999 Informs That GE Document Entitled, Addl Info Regarding 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant ML20210S9121999-08-11011 August 1999 Informs That Document NEDC-31624P,Suppl 2,Rev 6,entitled, Loss-Of-Coolant Accident Analysis Rept for Brunswick Steam Electric Plant Unit 2,Reload 13,Cycle 14 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) ML20210P8221999-08-11011 August 1999 Advises That Info Contained in Which Submitted Document,Prepared by Siemens Power Corp,EMF-2168(P) Rev 0, Marked Proprietary,Will Be Withheld from Public Disclosure, Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20210P9381999-08-10010 August 1999 Forwards SE Accepting Licensee & Suppls & 0517,which Submitted Assessment of Impact on Operation of Unit 1 with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P8911999-08-10010 August 1999 Forwards SE Authorizing Relief Requests CIP-01,02,06,07,08, 09,10,11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Requests CIP-04 & 05 Would Result in Hardship,Relief CIP-03 Not Required & CIP-11 Denied in Part BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 ML20210Q4581999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section to Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit List of Individuals to Take exam,30 Days Before Exam Date ML20210P2031999-08-0505 August 1999 Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2 ML20210N2041999-08-0505 August 1999 Forwards SE Accepting Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46, & Suppl 1 BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld ML20210G2941999-07-28028 July 1999 Discusses Public Meeting Conducted on 990720 to Present Results of Periodic Plant Performance Review for Brunswick Facility for Period of May 1997 to January 1999.List of Attendees Encl BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR ML20210E1181999-07-19019 July 1999 Forwards Insp Repts 50-324/99-04 & 50-325/99-04 on 990509- 0619.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl ML20196H8191999-06-21021 June 1999 Informs That on 980915,Commission Suspended SALP Program for an Interim Period Until NRC Completes Review of Process for Assessing Performance at NPPs ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20196A8111999-06-14014 June 1999 Ack Receipt of 990401 Response to NRC Ltr Issued on 990302 Re OI Investigation to Determine Whether Former BSEP Manager Threatened to Fire Employees Who Brought Safety Concerns to Nrc.Concluded That No Violation Occurred ML20195J1971999-06-14014 June 1999 Advises That GE-NE-523-B13-01920-56,Rev 1,submitted with 990202 Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARBSEP-99-0170, Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6)1999-10-19019 October 1999 Forwards Proprietery Notification of Change in Operator Status.Individual Name,Docket Number,License Number & Effective Date of Expiration,Encl.Proprietary Info Withheld, Per 10CFR2.790(a)(6) BSEP-99-0161, Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V3511999-10-13013 October 1999 Submits Response to NRC RAI Re Relief Request VRR-03.VRR-03 Requested Relief from full-stroke Open Exercise Requirements for Supply Check Valves to air-operated Valves 1(2)-RNA-V313,1(2)-RNA-V314,1(2)-RNA-V350 & 1(2)-RNA-V351 BSEP-99-0114, Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl1999-10-0404 October 1999 Forwards Supplemental Biological Assessment Submitted by CP&L Providing Updated Data for 1998 & 1999. Pictures of Intake Canal at Diversion Structure During High Tide Conditions Also Encl BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)1999-10-0404 October 1999 Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii) BSEP-99-0142, Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-23023 September 1999 Forwards Proprietary Updated List of Home Addresses for Individuals Licensed to Operate CP&L Bsep,Units 1 & 2. Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0158, Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-21021 September 1999 Provides Proprietary Notification of Change in Operator Status.Individual Name,Docket Number,License & Effective Date of Expiration Provided in Encl to Ltr.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0153, Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 19991999-09-14014 September 1999 Forwards Monthly Operating Repts for Brunswick Steam Electric Plant,Units 1 & 2.CP&L Is Submitting Encl Rept of Operating Statistics & SD Experience for Aug 1999 BSEP-99-0147, Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval1999-09-14014 September 1999 Forwards Response to NRC Telcon RAI Re Relief Requests RR-5, 12,13,14,22,23,24 & 25,per Inservice Insp Program for Third 10-yr Interval BSEP-99-0151, Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP1999-09-0808 September 1999 Notifies NRC That Unit 1 Digtial FW Control Sys Upgrade Was Completed on 990831 During Plant Sd.Action Completes Y2K Remediation Activities for BSEP BSEP-99-0150, Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-09-0202 September 1999 Forwards Proprietary Info Re Positive Drug Test for Operator Licensed on CP&L Bsep,Units 1 & 2,in Response to NRC .Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0149, Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld1999-09-0202 September 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Form 398 & NRC Form 396,for Operators Licensed at Plant.Proprietary Encls Withheld BSEP-99-0112, Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl1999-09-0101 September 1999 Forwards Summary of Exam Results for Feedwater Sparger & Nozzle Exams Performed During RFO13.Evaluation of Exam Results Documented in ESR 98-00333, Unit 2 Feedwater Sparger Evaluation Based on B214R1 IVVI Exam Results, Encl BSEP-99-0146, Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl1999-08-26026 August 1999 Forwards Revised EPIPs for Bsep,Units 1 & 2.List of Revised Procedures & Summary of Changes Are Encl BSEP-99-0141, Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-08-25025 August 1999 Forwards Proprietary Info Re Expiration of Operator Licenses SOP-20812-1,OP-20977-1 & OP-21217,per 10CFR50.74(b) Re Notification of Changes in Operator Status.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0148, Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 21999-08-25025 August 1999 Forwards Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept, IAW Section 13.4.2.1 of UFSAR for Brunswick Steam Electric Plant,Units 1 & 2 BSEP-99-0130, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl1999-08-25025 August 1999 Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Iaw 10CFR50.55a(g)(5)(iii) & NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2 & 3 Piping. Regulatory Commitments,Encl BSEP-99-0132, Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl1999-08-20020 August 1999 Requests Delay in Providing Update on Util Intended Actions Re GL 96-06,until 180 Days After NRC Approval of Generic Technical Basis.List of Regulatory Commitments,Encl BSEP-99-0134, Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl1999-08-13013 August 1999 Forwards Monthly Operating Repts for July 1999 for BSEP, Units 1 & 2.Revised Rept for June 1999 for Unit 2,reflecting Info on 990628 Forced Shutdown of Plant,Encl BSEP-99-0128, Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant1999-08-11011 August 1999 Forwards Revised Relief Request RR-17,applicable to Remainder of Third 10-year ISI Program for Plant BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl1999-08-0505 August 1999 Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl BSEP-99-0123, Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 21999-08-0505 August 1999 Forwards Rev 54 to Radiological Emergency Response Plan (RERP) & Revised Epips,Including Re 44 to OPEP-02.1,rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26.Summary of Changes Provided in Encl 2 BSEP-99-0110, Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI1999-08-0505 August 1999 Forwards Rev 0 to ESR 99-00279, B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, IAW Subparagraph IWB-3144(b) of 1989 Edition of ASME B&PV Code, Section XI BSEP-99-0124, Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld1999-07-30030 July 1999 Forwards Proprietary Medical Status Rept & NRC Form 396 for Individual Holding License SOP-20811-1. Proprietary Encls Withheld BSEP-99-0122, Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld1999-07-20020 July 1999 Informs That,Effective 990702,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired Because Individual Employment at BSEP Was Terminated.Proprietary Encl Containing Name,Docket & License Number Withheld BSEP-99-0111, Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR1999-07-19019 July 1999 Forwards New Affidavit Supporting Withholding of Proprietay Info Provided by GE Entitled, Addl Info Re 1.09 Cycle Specific SLMCPR for Brunswick Unit 1 Cycle 12 & Included in Util 980223 LAR BSEP-99-0121, Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant1999-07-19019 July 1999 Submits Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates. Estimates That 14 Submittals Will Be Made During Fy 2000 & Nine Will Be Made During Fy 2001 for Plant ML20209G1081999-07-13013 July 1999 Forwards Radiological Emergency Response Plan & Revised Epips,Including Rev 4 to OPEP-02.1.1 & Rev 7 to OPEP-02.6.26 BSEP-99-0106, Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl1999-06-28028 June 1999 Informs That Units 1 & 2 Odcm,Spec 7.3.10, Gaseous Radwaste Treatment Sys Requires Gaseous Radwaste Treatment Sys to Be in Operation Whenever Main Condenser Air Ejector Sys Is in Operation.Special Rept Encl BSEP-99-0103, Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 11999-06-24024 June 1999 Submits follow-up Info Re Interlaboratory Comparison Program for 1998 Radiological Environ Operating Rept,Suppl 1 BSEP-99-0100, Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results1999-06-23023 June 1999 Forwards Rev 0 to Calculation 2B11-0001, Core Shroud B214R1 Structural Evaluation, Which Provides Evaluation of Unit 2 Core Shroud Insp Results BSEP-99-0105, Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl1999-06-23023 June 1999 Forwards Rev 6 to OPEP-02.6, Severe Weather. Summary of Changes Encl BSEP-99-0091, Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-06-14014 June 1999 Notifies That Operator Licensed on Units 1 & 2,has Been Reassigned to non-licensed Activities & Operator License Considered Expired.Proprietary Info Encl.Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0090, Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 9905141999-06-0909 June 1999 Provides Notification That Data Point D23C0315 Has Been Restored to Original Configuration During RFO on 990514 BSEP-99-0092, Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld1999-06-0808 June 1999 Informs That,Effective 990513,NRC Operator License for Individual Licensed on BSEP Units 1 & 2,expired.Proprietary Encl Containing Name of Individual,Docket Number,License Mumber & Date of Expiration Encl.Proprietary Encl Withheld BSEP-99-0085, Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld1999-05-27027 May 1999 Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld BSEP-99-0078, Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT1999-05-17017 May 1999 Provides Addl Info Re Jet Pump Riser Weld Insp Results,Per 990406 Telcon with NRC Re Effect of worst-case Crack on LPCI Sys Flow & PCT BSEP-99-0080, Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval1999-05-17017 May 1999 Forwards Revs Made to TS Bases Between 980605 & 990507 Without Prior NRC Approval BSEP-99-0083, Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6)1999-05-14014 May 1999 Forwards Two Proprietary License Renewal Applications Consisting of NRC Forms 398 & 396,for Operators Licensed on CP&L Bsep,Units 1 & 2,IAW 10CFR55.57.Proprietary Info Withheld from Public Disclosure IAW 10CFR2.790(a)(6) BSEP-99-0056, Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively1999-05-13013 May 1999 Forwards 1998 Radiological Environ Operating Rept for BSEP, Units 1 & 2. Encl 1 Provides List of Regulatory Commitments.Vols II & Iii,Sample Analysis Data for Jan-June 1998 & Jul-Dec 1998,respectively BSEP-99-0073, Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by1999-05-12012 May 1999 Withdraws Request for Approval of Proposed QAP Change Which Was Submitted by BSEP-99-0062, Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.171999-05-11011 May 1999 Forwards Latest Revs of COLR & Suppl Reload Licensing Rept, for Bsep,Unit 2.Proprietary Rev 6,Suppl 2 to NEDC- 31624P & EMF-2168P,included.Proprietary Encls Withheld, Per 10CFR2.790 & 10CFR9.17 BSEP-99-0079, Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-05-0707 May 1999 Forwards Proprietary One License Renewal Application Consisting of NRC Form 398, Personal Qualification Statement - Licensee & NRC Form 396, Certification Of... Proprietary Info Withheld,Per 10CFR2.790(a)(6) BSEP-99-0066, Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided1999-05-0404 May 1999 Submits Revised Relief Requests Which Provides Alternative to ASME B&PV Code Requirements for Insp of Containments. Revised Copies of Relief Requests CIP-03,CIP-04,CIP-05, CIP-10,CIP-16 & CIP-17 Provided ML20195D6301999-04-30030 April 1999 Forwards Natl Marine Fisheries Svc Biological Opinion Based on Review of Continued Use of Cooling Water Intake Sys at Bsep.Rept Reviews Effects of Activity on Loggerhead,Kemps Ridley,Green,Hawksbill & Leatherback Sea Turtles BSEP-99-0071, Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6)1999-04-27027 April 1999 Forwards Notice of Expiration of Operator License,Per 10CFR50.75(b).Details Withheld Per 10CFR2.790(a)(6) BSEP-99-0069, Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-171999-04-26026 April 1999 Discusses Rev of Relief Request RR-17, Leakage at Bolted Connections, for ISI Program for Third ten-yr Interval.Util & NRC Were Unable to Reach Agreement Re Use of ASME Code Case N-566-1 as Permanent Basis for Relief Request RR-17 BSEP-99-0063, Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link1999-04-21021 April 1999 Notifies NRC of Plans to Install Mod for Bsep,Units 1 & 2 Erds.Physical Computer Sys Changeout Activities Will Temporarily Affect Availability of ERDS Computer Points Via NRC Data Link BSEP-99-0050, Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping,1999-04-0606 April 1999 Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, BSEP-99-0051, Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 21999-04-0101 April 1999 Forwards Response to Ofc of Investigations Rept 2-1998-014 to Support Final Resolution of Allegations.Response in Encl 1 Withheld.Public Version of Response in Encl 2 BSEP-99-0015, Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-03-31031 March 1999 Forwards Response to NRC 981221 RAI Re Cp&Ls Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves 1999-09-08
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Text
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Carolina Power & Light Company .
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Brunswick Nuclear Plant !
P.O. Box 10429 Southport, NC 28461-0429 December 10,1993
.l SERIAL:BSEP 93-0231 10CFR2.201 -
- U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 REPLY TO A NOTICE OF VIOLATION Gentlemen:
On November 4,1993, the Nuclear Regulatory Commission (NRC) issued a Notice of Violation -
for the Brunswick Steam Electric Plant, Units 1 and 2. The basis for the violation is provided in NRC Inspection Report 50-325/93-41 and 50-324/93-41. Carolina Power & Light Company finds the inspection does not contain information of a proprietary nature. Enclosure 1 -
provides Carolina Power & Light Company's response to the Notice of Violation inaccordance with the provisions of 10CFR2.201.
Please refer any questions regarding this submittal to Mr. R. C. Godley at (910) 457-2412.
Very truly yours, fin 0W C. S. Hinnant, Director-Plant Operations Brunswick Nuclear Plant JFM/jfm Enclosures
- 1. Reply to Notice of Violation
- 2. List of Commitments cc: Mr. S. D. Ebneter, Regional Administrator, Region ll Mr. P. D. Milano, NRR Project Manager - Brunswick Units 1 and 2 Mr. R. L. Prevatte, Brunswick NRC Senior Resident inspector 9312150252 931210 PDR ADDCK 05000324 U 0 //'$
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Enclosure List of Regulatory Commitments The following table identifies those actions committed to by Carolina I-. & Light Company in this document. Any other actions discussed in the submittal represent intended or planned actions by Carolina Power & Light Company. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Msnager-Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this document or any associated regulatory commitments.
Commitment
- 1. Revise PMC-02, Receiving, to indicate that documents received, such as vendor field installation procedures, etc. will be reviewed by the M&CS Material Technical group to ensure proper actions, such as storage requirements, are taken.
- 2. Receipt, storage, and maintenance information will be identified and maintained for all inventory items and will include storage requirements. This will enable Materials Control to identify and comply with any special storage requirements.
- 3. Revise PMC-03, Storage, to provide instructions for repressurization of inert gas covers and to clarify requirements for desiccant control
- 4. Revise appropriate procedures to ensure stock items are not removed from the Materials Control database before disposal tags are in place.
- 5. Develop a comprehensive storekeeper training program.
- 6. Revise OP-08, CRD Hydraulic System Operating Procedure, to include guidance on CRD isolation with cooling water in service.
- 7. Revise Special Process Procedure OSPP-HYDRO 500 to include considerations of the system configuration.
- 8. Revise OP-50, Plant Electric System Operating Procedure, to provide appropriate procedural steps to disable the automatic speed demand feature when in UAT Backfeed.
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ENCLOSURE f I
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 and 2 l NRC DOCKET NOS. 50-325 & 50-324 t OPERATING LICENSE NOS. DPR-71 & DPR-62 i REPLY TO NOTICE OF VIOLATION I
, VIOLATION A-t 10CFR 50, Appendix B, Criterion XIII Handling, Storage and Shipping requires that '3 measures be established to control the handling, storage, shipping, cleaning and !
preservatien of material and equipment in accordance with work and inspection [
instructions to prevent damage and deterioration. When necessary for particular j products, special protective environments such as inert gas atmosphere, specific j moisture content levels, and temperature levels shall be specified and provided. j I
- 1. Specification for Procurement of Silicon Dioxide Insulation Cables and >
Connectors, specification No. 113-030, Rev 0, Step 2.10.3 required that I the seller furnish receiving, storage, and handling instructions for l warranties and/or guaranties and to preserve the integrity of the cables !
placed in indoor storage. !
Field Installation Procedure for Local Power Range Monitor (LPRM) Cables,
- FIP-9233, Rev. O, section 4.0 required that end openings for cables be !
capped with halogen free plastic caps, and desiccant be placed on each ;
connector cable end and that cable assembles be sealed in heat scalable l polyethylene bags.
Contrary to the above, on October 5, 1993, several boxes of.LPRM cables in !
different storage containers were stored in polyethylene bags that had i been opened and were not properly resealed. Several of the cables ,.e !
not properly heat sealed prior to shipment from the vendor. In addit h , j desiccant material was not placed in each bag and one cable connector was !
missing an end cap.
- 2. Procurement and Material control Procedure, Storage, OPMC-03, Rev. 16, provides requirements for the storage of safety related and nonsafety-related items. Step 6.10.3, requires that items pressurized with inert gas be monitored each week to ensure that the gas pressure is maintained within specified limits. Step 6.17.1 of OPMC-03 requires that Q listed ,
material designated for QA review or hold be relocated to a designated l area. j Contrary to the above, on October 5, 1993, the inert gas pressures on two i spare electrical penetrations were below the 15 psig posted minimum limit. l The weekly warehouse inspection reports for July, August and September '
1993, revealed that the inert pressure had been below the posted minimum l value for at least this three month period. The inert gas pressures and '
desiccant indicator inspections had not been performed as required during ;
the week of September 13, 1993. Additionally, on October 5, a control rod drive piston rod which was tagged for OA hold had not been placed in a designated storage area. Also, several other control rod drive piston rods were found to have expired desierant indicators.
This is a Severity Level IV violation (Supplement I).
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Violation A - Example 1 Admission or Denial of Violation Carolina Power & Light Company admits this violation.
Reason for Violation This violation occurred because the proper storage requirements for the LPRM cables were not provided to the Materials and Contract Services (M&CS) department. The purchase specification listed storage requirements for " Level C" equipment and required the vendor to furnish any additional receiving, handling, and storage instructions. The purchase specification was sent to the vendor for review and comment. The vendor made no comments related to storage.
Subsequently, the vendor supplied additional storage instructions in the " field installation procedure". The storage requirements provided at that time included requirements for cable end caps, that desiccant be attached to each connector, and that the cables be stored in heat-sealed polyethylene bags. The additional storage requiretaents were received but were not addressed as design requirements and were not included in the purchase order. The material receipt process does not currently include review of field installation procedures. Each CP&L unit has specific procedures that cover their assigned areas; however, there was a.
failure to communicate between the different units regarding the storage requirements.
Corrective Actions Which Have Been Taken and Results Achieved
- 1. The LPRM cables were moved to a temperature / humidity controlled storage area.
-2. An Engineering Evaluation Report was generated . providing disposition instructions to bring cablea currently in storage in compliance with the vendor's field installation procerbire.
- 3. The Engineering /QA approvals were removed from the Materials Control Database for the LPRM cables to prevent future reorders until the database can be revised to incorporate storage requirements from the vendor's field installation procedure.
- 4. A review was performed to identify items which are subject to unique storage requirements and verify the adequacy of storage conditions and acceptability for use.
Corrective Steps Which Will Be Taken to Avoid Further Violations
- 1. Procurement and Materials Control (PMC-02) , Receiving, will be revised to indicate that documents received, such as vendor field installation procedures, etc. will be reviewed by the M&CS Material Technical group to ensure proper actions, such as storage requirements, are taken.-
- 2. Receipt, storage, and maintenance information will be identified and maintained for all inventory items and will include storage requirements.
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This will enable Materials Control to identify and comply with any special storage requirements.
Date When Full Compliance Will Be Achieved Carolina Power & Light is in full compliance. -;
i Violation A - Example 2 {
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Reason for Violation ;
This violation occurred due to inadequate procedures and training. PMC-03, !
Storage, requires that the minimum and maximum pressure limits for storage will i be established by manufacturer specifications or by an engineering evaluation and '
identified on the container or box. The container was posted 15-17 psig but had no identified actions if actual pressure f alls outside that range. . The . procedure instructs the storekeeper to ensure that the gas pressure is maintained within specified limits. There was a lack of a " questioning attitude" among the storekeepers regarding pressure limits and the compensatory actions if _ the >
. pressure falls below the posted minimum. .;
The vendor limit for the electrical penetrations is 62 psig maximum. For long- !
term storage, a pressure of 15-17 psig is suggested, with a repressurization- ;
approximately every 3 months when the pressure has dropped to 5 psig. This information was not indicated on the container and was not accessible to Material t
. Control personnel. ;
1{
PMC-03 requires that items with desiccant indicators shall be monitored each '!
week. Upon subsequent investigation, the weekly inspection was performed for the l week of September 13, 1993. There was a programmatic problem which contributed l to the expired desiccant indicators on the control rod drive piston rods. The -)
items were being prepared for disposition in the inventory reduction program. .j The items had been taken off of the database, but had not been individually ;
marked with "1598 Disposal" tags . When the items were removed from the database, - j the desiccant inspection was not required or performed. There was one piston rod l which had a " Materials Hold" tag attached. The other piston rods could have been !
issued even though they had been removed from the database and had expired l desiccant indicators. The process to dispose of material is inadequate in that i the waterial can be removed from the database, thus eliminating any required i inspections, before the "1598 Disposal" tags, which prevent issuance, are in place.
Corrective Actions Which Have Been Taken and Results Achieved
- 1. The penetrations were evaluated as acceptable by an Engineering Evaluation Report. The minimum or maximum pressure limits had not been exceeded.
- 2. Training was provided to the appropriate M&CS personnel regarding inert gas covers and the requirements to keep the pressure within the specified j limits. '
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- 3. The weekly desiccant inspection form was revised to incorporate _the new )
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Corrective Steps Which Will Be Taken to Avoid Further Violations 1.. PMC-03 will be revised to provide-instructions for re-pressurization of inert gas covers and to clarify requirements for desiccant control. !
- 2. Appropriate procedures will be revised to ensure stock ' items are'not removed from the Materials Control database before disposal tags are in place.
- 3. A comprehensive storekeeper training program will be developed to increase procedural knowledge and stress adherence to procedures.
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Date When Full Comn1 dance Will Be Achieved -
i Carolina Power & Light is in full compliance. ;
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VIOLATION B- '!
i Technical Specification 6.8.1 (a) requires that written procedures shall be established, implemented, and maintained covering the activities referenced in- i Regulatory Guide'1.33, Appendix A, November 1972.
- 1. Regulatory Guide 1.33, Appendix A, Section 1(c) requires procedures for !
control of plant equipment. AI-58, Equipment Clearance Procedure i implements these requirements. Clearance 1-93-2488 was established on i September 3, to isolate and depressurize the Control Rod Drive (CRD) !
Hydraulic Control Units (HCUs) for the 68 control rods withdrawn to ;
f acilitate the shroud inspection. The clearance was to prevent rod motion. l on a scram signal. 3 contrary to the above, the established clearance was inadequate in maintaining the accumulators depressurized, and therefore did not prevent ,
rod motion when a manual scram signal was inserted on September 24, 1993. '
Receipt of this scram signal resulted in 50 of the 68 control rods under clearance inserting into the core.
- 2. Regulatory Guide 1.33, Appendix A, Section 4 (m) requires procedures for l the system line up of the turbine generator system. FP-82236, Steam =
Turbine EHC System Field Line Up Instructions, implements the requirements l for the plant electrical system operating in the backfeed node, j i
Contrary to the above, procedures FP-82236 and 1-OP-50 were inadequate in j that neither procedure provided prerequisite conditions or steps to -
prevent the Group I Isolation Signal which occurred on September 28, 1993, ,
as the result of resetting the turbine trip (while backfeeding via . the .
Unit Auxiliary Transformer) per procedure FP-82236.
This is a Severity Level IV violation (Supplement I).
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RESPONSE TO VIOLATION: l l
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Violation B - Example 1 (
I Admission or Denial of Violation i Carolina Power & Light Company admits this violation. -l f
f Reason for violation j t
This event was due to the failure to properly establish and provide necessary i guidance and precautions for the clearance. At the time of the event, a hydrostatic test of the Scram Discharge Volume (SDV) was about to commence. The >
purpose of this test was to re-establish the operability of the CRD Hydraulic System and allow control of the system to be turned over to Operations. A manual scram was to be inserted as a preliminary step to depressurize the 69 charged HCU [
accumulators and assist in filling the SDV. However, because inspections of_the l core shroud were in progress, the 68 control rods in the outer two rings of the !
core had previously been fully withdrawn and placed under clearance. The 't clearance was prepared to prevent the control rods from moving into the core l while maintaining cooling water to the drive mechanisms for flushing the drive ;
piston seals. I When the clearance was written, it was recognized that some minimal valve leakage past the charging header isolation valves was possible. The Clearance Center {
Senior Reactor Operator believed that the clearance was adequate based on a i verbal understanding that the Technical Support Engineer intended for Operations ,
to keep the water side of the accumulators drained (depressurized); The water [
side of the accumulators were drained, but the nitrogen side was not J depressurized. The water side was verified drained twice per shif t by observing i accumulator pressure was not greater than 955 psig - (accumulator low pressure alarm ' point). The instructions to verify that the ' accumulators were .!
depressurized were poorly communicated and executed. Without being'given the 1 reason for depressurizing ' the HCDs, Operations did not realize that merely keeping the HCUs' pressure below the low pressure alarm setpoint did not meet the intent of the clearance. ,
The vendor instructions discuss HCU isolation with cooling water flow and specifies that the gas side of the accumulators is required to be discharged in '
order to prevent CRD movement in response to a Reactor Protection System (RPS) l signal. The gas side of the accumulators was not bled down because of previous l problems involving the bottoming-out of the accumulator pistons, ALARA concerns, and experiences where this particular lineup was used successfully.
place for the core shroud inspection was deemed appropriate for the CRD system )
test. Management did not adequately address the specific rod configuration or the f act that this test would insert a manual scram and therefore challenge - the clearance that was in place to prevent rod motion. ;
CP&L believes programmatic controls exist to ensure appropriate coordination and evaluation of plant activities. However, the implementation of these processes ,
was less than adequate as described above. !
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- l Corrective Actions Which Have Been Taken and Results Achieved 'l
- 1. The control rods were inspected with no damage found.
- 2. Work Requests / Job Orders were written to repair the charging header !
isolation valves that were identified as leaking by. ,
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- 3. Briefings have been conducted with the Operations shift personnel j detailing the lessons learned from this event and the management 1 expectations. ;
- 4. Individuals involved have been counseled on the need for a questioning attitude and the positive aspects of thorough communications. i
- 5. A letter from the Director, Site Operations to appropriate plant i management concerning the details of this event and the expectations of F plant and work control when recovering from an outage has been issued. ;
Corrective Steps Which Will Be Taken to Avoid Further Violations
- 1. Operations procedure OP-08, Control Rod - Drive (CRD) Hydraulic System i Operating Procedure, will be revised to include guidance on CRD isolation with cooling water in service.
- 2. Special Process Procedure DSPP-HYDRO 500 for the CRD System Scram Discharge l Volume will be revised to include considerations of the system "
configuration.
Date When Full Compliance Will be Achieved /j t
Carolina Power & Light is in full compliance. 'l Violatien B - Example 2 [
t Admission or Denial of Violation Carolina Power & Light Company admits this violation !
i Reason for Violation This event was due to procedural deficiencies. The Unit Auxiliary Transformer [
(UAT) Backfeed procedure does not support maintenance activities requiring ;
movement of the turbine control valves. The main turbine trip is reset several times during an outage to support valve timing and other maintenance activities. .
As long as the main generator Power Circuit Breakers (PCBs) are open, the 1800 i RPM speed select will not be activated. When the unit is being supplied through J a UAT backfeed, the main generator PCBs are closed. With the PCBs closed and the l turbine trip reset, the Electrohydraulic Control System (EHC) will automatically j select a turbine speed of 1800 RPM which will open the turbine control valves.
When the turbine control valves open, the low condenser vacuum Group 1 isolation is enabled.
In previous outages, the unit was normally supplied from the Startup Auxiliary Transformer (SAT) with the main generator PCBs open. The UAT Backfeed procedure was developed to provide an alternate power source if outage work was scheduled 7 of 8
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to be performed on the SAT or the Emergency Diesel Generators. The procedure i enabled the unit to be supplied from offsite power through the main generator _j PCBs and the UAT. When developing the UAT Backfeed procedure, no steps were j included to defeat the auto speed select as the use of the backfeed coincident ;
with the EHC con-rol setup was not expected. l Corrective Actions Which Have Been Taken and Results Achieved ;
l A Caution Tag was placed on the main turbine trip reset switch warning of the- i potential for the Group 1 isolation. j t
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Corrective Steps Which will Be Taken to Avoid Further Violations .l Operating Procedure 50, Plant Electric System Operating Procedure, will be f revised to provide appropriate procedural steps to disable the automatic speed i demand feature when in UAT Backfeed. l t
Date When Full Compliance Will Be Achieved Carolina Power & Light is in full compliance. ,
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