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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N1931999-10-22022 October 1999 Forwards Insp Rept 50-298/99-12 on 990927-30.No Violations Noted.Insp Exam of Activities Under License as They Relate to Emergency Preparedness & to Compliance with Commission Rules & Regulations & with Conditions of License ML20217G8771999-10-14014 October 1999 Forwards Insp Rept 50-298/99-10 on 990920-24.No Violations Noted ML20217G7401999-10-14014 October 1999 Forwards MOR for Sept 1999 for Cooper Nuclear Station. Rept Includes Documentation of Challenges to Safety/Relief Valves,Iaw TS 5.6.4 ML20217C2671999-10-0808 October 1999 Forwards Insp Rept 50-298/99-03 on 990823-27 & 0907-10.No Violations Noted.Purpose of Insp to Ensure That Licensee Had Effective Programs for Identifying,Evaluating & Correcting Problems Which Could Impact Safe Plant Operations ML20212K9661999-09-30030 September 1999 Forwards Safety Evaluation Accepting plant-specific Safety Evaluation Rept for USI A-46 Program Implementation at Cooper Nuclear Station ML20216J1081999-09-28028 September 1999 Ltr Contract:Task Order 048, Cooper Safety Sys Design & Performance Capability Insp, Under Contract NRC-03-98-021 ML20212J5061999-09-27027 September 1999 Forwards Insp Rept 50-298/99-07 on 990718-0828.No Violations Noted.Inspectors Focused on Implementation of Licensee Reactor Safety & Emergency Preparedness Programs ML20212F3641999-09-22022 September 1999 Forwards Insp Rept 50-298/99-09 on 990823-26.No Violations Noted ML20216J8061999-09-20020 September 1999 Forwards Rev 37 to Safeguards Plan,Iaw Provisions of 10CFR50.(p).Rev Withheld,Per 10CFR73.21 ML20212C4921999-09-15015 September 1999 Forwards Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station.Rept Includes Operating Data Rept,Unit SD Rept & Documentation of Challenges to Safety/Relief Valves ML20212A6061999-09-14014 September 1999 Forwards Insp Rept 50-298/99-08 on 9900816-20.No Violations Noted.Insp Focused on Implementation & Effective Performance of Access Authorization/Fitness-for-Duty (Behavior Observation) Program & Access Control of Personnel ML20211N5271999-09-0202 September 1999 Responds to NRC 990823 RAI Re Y2K Readiness at Cooper Nuclear Station,Per GL 98-01,Suppl 1 05000298/LER-1999-006, Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl1999-08-26026 August 1999 Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl ML20211F1311999-08-24024 August 1999 Forwards Rev 1 to Calculation Nedc 97-044, NPSH Margins for RHR & CS Pumps, in Support of 990615 Proposed Amend to DPR-46 Re Containment Overpressure Contribution to ECCS Pumps NPSH Requirements 05000298/LER-1999-003, Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel1999-08-23023 August 1999 Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel ML20211F4661999-08-23023 August 1999 Discusses GL 98-01 Issued by NRC on 980511 & NPPD Responses for Cooper Nuclear Station & 990628 & Results of Visit to Plant on 990811-12.Staff Determined That Integrated Contigency Plan Incomplete & CNS Not Y2K Ready ML20210R0301999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Cooper Nuclear Station,Iaw Guidance Provided by GL 97-02.Rept Also Includes Documentation of Challenges to Srvs,Per TS 5.6.4 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P6761999-08-10010 August 1999 Requests That Following Changes Be Made to Distribution on NRC Correspondence ML20210P6861999-08-0909 August 1999 Forwards Insp Rept 50-298/99-06 on 990530-0717.No Violations Noted.During Insp,Inspectors Identified Two Issues Categorized as Being Low Risk Significance & within Licensee Response Band ML20210N1331999-08-0606 August 1999 Forwards Notice of Withdrawal of Application for Amend to FOL DPR-46.By Ltr Licensee Withdrew Amend Request Which Would Have Revised Usfar to Reflect as-built Configuration of Reactor Bldg Isolation Dampers ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K6071999-08-0202 August 1999 Submits Withdrawal of Proposed License Amend Re Secondary Containment Isolation Description & Refueling Accident Analysis Results ML20210K3811999-08-0202 August 1999 Forwards Listed Info,Which NPPD Believes Demonstrates Ability to Obtain Funds in Amount of $10 Million for Payment of Such Premiums within Specified Three Month Period,Iaw 10CFR140.21 ML20210G5101999-07-28028 July 1999 Forwards fitness-for-duty Program semi-annual Performance Rept for Period of 990101-0630,per Provisions of 10CFR26.71(d) ML20210D2541999-07-21021 July 1999 Forwards Insp Rept 50-298/99-02 on 990628-0702.Purpose of Insp Was Primarily to Evaluate Effectiveness of Licensed Operator Requalification Program.No Violations Were Identified ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20209H8191999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20209E6951999-07-12012 July 1999 Discusses Response to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Recommends Review of New Database Diskettes on Listed Website.Comments Due by 990901 or Data Entered Into Rvid for Plant Will Be Acceptable ML20209D8731999-07-0808 July 1999 Refers to 990707 Meeting Re Licensee Recent Maintenance Program self-assessment.Also Discussed How Licensee Incorporated Assessment Findings Into Rev of Maintenance Performance Improvement Plan.List of Attendees Encl ML20209B7851999-07-0101 July 1999 Forwards Corrected Occupational Radiation Exposure Repts, for Cys 1996 & 1997.Util Stated That Repts Did Not Properly Tabulate Number of Personnel Receiving Exposures Less than 100 Mrem by Work & Job Functions in CY96 & CY97 05000298/LER-1999-005, Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl1999-07-0101 July 1999 Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl ML20196J2471999-06-29029 June 1999 Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps, 05000298/LER-1999-004, Forwards LER 99-004-01.Commitments Made by Util Are Encl1999-06-28028 June 1999 Forwards LER 99-004-01.Commitments Made by Util Are Encl ML20209B5451999-06-28028 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196H0331999-06-24024 June 1999 Informs NRC of Deletion of 1991 Commitment Contained in Ltr Re Feedwater Nozzle Bypass Leakage Monitoring at Plant ML20196F7511999-06-24024 June 1999 Discusses 990622 Meeting with Public at Arbor Manor, Alburn,Ne to Provide Overview of Pilot Insp Program ML20209A7221999-06-23023 June 1999 Submits Revised Pages to Proposed Change to Plant TS Previously Submitted in ,Per 990615 Telcon with NRC ML20196F5331999-06-22022 June 1999 Forwards Examination Summary Rept for FW Nozzle Examinations Performed During 1998 Fall Refueling Outage at Cooper Nuclear Station.Rept Covers Past Examinations Up to & Including 1998 Fall Refueling Outage ML20196B4681999-06-17017 June 1999 Forwards TS Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610.List of Effective Pages for TS Bases, Encl ML20196E1411999-06-16016 June 1999 Forwards Insp Rept 50-298/99-05 on 990502-29.Noncited Violations Identified ML20195H8891999-06-14014 June 1999 Forwards Response to NRC 990315 RAI Re GL 95-07, Pressure Locking & Thermal-Binding of SR Power-Operated Gate Valves, 180-day Response Submitted by District on 960213 ML20195F6171999-06-0909 June 1999 Informs That GE Rept, Matl Presented by GE 970709 Meeting at Cooper Nuclear Power Station Re Replacement of ECCS Pump Suction Strainers Between Nppd,Ge & NRC Staff, Will Be Withheld from Public Disclosure as Requested ML20207G3031999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Rev 24,under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195E2351999-06-0808 June 1999 Forwards Response to NRC 990517 RAI Re Util Proposed Change to TS Re Calibr Frequency of Reactor Recirculation Flow Transmitters Associated with APRM ML20207G4481999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure,Epip 5.7.1, Emergency Classification,Rev 23 C2,under Provisions of 10CFR50,App E,Section V ML20207G3001999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station Ep,Rev 33,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required Based on Determination That EP Effectiveness Not Affected by Changes ML20207G4531999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Revision 25,under Provisions of 10CFR50,App E,Section V ML20207D3811999-05-27027 May 1999 Informs That During Next 6 to 12 Months,Starting 990530,NRC Plans to Conduct Insps Shown in Attached Insp Plan.Insps Include Both Planned Baseline & Supplemental Insps (Formerly Core & Regional Initiative Insps) ML20207A5191999-05-19019 May 1999 Forwards Insp Rept 50-298/99-04 on 990321-0501.Four Violations Identified & Being Treated as non-cited Violations 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARIR 05000298/19900291990-11-0909 November 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/90-29 ML20217A3691990-11-0707 November 1990 Forwards Insp Rept 50-298/90-33 on 900904-1016.Violations Noted But Not Cited ML20058G1461990-11-0505 November 1990 Ack Receipt of Submitting Rev 13 to Emergency Plan.Changes Acceptable for Implementation.Commitment Date for Submission of Changes Is 901031 ML20058H0581990-11-0101 November 1990 Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04 IR 05000298/19900251990-10-16016 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/90-25 ML20059M8751990-10-0202 October 1990 Informs That Util Response to Generic Ltr (GL) 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2, Part 2 'Vendor Interface for Safety-Related Components,' Acceptable ML20059M7391990-09-28028 September 1990 Forwards Sys Entry & Retest Insp Rept 50-298/90-31 on 900910-14 & 17.No Violations or Deviations Noted ML20059M4651990-09-27027 September 1990 Forwards Insp Rept 50-298/90-30 on 900827-31 & Notice of Violation ML20059E2691990-08-31031 August 1990 Forwards Safety Evaluation Granting Licensee 900525 Relief Requests RP-14 & RP-15 for Relief from Requirements to Measure Pump Inlet Pressure & Instrument Ranges, Respectively ML20058P4151990-08-0808 August 1990 Forwards Insp Rept 50-298/90-26 on 900616-0715.No Violations or Deviations Noted ML20056A1701990-07-30030 July 1990 Advises That Written Licensing Exams Scheduled on 901119 & Operating Licensing Exams Scheduled on 901120.Preliminary Applications Should Be Submitted at Least 30 Days Prior to Exam Date to Review Training & Experience of Candidates ML20055J2301990-07-24024 July 1990 Forwards Insp Rept 50-298/90-27 on 900709-13.No Violations or Deviations Noted.Actions Taken Re Previous Insp Findings Examined ML20055G8751990-07-20020 July 1990 Forwards Insp Rept 50-298/90-20 on 900611-15 & 25-29.No Violations or Deviations Noted ML20055G1841990-07-18018 July 1990 Confirms 900720 Mgt Meeting in Region IV Ofc Re Emergency Actions Levels,Annual Exercise & Emergency Preparedness Program Enhancements ML20055E6841990-07-0909 July 1990 Discusses Generic Implications & Resolution of Control Element Assemblies at Plant.Util Should Submit Plans & Justification for Any Continued Use of Old Style Control Element Assemblies Beyond Current Cycle for NRC Review ML20055D9441990-07-0505 July 1990 Forwards Insp Rept 50-298/90-22 on 900516-0615.No Violations or Deviations Noted.Actions Taken W/Regard to Previously Identified Insp Findings Examined IR 05000298/19900121990-06-28028 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/90-12 IR 05000298/19900051990-06-27027 June 1990 Ack Receipt of Informing NRC That Util Evaluated Observation Re Vital Area Key Control,Per Insp Rept 50-298/90-05.Initiatives to Delineate Responsibilities for Vital Key Exchange During Shift Turnover Appropriate ML20055C7741990-06-18018 June 1990 Forwards Insp Rept 50-298/90-18 on 900416-0515.No Violations or Deviations Noted ML20059M9251990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H2791989-10-0606 October 1989 Forwards Comments from Bnwl Re Util Scenario for Exercise Planned on 891025 IR 05000298/19890251989-10-0505 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/89-25 ML20248E8151989-10-0202 October 1989 Confirms 890926 Telcon Re Change of Dates for Maint Team Insp Preparation Meetings from 891023-25 to 891031-1102 ML20247Q6071989-09-21021 September 1989 Forwards Amend 11 to Indemnity Agreement B-57,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, for Signature IR 05000298/19890291989-09-19019 September 1989 Forwards Insp Rept 50-298/89-29 on 890801-31.No Violations Noted IR 05000298/19890161989-09-14014 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/89-16. Implementation of Corrective Actions Will Be Reviewed During Future Insp IR 05000298/19890061989-09-13013 September 1989 Discusses Insp Rept 50-298/89-06 on 890206-10 & Forwards Notice of Violation.Concerns Raised Re Various Failures to Log or Rept Security Incidents.Decision Re Ofc of Investigations Findings Will Be Sent Separately ML20247G8531989-09-12012 September 1989 Forwards Insp Rept 50-298/89-24 on 890731-0804 & Notice of Deviation ML20247D4731989-09-0606 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/89-22 ML20247C0581989-09-0505 September 1989 Forwards Insp Rept 50-298/89-27 on 890821-25.No Violations or Deviations Noted ML20247G8051989-08-30030 August 1989 Forwards Summary of 890712 Meeting W/Util Re SALP for 880201-890415.Util 890811 Response to SALP Also Encl ML20247B3801989-08-30030 August 1989 Summarizes 890818 Region Iv/Senior Util Executives Meeting in Arlinton,Tx Re General Matters on Topics Discussed, Including SALP Process in Region 4.List of Attendees & Agenda Encl ML20246H9501989-08-28028 August 1989 Forwards Insp Rept 50-298/89-26 on 890717-21.No Violations or Deviations Noted ML20246F8171989-08-25025 August 1989 Forwards Insp Rept 50-298/89-30 on 890807-11.Violations Noted,But No Citation Issued ML20246G3201989-08-22022 August 1989 Forwards Insp Rept 50-298/89-25 on 890701-31 & Notice of Deviation ML20246G1341989-08-22022 August 1989 Documents NRC 890810 Meeting W/Licensee,Including H Parris & Staff in Region IV Ofc to Discuss General Issues of Interest to Licensee & Nrc,Region Iv.Topics Covered During Licensee Presentation Described ML20246E1291989-08-21021 August 1989 Forwards Insp Rept 50-298/89-28 on 890731-0804 & Notice of Violation.Response to One of Two Violations Required ML20245K9991989-08-11011 August 1989 Confirms 890808 Conversation in Which Util Agreed to Participate in 891012 NRC Regulatory Impact Survey.Info Re Survey Provided ML20245J7291989-08-0909 August 1989 Advises of Maint Team Insp Scheduled for Wks of 891113-1204, Per 890807 Telcon.Purpose of Meetings Is to Define Scope of Insp,To Discuss Interfaces Between Team & Staff & to Receive Info to Support Badging Team Members for Unescorted Access ML20245H1131989-08-0404 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/89-18 ML20248C2121989-08-0303 August 1989 Ack Receipt of in Response to 890608 Notice of Violation Re Insp Rept 50-298/89-19.Util Basis for Denial of Violation Not Substantiated & NRC Concludes That Violation Did Occur ML20247M1671989-07-27027 July 1989 Forwards Insp Rept 50-298/89-21 on 890626-30.No Violations or Deviations Noted IR 05000298/19880291989-07-27027 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/88-29 ML20236E6561989-07-24024 July 1989 Forwards Insp Rept 50-298/89-23 on 890626-30.No Violations or Deviations Noted ML20247L9501989-07-24024 July 1989 Forwards Insp Rept 50-298/89-22 on 890601-30 & Notice of Violation ML20246M4961989-07-11011 July 1989 Provides Agenda for 890809 Meeting of Senior Util Executives Sponsored by Region IV at Univ of Texas.Recipient Scheduled to co-lead Discussion of SALP Process W/J Milhoan ML20246N2051989-07-10010 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/89-17 ML20246A7091989-06-22022 June 1989 Forwards Insp Rept 50-298/89-18 on 890416-0531 & Notice of Violation.Nrc Considers Inadequate Station Mod Work Instructions Significant.Other Weaknesses in Plant Mod Process Identified in Paragraph 6 in Insp Rept ML20245K5371989-06-22022 June 1989 Forwards NRR Ack Receipt of Petition Filed by Ecology Ctr of Southern California & Stating That Petition Being Treated Under 10CFR2.206 of NRC Regulations ML20245B5591989-06-20020 June 1989 Forwards SALP Board Rept 50-298/89-12 for 880201-890415.NRC Pleased Overall,Although Sys for Identifying to Mgt Areas Where Corrective Actions Needed Should Be Improved 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217N1931999-10-22022 October 1999 Forwards Insp Rept 50-298/99-12 on 990927-30.No Violations Noted.Insp Exam of Activities Under License as They Relate to Emergency Preparedness & to Compliance with Commission Rules & Regulations & with Conditions of License ML20217G8771999-10-14014 October 1999 Forwards Insp Rept 50-298/99-10 on 990920-24.No Violations Noted ML20217C2671999-10-0808 October 1999 Forwards Insp Rept 50-298/99-03 on 990823-27 & 0907-10.No Violations Noted.Purpose of Insp to Ensure That Licensee Had Effective Programs for Identifying,Evaluating & Correcting Problems Which Could Impact Safe Plant Operations ML20212K9661999-09-30030 September 1999 Forwards Safety Evaluation Accepting plant-specific Safety Evaluation Rept for USI A-46 Program Implementation at Cooper Nuclear Station ML20216J1081999-09-28028 September 1999 Ltr Contract:Task Order 048, Cooper Safety Sys Design & Performance Capability Insp, Under Contract NRC-03-98-021 ML20212J5061999-09-27027 September 1999 Forwards Insp Rept 50-298/99-07 on 990718-0828.No Violations Noted.Inspectors Focused on Implementation of Licensee Reactor Safety & Emergency Preparedness Programs ML20212F3641999-09-22022 September 1999 Forwards Insp Rept 50-298/99-09 on 990823-26.No Violations Noted ML20212A6061999-09-14014 September 1999 Forwards Insp Rept 50-298/99-08 on 9900816-20.No Violations Noted.Insp Focused on Implementation & Effective Performance of Access Authorization/Fitness-for-Duty (Behavior Observation) Program & Access Control of Personnel ML20211F4661999-08-23023 August 1999 Discusses GL 98-01 Issued by NRC on 980511 & NPPD Responses for Cooper Nuclear Station & 990628 & Results of Visit to Plant on 990811-12.Staff Determined That Integrated Contigency Plan Incomplete & CNS Not Y2K Ready ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P6861999-08-0909 August 1999 Forwards Insp Rept 50-298/99-06 on 990530-0717.No Violations Noted.During Insp,Inspectors Identified Two Issues Categorized as Being Low Risk Significance & within Licensee Response Band ML20210N1331999-08-0606 August 1999 Forwards Notice of Withdrawal of Application for Amend to FOL DPR-46.By Ltr Licensee Withdrew Amend Request Which Would Have Revised Usfar to Reflect as-built Configuration of Reactor Bldg Isolation Dampers ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210D2541999-07-21021 July 1999 Forwards Insp Rept 50-298/99-02 on 990628-0702.Purpose of Insp Was Primarily to Evaluate Effectiveness of Licensed Operator Requalification Program.No Violations Were Identified ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20209H8191999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20209E6951999-07-12012 July 1999 Discusses Response to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Recommends Review of New Database Diskettes on Listed Website.Comments Due by 990901 or Data Entered Into Rvid for Plant Will Be Acceptable ML20209D8731999-07-0808 July 1999 Refers to 990707 Meeting Re Licensee Recent Maintenance Program self-assessment.Also Discussed How Licensee Incorporated Assessment Findings Into Rev of Maintenance Performance Improvement Plan.List of Attendees Encl ML20196J2471999-06-29029 June 1999 Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps, ML20196F7511999-06-24024 June 1999 Discusses 990622 Meeting with Public at Arbor Manor, Alburn,Ne to Provide Overview of Pilot Insp Program ML20196E1411999-06-16016 June 1999 Forwards Insp Rept 50-298/99-05 on 990502-29.Noncited Violations Identified ML20195F6171999-06-0909 June 1999 Informs That GE Rept, Matl Presented by GE 970709 Meeting at Cooper Nuclear Power Station Re Replacement of ECCS Pump Suction Strainers Between Nppd,Ge & NRC Staff, Will Be Withheld from Public Disclosure as Requested ML20207G3031999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Rev 24,under 10CFR50,App E,Section V Provisions.No Violations Identified ML20207G4481999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure,Epip 5.7.1, Emergency Classification,Rev 23 C2,under Provisions of 10CFR50,App E,Section V ML20207G4531999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Revision 25,under Provisions of 10CFR50,App E,Section V ML20207G3001999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station Ep,Rev 33,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required Based on Determination That EP Effectiveness Not Affected by Changes ML20207D3811999-05-27027 May 1999 Informs That During Next 6 to 12 Months,Starting 990530,NRC Plans to Conduct Insps Shown in Attached Insp Plan.Insps Include Both Planned Baseline & Supplemental Insps (Formerly Core & Regional Initiative Insps) ML20207A5191999-05-19019 May 1999 Forwards Insp Rept 50-298/99-04 on 990321-0501.Four Violations Identified & Being Treated as non-cited Violations ML20206Q6171999-05-17017 May 1999 Forwards RAI Re 990301 & 10 Ltrs Re Proposed TS Changes to Calibr Frequency of Recirculation Flow Transmitters from Once Every 184 Days to Once Every 18 Months.Util Responses Should Be Provided within 30 Days of Ltr Date ML20206P0171999-05-12012 May 1999 Discusses GL 96-05 Issued on 960918 & NPPD Responses Submitted on 961118,970317,980504 & 990222 for Cooper Nuclear Station.Forwards Safety Evaluation Concluding That NPPD Adequately Addressed Actions Requested in GL 96-05 IR 05000298/19980091999-05-12012 May 1999 Refers to Insp Rept 50-298/98-09 Conducted Between 981227-990130.During Insp,Apparent Violation of 10CFR50.50 Identified & Being Treated as non-cited ML20206M1791999-05-11011 May 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328. Reorganization Chart Encl ML20206H4191999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key,Encl for Info.Without Encl ML20206P8961999-05-0707 May 1999 Refers to Meeting Conducted at Region IV Office on 990506 Re Licensee Upcoming Rev to Strategy for Achieving Engineering Excellence & Plans to Achieve Performance Improvements.List of Attendees & Util Presentation,Encl ML20206H7541999-05-0505 May 1999 Forwards Insp Rept 50-298/99-01 on 990207-0320.Violations Being Treated as non-cited Violations ML20205R5541999-04-16016 April 1999 Submits Summary of 990330 Public Meeting in Brownville,Ne to Discuss Results of PPR Completed on 990211,which Allowed for Exchange on New Assessment Process,Current Performance Review & Upcoming Actions Taken in Response to Y2K Concerns IR 05000298/19980221999-03-19019 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/98-22 on 990107.Finds Reply Responsive to Concerns Raised in NOV ML20205E8991999-03-19019 March 1999 Advises of Completion of Plant Performance Review on 990209 to Develop Integrated Understanding of Safety Performance. Overall Performance Was Acceptable.Problems with Communication in CR Resulted in Several Minor Events ML20204D9451999-03-18018 March 1999 Forwards Insp Rept 50-298/98-09 on 981227-990206.Three Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML20207M9591999-03-15015 March 1999 Forwards Request for Addl Info Re Licensee Response to GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20204B6771999-03-15015 March 1999 Submits Withdrawal of Amend Request for Operating License DPR-46.Proposed Change Would Have Modified Facility TSs Pertaining to Neutron Monitoring Neutron Detectors ML20207M9811999-03-15015 March 1999 Advises That Which Withdrew 980415 Amend Request, Being Treated as Withdrawal.Proposed Change Would Have Modified Facility TSs Pertaining to Neutron Monitoring,Flow Biased Rod Block Monitor ML20204B3301999-03-11011 March 1999 Forwards SE Accepting Third 10-year Interval Inservice Insp Program Plan Requests for Relief Numbers RI-13,RI-17 & RI-25 for Plant ML20204B7061999-03-11011 March 1999 Requests Approval of Proposed Operability Criteria for Use in Evaluation & Interim Resolution of Degraded & Nonconforming Conditions with Piping & Pipe Supports at Facility ML20205A5811999-03-0909 March 1999 Forwards Exam Rept 50-298/99-301 for Exam Administered on 990212.Exam Included Evaluation of Four Applicants for Reactor Operator License ML20207K3231999-03-0808 March 1999 Discusses 990224 Meeting Re Staff Critique of Refueling & Equipment Outage RE-18 & Implementation Status of Improvement Strategy for Engineering.List of Attendees & Matl Used in Presentation Encl ML20202G1701999-02-0202 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam at Util Facility on 990407.Authorized Representative from Facility Must Submit Ltr Listing Names of Candidates ML20202E3121999-01-22022 January 1999 Forwards Insp Rept 50-298/98-08 on 981115-1226 & Notice of Violation.First Violation Re Staff Failure to Follow Procedures (Two in Operations,One in Maint & One in Plant Support) ML20199G6041999-01-19019 January 1999 Informs That Effective 990118,JN Donohew Has Assumed NRC Project Mgt Responsibility for Cooper Nuclear Station ML20199E1521999-01-0707 January 1999 Forwards Insp Rept 50-298/98-22 on 981116-1208 & Notice of Violation Re Lack of Effective Oversight by Plant Mgt 1999-09-30
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NOV 161987 l In Reply Refer To Docket: 50-298 Nebraska Public Power District ATTN: George A. Trevors Division Manager - Nuclear Support P. O. Box 499 l Columbus, Nebraska 68601 Gentlemen: J
SUBJECT:
OPERATOR LICENSING EXAMINATIONS AT COOPER NUCLEAR STATION (CNS) l In a telephone conversation between Messrs. Guy Reese, Training Coordinator, i CNS and David Graves, NRC Operator Licensing Examiner, arrangements were made l for the administration of operator license examinations at the Cooper Nuclear '
Station.
The written examination is scheduled for February 16, 1988. The operating examinations are scheduled for February 17-19, 1988. )
In order for the NRC to meet the above schedule, it will be necessary for the facility licensee to furnish the approved reference material listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," by August 10, 1987. However, the Region IV )
Operator Licensing Section maintains a set of CNS reference material in the J regional office. Therefore, only timely corrections are necessary to avoid any '
delay in administering the examinations. Examinations are scheduled far in advance with considerable planning to utilize limited examiner manpower and to meet the examination dates requested by the various facility licensees. 1 Failure to maintain this material current, may result in a long delay because j it may not be possible to reschedule' examinations for other facility licensees. <
Mr. Reese has been advised of our reference material requirements and the '
distribution of any additional material needed to support examination development. ;
The facility licensee management is responsible for providing adequate space and accommodations in order to properly conduct the written examinations.
Enclosure 2, " Administration of Reactor / Senior Reactor Operator Licensing Written Examinations," describes NRC requirements for conducting these examinations. Mr. Reese has also been informed of these requirements. l I
The facility licensee staff review of the written examination will be conducted 1 in accordance with the specifications in Enclosure 3, " Requirements for {
Facility Review of Written Examination." Mr. Reese' has been informed of these requirements. {
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.. , i Nebraska Public Power District l
Preliminary copies of all reactor / senior reactor operator license applications should normally be submitted at least 60 days before the scheduled examination date so that the NRC will be able to review the training and experience of the candidates, process medical certifications, and issue examiner assignments. If the preliminary copies of the applications are not received at least 30 days before the examination date, it is likely that a postponement will be necessary. When ALL training and qualification requirements have been met by !
the candidates scheduled for the current license examination, final applica- '
tions with all required signatures must be received by the Chief of the Operator Licensing Section not less than 1 week before the scheduled examination date. Significant differences between the preliminary and final applications may result in a candidate being removed from the examination.
This request for information was approved by the Office of Management and Budget under Clearance No. 3150-0101, which expires May 31, 1989. Comments j on burden and duplication may be directed to the Office of Management and l Budget, Reports Management Room 3208, New Executive Office Building, ;
Washington, DC 20503. l i
Thank you for your consideration in this matter. If you have any questions j regarding the examination procedures and requirements, please contact Messrs. David Graves, Chief Examiner at (817)860-8168 or John Pellet, Chief, Operator Licensing Section at (817)860-8147.
Sincerely.
Original Signed By, '
A. B. Beacli t,
L. J. Callan, Director Division of Reactor Projects
Enclosures:
As Stated )
cc w/ enclosures:
Cooper Nuclear Station ATTN: Guy Horn, Division Manager of Nuclear Operations ,
P. O. Box 98 l Brownville, Nebraska 68321 l 1
Cooper Nuclear Station l ATTH: J. Dutton, Traininn Manager P. O. Box 98 l Brownville, Nebraska 68321 Kansas Radiation Control Progran Director Nebraska Radiation Control Program Director i
bcc: (see next page)
I E__._____ _ _ _ _ _ _ _
Nebraska Public Power District bec to DMB (IE42)-
bec distrib. by RIV:
DRP/C DRP .
RRI R. D. Martin, RA SectionChief-(DRP/C) Lisa Shea, RM/ALF RPSB-DRSS MIS System RIV File Project Engineer DRP/C RSTS Operator '
W. Long, NRR Project Manager R. Hall DRS TSS J. Pellet D. Graves i________..
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1 ENCLOSURE-1 -
REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR: ;
OPERATOR LICENSING EXAMINATIONS j
- 1. Existing learning objectives and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics,etc.). q Training materials should include all substantive written material used for preparing candidates for initial R0 and SRO licensing. The written material should be inclusive of learning objectives and the details presented during lecture, rather than outlines. Training materials should be identified by plant and unit, bound, and indexed. Failure to provide complete, properly bound, and indexed reference material will result in canceling and rescheduling of the' examinations. Training materials which include the following.should be provided: -
o 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.
o Complete and operationally useful descriptions of all safety system interactions and, where available, BOP system interactions under a emergency and abnormal conditions, including consequences of i anticipated operator error, maintenance error, and equipment failure. j o Training material used to clarify and strengthen understanding of emergency operating procedures. l l
o Comprehensive theory material that includes fundamentals in the areas :
of theory of reactor operation, thermodynamics, heat transfer, and )
fluid flow, as well as specific applications to actual in-plant ;
components. For example, mechanical theory material should include j pump theory, as well as descriptions of how these principles actually :
apply to major plant pumps and the system in which they are installed (i.e., reactor coolant pumps, all ECCS pumps, recirculation pumps, and feedwater and emergency feedwater pumps). Reactor theory material should include descriptions that draw explicit ties between the fundamental and actual operating limits followed in the plant (e.g.,
reactor theory material should contain explanations on how principles '
relate to the actual curves used by operators to verify shutdown margin or calculating an ECP).
- 2. Procedure Index (alphabetical by subject).
- 3. All administrative procedures (as applicable to reactor operation or safety). <
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- 4. All integrated plant procedures.(normal or general operating procedures).
- 5. Emergency rocedures (emergency. instructions, abnormal, or special procedures .
- 6. Standing orders (important orders that are safety-related and may j supersede the regular procedures).
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- 7. Fuel handling and core-loading procedures (initial core-loading procedure,whenappropriate).
- 8. Annunciator procedures (alarm procedures, including set points).
- 9. Radiation protection manual (radiation protection 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 I flow diagrams, f
- 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 (voluntary by facility licensee).
- 16. The following on the plant reference simulation facility:
- a. List of all readily available initialization points.
- b. List of all preset malfunctions with a clear identification number.
The list should include cause and effect information. Specifically, I for each malfunction, a concise description of the expected result, or range of results, that will occur on implementation should be l provided. Additionally, an indication of which annunciators'are to l be initially expected should be given..
- c. A description of simulator failure capabilities for. valves, breakers, indicators, and alarms. 4
- d. Where the capability exists, an explanation of the ability to vary the severity of a particular malfunction should be provided, i.e.,
the 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 1 feedwater control valve).
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- e. An indication of modeling conditions or problems that may impact the examination.
- f. Identification of unknown performance test failures not yet completed.
- g. Identification of significant differences between the simulator and the control room,
- h. Copies of facility licensee generated scenarios that expose the ,
candidates to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR), and containment challenges (BWR) may be provided (voluntary by facility licensee).
- i. Simulator instructors manual (voluntary by facility licensee).
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- j. Description of the scenarios used for the training class (voluntary by facility licensee). ,
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- 17. Additional material required by the examiners to develop examinations that meet the requirements of these standards and regulations.
The above reference material should be approved, final issues and so marked.
If a plant has not finalized some of the material, the chief examiner is responsible for ensuring that the most complete, up-to-date material is available and that agreement has been reached with the facility _ licensee for j limiting changes before the administration of the examination. .All procedures !
and reference material should be bound or.IN THE FORM USED BY THE CONTROL ROOM l OPERATORS, WITH appropriate INDEXES or TABLES OF CONTENTS so that they can be l used efficiently.
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ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS l
- 1. A single room shall be provided for completing the written examination.. ~]
The location of this room and supporting rest room facilities. shall be l such as to prevent contact with all other facility licensee and/or j contractor personnel during the duration of the written examination. If !
necessary, the facility licensee should make ' arrangements for use of a i suitable room at a local school, motel, or other building. Obteining this i room is the responsibility of the facility licensee, i '
- 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 y training materials shall be present in the examination room.
- 3. Suitable arrangements shall be made by the facility licensee if the candidates are to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above. These arrangements shall be reviewed by the chief examiner and/or proctor.
- 4. The facility licensee shall provide pads of 8 1/2- by 11-inch, lined paper in unopened packages for each candidate's use in completing the. examination.
The examiner shall distribute these pads to the candidates. 'The facility licensee shall provide unmarked steam tables for candidate use as requested by the chief examiner. When requested by the chief examiner, the facility licensee shall also prepare copies of large documents (i.e.,
Technical Specifications, Emergency Plan Implementing Procedures, l Emergency Operating Procedures, etc.) for use by the candidates. Such requests will normally be made known to the facility' licensee the working day prior to the written examination. All other reference material _ needed to complete the examination shall be furnished by the examiner. Candidates ,
may bring pens, pencils, nonprogrammable calculators, or slide rules into I the examination room. No other equipment or reference material shall be allowed.
- 5. Only black ink or dark pencils should be used for writing answers to questions.
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ENCLOSURE 3 REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS .
1
- 1. There shall be no review of the' written examination by the facility licensee staff before or during the administration of.the examination.
Following the administration of the written examination, the facility ,
licensee staff shall be provided a marked-up copy of the examination and !
the answer key. 1 j
- 2. The facility licensee will have'five (5) working days from.the day the written examination is given to submit formal comments. The formal comments will be approved by the highest level of corporate management for !
plant operations, e.g., Vice President for Nuclear Operations, and 1 submitted to the Region IV office with a copy to the Section Chief for !
Operator Licensing. Comments not submitted within five (5) working days ,
I will be. incorporated into the grading process on a case-by-case basis as l l determined by the Section Chief. No grading will be done until the formal l comments are received and resolved. If the formal comments are not received by the deadline, the final examination results may be delayed- l several weeks since the grading may have to be rescheduled in a later time j slot. !
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- 3. The following information shall be provided for each individual comment: )
- a. NRC question number
- b. Facility licensee comment
- c. Copy of supporting documentation (the reference may be cited if the document is held by the Operator Licensing Section) .l NOTES: 1. No change to the examination will be made without submittal ,
of, or proper reference to, complete, current, and approved I reference material. I
- 2. Comments made without a clear, concise facility-licensee recommendation will not be addressed. '
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