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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:NRC TO UTILITY
MONTHYEARML20062G5581990-11-23023 November 1990 Forwards Insp Repts 50-324/90-44 & 50-325/90-44 on 901022- 26.No Violations or Deviations Noted ML20062G3851990-11-19019 November 1990 Forwards Insp Repts 50-324/90-41 & 50-325/90-41 on 901002-1104.Violations Noted ML20058G5671990-11-0808 November 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/90-25 & 50-325/90-25 ML20062D3921990-11-0505 November 1990 Forwards Insp Repts 50-324/90-46 & 50-325/90-46 on 901017.No Violations or Deviations Noted ML20058H4371990-11-0101 November 1990 Forwards Summary of 901016 Enforcement Conference Re Events Surrounding 900819 Unit 2 Reactor Scram ML20058E9681990-10-30030 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/90-29 & 50-325/90-29 ML20058F3061990-10-29029 October 1990 Forwards Insp Repts 50-324/90-42 & 50-325/90-42 on 900924-28.No Violations or Deviations Noted ML20058B0511990-10-18018 October 1990 Forwards Insp Repts 50-324/90-37 & 50-325/90-37 on 900908-1001.Violations Noted ML20058B1141990-10-18018 October 1990 Forwards Insp Repts 50-324/90-32 & 50-325/90-32 on 900806-10.No Violations or Deviations Noted ML20059M7961990-09-20020 September 1990 Ack Receipt of Util 900806 Response & 900629 & 0308 Supplemental Responses to NRC 900308 Notice of Violation ML20059M6391990-09-19019 September 1990 Forwards Augmented Insp Team Insp Repts 50-325/90-36 & 50-324/90-36 on 900821-25 ML20059M1731990-09-13013 September 1990 Forwards Summary of 900806 Meeting in Atlanta,Ga Re Corporate Emergency Preparedness & Recent Drill Performance. List of Attendees & Viewgraphs Encl IR 05000324/19900191990-09-0505 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/90-19 & 50-325/90-19 ML20059M3591990-08-30030 August 1990 Discusses Region II 900808 Review of Emergency Response Facilities Focusing on Availability of Workspace & Communications for NRC Personnel in Event Agency Response Warranted.Summary of Mods/Additions to NRC Resources Encl ML20059H3271990-08-29029 August 1990 Forwards Summary of 900815 Meeting W/Util in Region II Ofc to Discuss Corrective Action Plan Re Requalification Program.List of Attendees Encl ML20059K8291990-08-27027 August 1990 Forwards Insp Repts 50-325/90-31 & 50-324/90-31 on 900730-0803.No Violations or Deviations Noted ML20059D0261990-08-24024 August 1990 Forwards Partially Withheld Safeguards Insp Repts 50-324/90-30 & 50-325/90-30 on 900730-0803.No Violations or Deviations Noted ML20059J0201990-08-24024 August 1990 Forwards Insp Repts 50-324/90-28 & 50-325/90-28 on 900723-27.No Violations or Deviations Noted ML20059H0751990-08-23023 August 1990 Forwards Insp Repts 50-324/90-26 & 50-325/90-26 on 900701-31 & Notice of Violation ML20058Q3961990-08-15015 August 1990 Forwards NRC Operational Evaluation Repts 50-324/OL-90-04 & 50-325/OL-90-04 on 900725 & 26 ML20058Q2231990-08-0303 August 1990 Forwards Corrected Summary Page for Insp Repts 50-324/90-27 & 50-325/90-27,per ML20056A7711990-08-0202 August 1990 Forwards Fr Notice of Withdrawal of 900419 Application to Amend Tech Spec 4.8.1.1.2.d.1 to Allow One Time Only Extension of Surveillances Until 901031 ML20059A7201990-08-0101 August 1990 Forwards Insp Repts 50-325/90-27 & 50-324/90-27 on 900709-12.No Violations or Deviations Noted ML20058L7041990-07-27027 July 1990 Confirms 900806 Mgt Meeting W/Util in Atlanta,Ga to Discuss Recent Significant Potential for Personnel Overexposure ML20056A4871990-07-27027 July 1990 Confirms 900815 Mgt Meeting in Atlanta,Ga to Discuss Issues Re Operator Training Program,Including Root Cause & Corrective Actions,Shortcomings in Root Cause Analysis, Scheduling Future Insps & Integration of Action Plan Items ML20058L7281990-07-26026 July 1990 Forwards Insp Repts 50-324/90-25 & 50-325/90-25 on 900709-13.Violations Noted & Under Consideration for Escalated Enforcement Action ML20058L7381990-07-25025 July 1990 Ack Receipt of 900628 Response to Confirmation of Action Ltr Re Results of Root Cause Analysis for Failures of Requalification Exam & Operational Evaluation & Associated long-term Corrective Action Plan ML20056A9071990-07-17017 July 1990 Forwards Insp Repts 50-324/90-19 & 50-325/90-19 on 900601-30 & Notice of Violation ML20058L7731990-07-16016 July 1990 Forwards Operational Evaluation Repts 50-324/90-03 & 50-325/90-03 on 900609-10.Results of Evaluations Discussed ML20055F6951990-07-13013 July 1990 Advises That Util 900502 Response to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plant' Per 10CFR50.54(f) Meets All Guidance Provided in Generic Ltr ML20055H4291990-07-13013 July 1990 Forwards Insp Repts 50-324/90-22 & 50-325/90-22 on 900611-15.No Violations or Deviations Noted ML20055H4111990-07-11011 July 1990 Forwards Insp Repts 50-324/90-23 & 50-325/90-23 on 900611-15.No Violations or Deviations Noted.Insp Concluded That Adequate Control Over Engineering Work Requests Existed IR 05000324/19900021990-07-11011 July 1990 Documents 900610 Approval for Restart of Plant in Confirmation of Action Ltrs 50-324/90-02 & 50-325/90-02 on 900521 ML20055H4551990-06-28028 June 1990 Confirms 900622 Telcon Scheduling 900823 Mgt Meeting at Plant Site Re Status of Integrated Action Plan & Schedule for Upcoming Unit 1 Refueling Outage ML20055H3861990-06-27027 June 1990 Forwards Insp Repts 50-324/90-21 & 50-325/90-21 on 900521- 25.No Violations or Deviations Noted.Separate Insp to Review Engineering Work Requests Scheduled Due to Concerns Raised in Area IR 05000324/19900141990-06-26026 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.NRC Understands That Supplemental Response Will Be Issued by 900723 Re Improvement of Equipment Anomalies ML20059M8571990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248F1341989-09-28028 September 1989 Forwards Insp Repts 50-324/89-30 & 50-325/89-30 on 890905-08.No Violations or Deviations Noted ML20248C8621989-09-26026 September 1989 Forwards Insp Repts 50-325/89-24 & 50-324/89-24 on 890814-18.No Violations or Deviations Noted.Unresolved Item Noted ML20248C4621989-09-22022 September 1989 Forwards Corrected Pages to Insp Repts 50-324/89-22 & 50-325/89-22 ML20248A9041989-09-22022 September 1989 Forwards Insp Repts 50-324/89-20 & 50-325/89-20 on 890801-31 & Notice of Violation.Particular Attention in Response to Identification of Root Cause of Problem of Similarity to Violation Noted in Notice Forwarded by Requested IR 05000324/19890111989-09-15015 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-324/89-11 & 50-325/89-11 ML20247L1301989-09-14014 September 1989 Forwards Insp Repts 50-324/89-27 & 50-325/89-27 on 890824-25.No Violations or Deviations Noted ML20247K1511989-09-12012 September 1989 Forwards Summary of 890907 Meeting W/Util Re Self Assessment of Plant.Meeting Provided Better Understanding of Actions to Promote Improvement During Stated SALP Period ML20247D7061989-09-0707 September 1989 Forwards Insp Repts 50-324/89-22 & 50-325/89-22 on 890724-28.No Violations or Deviations Noted ML20247C5621989-08-30030 August 1989 Documents Info Received Between Region II & Concerned Individual Re Case RII-89-A-0070.Info Withheld (Ref 10CFR2.790(a)(6) & (7)) ML20247B6071989-08-28028 August 1989 Forwards Insp Repts 50-324/89-14 & 50-325/89-14 on 890622-0731 & Notice of Violation.Unresolved Item Will Be Pursued During Future Insp ML20246D4511989-08-21021 August 1989 Advises That Util Alternate Rod Insertion & Recirculation Pump Trip Sys Design & Conformance to ATWS Rule (10CFR50.62) Basic Requirements & Objectives Not Acceptable ML20246D6661989-08-18018 August 1989 Forwards SER Accepting Design & Installation of Nitrogen Pneumatic Sys at Plant in Response to Generic Ltr 84-09. Both Nitrogen Backup & New full-time Nitrogen Pneumatic Sys Acceptable for Use.Sys Already Installed at Unit 1 ML20246A4261989-08-16016 August 1989 Forwards Insp Repts 50-324/89-23 & 50-325/89-23 on 890803-04.No Violations or Deviations Noted 1990-09-05
[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] |
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!s August 7, 1989 l-Carolina Power'and Light Company ATTN: Mr. Lynn W. Eury Executive Vice President Power Supply
. P. O. Box 1551-
.Raleigh, NC. 27602
- Gentlemen:
SUBJECTi REACTOR OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS
- In antelephoneL conversation between Mr. ' Lou Sossler, Training Supervisor, and Mr. _ Charles' Payne, NRC Region II Operator Licensing Section, arrange-ments _were made for , administration of the . licensing examinations. at the Brunswick Steam Electric Plant; TheE written examinations are. scheduled for the week of November 27, 1989.
The simulator / operating examinations are scheduled fo'r the same week at the Brunswick simulation facility.
In order. for us. to' meet the above schedule, it will be necessary- for the Lfacility to furnish the approved reference material lis'ted in Enclosure 1,
" Reference Material Requirements. for Reactor / Senior Reactor Operator Licensing
- Examination," by September 1,1989. Any delay in receiving approved, properly-bound and~ indexed reference . material, or the submittal of inadequate or incomplete reference material will result in the examinations being rescheduled.
,Mr. Sossler has been advised of our reference material . requirements and the examiners' names and addresses where each set is to be mailed.
The facility management is responsible for providing adequate space and accommodations in order to properly conduct the written examinations.
Enclosure 2, " Requirements - for Administration of Written Examinations,"
describes our requirements for conducting these examinations. Mr. Sossier has also been informed of these requirements.
In addition, to better document simulator examinations, the Chief Examiner will have the facility simulator operator record prespecified plant conditions (i.e., plant pressure, temperature, pressurizer level, etc.), for each simulator scenario. The candidate will be responsible for providing this
- information, along with any appeal of his simulator operating examination.
Therefore, the facility training staff should retain the simulator examination
- scenarioJinformation until all candidates taking the examination have passed the operating examination, accepted the denial of their license, or had their appeals completed.
8908180187 890807 gDR ADOCK0500g4 y2 :
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8E Carolina-Power and Light Company 2. August 7, 1989 Enclosure '3 contains the _ Rules and Guidelines that willIbe in effect during the administration of the written examination. -The facility management is responsible for ensuring that all candidates are aware of these Rules.
All completed reactor operator and senior reactor operator license. application-information should be submitted at least 30 days before the first examination dates so that we will be able to review the training and experience of.the candidates,- process the medical certifications, and prepare final examiner assignments after candidate eligibility has been determined.
- This. request is covered by Office of Management and Budget Clearance Number 3150-0101 which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing,. and mailing the required material. Send comments: regarding. this burden estimate or any other aspect; of
'this collection' of information, including. suggestions for reducing this
' burden, to ' the Records ' and Reports Management Branch, Division oflInformation Support Services, Office of Information Resources Management, U. S. Nuclear
~ Regulatory. Commission, Washingtonm D. C. 20555; and to the Paperwork Reduction
~
Project ~(3150-0101), Office of Management and Budget, Washington, D. C.
20503.
The facility staff review of the written examination will be conducted in accordance . with requirements specified- in Enclosure 4, " Requirements for
- Facility Review of Written Examination." Mr. Sossler has been informed of these requirements.
Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact Mr. Ken Brockman, Chief, Operator Licensing Section 2, at 404/331-5594.
Sincerely, (original signed by K. E. Brockman)
Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines for Written Examinations
- 4. Requirements for Facility Review of Written Examinations cc w/encls: . i L. Sossler, Training Supervisor R. B. Starkey, Manager, Brunswick Nuclear Project State of North Carolina ;
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Carolina Power and Light Company 3 August 7, 1989-l l
- l. bec w/encls:
l E. Tourigny, NRR D.-Verre11i, DRP D. C. Payne, DRS W. Ruland, Brunswick Senior Resident Inspector Document 7Contro17Deskif (~l RII RI 1 RII RII bo h f 1V/
BMichael:btm C ayne KBrdckman TPeebles 8/'/ /89 8/ 9 /89 8/1 /89 j%/1/89
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. ENCLOSURE 1-REFERENCE MATERIAL' REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS- j
- 1. Existing learning objectives, Job Performance . Measures and lesson n plans L(including training manuals,_ plant orientation manual, system
. descriptions, reactor theory, thermodynamics, etc. ).
A copy of. the facility Job and Task Analysis (JTA), specifying the-
. knowledges and abilities ' required of an operator at _the~ facility. Each' particular knowledge and/or ability will include .an importance rating correlating it to ensuring the health and the safety of the public. If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power _ Plant - Operators, NUREG 1122 (1123) will be used to establish content validity for the examination.
g All Job Performance Measures-(JPMs) used to ascertain the competence of L the operators in performing tasks within the control room complex and, as I identifie~d in the facility JTAs,_ outside of the control room, i.e., local
. operations.
Training materials shall include' all substantive written material. used for preparing applicants for initial R0 and SR0 licensing. The written material shall- include learning objectives and the details presented-during lectures, rather than outlines. Training materials shall be identified by plant and unit, bound, and indexed. FAILURE TO PROVIDE COMPLETE, PROPERLY BOUND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL .TO THE PERSON WH0 IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G. ,- VICE PRESIDENT OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Training materials which include the following shall be provided:
System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system.
Complete and operationally useful_ descriptions of all safety-system interactions and, where available, B0P system interactions under emergency and ' abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating procedures.
1 L
Enclosure 1 2
- 2. . Complete Procedure Index (alphabetical by subject).
' 3. All administrative procedures (as applicable to reactor operation or safety).
.4. -All integrated plant procedures (normal or general operating procedures).
- 5. Emergency procedures -(emergency instructions, abnormal or special
- procedures).
- 6. Standing orders (important orders that are safety related and may l~ supersede the regular procedures).
- 7. Fuel-handling and core-loading procedures.
- 8. Annunciator procedures (alarm procedures, including set points).
l' 9. Radiation protection manual (radiation control manual or procedures).
- 10. Emergency plan implementing procedures.
- 11. Technical Specifications.
!- 12. System operating procedures.
- 13. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams.
- 14. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility.
- 15. Questions and answers that the facility licensee has prepared and which may be used in the written or operating examinations.
l 16. The following on the plant reference simulation facility:
1
- a. List of all readily available initialization points.
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i 1
._- . _ _ _ _ _ - - _ - - - _ - - . _ _ _ _ _ _ _ _ ~
_ i> ,,,
- z. ,
ll ' M ' Enclosure 1 '3
- b. List' of all preset' malfunctions; with a clear. identification number.
, , ,The list should include cause and'effect information. Specifically, for each' malfunction,- a concise description of the expected result, or range of. results, that will occur upon implementation should be provided. : Additionally, an indication. of which annunciators are to .
be initially expected should be given.
- c. A description of simulator capabilities .for valves, breakers, indicators,.and alarms.
. d. Where the capability exists, an explanation of the ability to vary the -severity of a particular malfunction should be provided, i.e. ,
ability, to vary the' size of a given LOCA 'or steam leak, or the -
ability to 'cause a slow failure of a component such as a feed pump, turbine generator or major valve (e.g. , drifting shut of a main =
feedwater control valve).
- e. An identification of. modeling conditions / problems that may impact the examination.
.f. Identification of any known Performance Test Failures not yet completed.
- g. Identi"' cation of significant differences between the simulator and the rr twence plant's control room.
- h. Copies of facility generated scenarios that expose the candidates to situations of- degraded pressure control (PWR), degraded he at removal capability (PWR and BWR), and containment challenges (BWR) shall be provided.
- i. Simulator instructors manual.
- j. Description of the scenarios used for the training class (voluntary by licensee).
- 17. Surveillance procedures (procedures that are frequently run, i.e. , weekly or daily).
- 18. Additional material required by the examiners to develop examinations that meet the requirements of these standards and the regulations.
The above reference material should be approved, final issues and should be so marked. If a plant has not finalized some of the material, the Chief Examiner shall verify with the facility that the most complete, up-to-date material is available and that agreement has been reached with the licensee for limiting i
changes before the administration of the examination. All procedures and reference material should be bound with appropriate indexes or tables of contents so that they can be used efficiently. Failure to provide complete, properly bound and indexed plant reference material will result in the material being returned and could result in cancellation or rescheduling of the examinations.
p
d ENCLOSURE 2 l
l REQUIREMENTS FOR_ ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. ' A single room shall be provided for completing the written examination.
The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the written examination. If necessary, the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of the licensee.
- 2. Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. Minimum spacing should be one candidate per table, with a 3-foot space between tables. No wall charts, models, and/or other training materials shall be present in the examination room.
- 3. Suitable arrangements shall be made by the facility if the candidates ere to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above. These arrangements shall be reviewed by the examiner and/or proctor.
- 4. The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination. The facility staff shall then have five working days to provide formal written comments with supporting documentation on the examination and answer key to the Chief Examiner or to the Regional Office Section Chief.
- 5. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each candidate's use ir completing the examination. The examiner shall distribute these pads to the candidates. All reference material needed to complete the examination shall be furnished by the examiner. Candidates can bring pens, pencils, calculators, or slide rules into the examination room, and no other equipment or reference material shall be allowed.
- 6. Only blank ink or dark pencils should be used for writing answers to questions.
- 7. The licensee shall provide one set of steam tables for each applicant.
The examiner shall distribute the steam tables to the applicants. No wall charts, models, and/or other training materials shall be present in the examination room. No other equipment or reference material shall be allowed unless provided by the examiner.
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FR .
ENCLOSURE 3 PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. Check identification badges.
- 2. Pass out examinations and all handouts. Remind applicants not to review examination until instructed to do so.
READ THE FOLLOWING INSTRUCTIONS VERBATIM:
During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.
READ THE FOLLOWING INSTRUCTIONS
- 1. Restroom trips are to be limited and only one applicant at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 2. Use black ink or dark pencil only to facilitate legible reproductions.
- 3. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 4. Fill in the date on the cover sheet of the examination (if necessary).
- 5. You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND 00 NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 6. If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question. DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 7. Print your name in the upper right hand corner of the first page of each )
section of your answer sheets whether you use the examination question pages or separate sheets of paper. Initial each page.
i Enclosure 3 2 1
- 8. Before you turn in your examination, consequently number each answer sheet, including any additional pages inserted when writing your. answers on the examination question page.
- 9. If you are using separate sheets, number each answer as to category and number (i.e., 1.04, 6.10) and skip at least 3 lines between answers to allow space for grading.
- 10. Write "End of Category " at the end of your answers to a category.
- 11. Start each category on a new page.
- 12. Write "Last Page" on the last answer sheet.
- 13. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
- 14. The point value for each question' is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an-indication of the depth of answer required.
- 15. Show all calculations, methods, or assumptions used to obtain an answer.
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
- 17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
- 18. lf ' the intent of a question is unclear, ask questions of the examiner only.
- 19. When turning in your examination, assemble the completed examination with examination questions, examination aids, and answer sheets. In addition, turn in all scrap paper.
- 20. To pass the examination, you must achieve an overall grade of 80 percent or greater and at least 70 percent in each category.
- 21. There is a time limit of (6) hours for completion of the examination (or some other time if less than the full examination is taken).
- 22. When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area while the examination is still in progress, your license may be denied or revoked.
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ENCLOSURE 4
. REQUIREMENTS FOR FACILITY.RnVIEW 0F WRITTEN EXAMINATIONS At' the option of the Chief Examiner, the facility may. review the written'
- l'.
examination up to.-two weeks prior to its administration. This review'may
.take place' at the facility or in the Regional office. The Chief Examiner will coordinate the .. details' of the review with the:-facility.
An.NRC-examiner.'will always be present during the_ review.
L Whenever - this option of_ examination review is utilized, the facility reviewers 'will- sign the following statement prior to being allowed access to the examination. The examination or written notes will not by '
retained by the facility, h
- a. Pre-Examination Security Agreement I agree that I will not knowingly divulge any.
information . concerning the replacement (or _ initial) ' examination
,_ scheduled for to any unauthorized persons. I understand that I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants. scheduled to be' administered the above. replacement (or initial) examination from now until after the examination has been administered. I understand that violation of this security agreement could result in the examination being voided.
Signature /Date In addition, the facility staff reviewers will sign the following statement after the written examination has been administered.
- b. Post-Examination Security Agreement I did not, to the best of my knowledge, divulge any information concerning the written examination administered on to any unauthorized persons. I did not participate in providing any instruction to those reactor operator and senior reactor operator applicants who were administered the examination from the time that I was allowed access to the examination.
Signature /Date
= _ _ _ _ - - - - -
l' Enclosure 4 2 L
- 2. Regardless. of whether the above examination review option is exercised, l immediately following the administration of the written examination, the facility staff shall be provided a marked up copy of the examination and the answer key. The copy of the written examination shall include pen and ink changes made to questions during the examination administration.
If .the facility did not review the examination prior to its administra-tion, they will have five (5) working days from the day _of the written examination to submit formal comments. If the facility reviewed the examination prior to its administration, any additional comments must be given to an examiner prior to his/her leaving the site at the end of the week of the written examination administration. In either case, the comments will be addressed to the responsible Regional Office by the highest level of corporate management for plant operations, e.g. , Vice President for Nuclear Operations. A copy of the submittal will be forwarded to the Chief Examiner, as appropriate. Comments not submitted within the required time frame will be considered for inclusion in the grading process on a case-by-case basis by the Regional Office Section Chief. Should .the comment submittal deadline not be met, a long delay in grading the examinations may occur.
l 3. The following format should be adhered to for submittal of specific comments:
- a. Listing of HRC Question, answer and reference.
- b. Facility comment / recommendation.
- c. Reference (to support facility comment).
l NOTES: 1. No change to the examination will be made without submittal of a reference to support the facility comment. Any supporting documentation that was not previously supplied, should be provided.
- 2. Comments made without a concise facility recommendation will not be addressed.
- 4. A two-hour post examination review may be held at the discretion of the Chief Examir,er. If this review is held, the facility staff should be informed that only written comments that are properly supported will be considered in the grading of the examination.
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