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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 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 ML20246G3201989-08-22022 August 1989 Forwards Insp Rept 50-298/89-25 on 890701-31 & Notice of Deviation 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 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 ML20247M1671989-07-27027 July 1989 Forwards Insp Rept 50-298/89-21 on 890626-30.No Violations or Deviations Noted 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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Docket No. 50-298 June 20, 1986 Mr. J. M. Pilant Technical Staff Manager Nuclear Power Group Nebraska Public Power District Post Office Box 499 Columbus, Nebraska 68601
Dear Mr. Pflant:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) PROCEDURES GENERATION PACKAGE Re: Cooper Nuclear Station By letter dated June 29, 1984, you submitted the Procedures Generation Package (PGP) for Cooper Nuclear Station. Our contractor, Battelle Pacific Northwest Laboratories (PNL), and the NRC staff have reviewed your submittal. The review was performed in accordance with Section 13.5.2 of the Standard Review Plan.
In order to complete our review, we need additional information as described in the enclosure. Please respond within 60 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
/S/
William 0. Long, Project Manager BWR Project Directorate #2 Division of BWR Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page Distribution: VBenaroya
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Mr. J. M. Pflant Nebraska Pt.blic Power District Cooper Nuclear Station cc:
Mr. G. D. Watson, . General Counsel Nebraska Putilic Power District P. O. Box 4999 Columbus, Nebraska 68601 Mr. Arthur C. Gehr. Attorney Snell & Wilmer 3100 Valley Center Phoenix, Arizona 85073 Cooper Nuclear Station -
ATTN: Mr. Paul Thomason, Division Manager of Nuclear Operations P. O. Box 98 Brownville, Nebraska 68321 Director Nebraska Department of Environmental
-. Control P. O. Box 94877 State House Station Lincoln, Nebraska 68509 Mr. William Siebert, Comissioner Nemaha County Board of Comissioners Nemaha County Courthouse
!' Auburn, Nebraska 68305 t
! Resident Inspector i U.S. Nuclear Regulatory Comis.iion
- Brownville, Nebraska 68321 I
Regional Administrator, Region IV
, . U.S. Nuclear Regulatory Comission l 611 Ryan Plaza Drive Suite 1000
- j Arlington, Texas 76011 9' H. Ellis Simons, Director
, Division of Radiological Health Department of Health 301 Centennial Mall, South P. O. Box 95007 Lincoln, Nebraska 68509
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\*.../ REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE PROCEDURES GENERATION PACKAGE (PGP)
NEBRASKA PUBLIC POWER DISTRICT (NPPD)
COOPER NUCLEAR STATION DOCKET NO. 50-298 The Cooper Nuclear Station (CNS) Procedures Generation Package (PGP) submitted by letter dated June 29, 1984 from J. M. Pflant to D. G. Eisenhut was reviewed by our contractor, Pacific Northwest Laboratories (PNL).
Based on our review and on PNL's Technical Evaluation Report (TER) we have determined that the following information is needed to complete our review. The infor.ut'.on should be provided as a revision to the PGP.
1.0 PLANT SPECIFIC TECHh! CAL GUIDELINES (P-STG)
I The P-STG program was reviewed to determine if it contained acceptable methods for meeting the criteria of the Standard Review Plan (SRP),
NUREG-0800, Section 13.5.2 Appendix A, Subsection 3.0. Our review identifies the need for additional information in the following areas:
1,1 Emergency Containment Venting The BWROG EPGs call for emergency containment venting as the last step in
- a sequence of procedural steps involving operator actions designed to reduce primary containment pressure. The staff in its Safety Evaluation dated November 23, 1983, of the BWROG EPGs addressing this issue l , identified the need for additional analysis. Specifically, the criteria -
for defining primary containment venting pressure needs to be established.
In the interim, the staff proposed a limit of twice the design pressure
( for venting, subject to a plant-unique analysis to demonstrate containment l integrity. Therefore, provide the following additional information relevant to the emergency containment venting for our review:
(a) Identify the bases for selecting the primary containment venting pressure limit.
, (b) A rapid containment depressurization from venting may result in l' suppression pool flashing and hydrodynamic loads. Provide the analyses performed to determine if the resulting hydrodynamic loads j would exceed the design capability of the suppression pool.
l (c) Identify and provide the bases for all venting flow paths to be used,
! and consider setting priorities for the selected emergency vent paths to minimize radioactive release rates, L
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(d) Since the use of any vent path in the E0P is for an action beyond design-basis events, provide a best estimate evaluation of the remote manual or automatic vent path valve operability (i.e., capability to open and reclose consistent with the selected venting pressure limit).
(e) Provide the analyses performed to demonstrate the effect of containment venting on ductwork failure (if used as a pathway) and the resulting consequence of subjecting equipment near the failed duct to the steam / radiation environment.
1.2 Documentation of Deviations from BWROG PGP, Revision 3 Identify and document the deviations (or additions) from Revision 3 of the BWROG EPG and provide an analysis or technical justification for the deviations and additions that have safety significance. The documentation of the deviations and additions should be performed and included as part of the PGP. Also, all plant specific values that are required in Revision 3 of the BWROG EPG should be provided in the CNS PGP.
1.3 Combustible Gas Control
) Combustible gas control guidelines were not addressed in the BWROG EPGs,
. which you referenced in the Procedures Generation Package for Cooper.
Therefore, discuss your approach in developing plant specific E0Ps for combustible gas control.
2.0 PLANT SPECIFIC WRITER'S GUIDE (P-SWG)
The Plant Specific Writer's Guide (P-SWG) was reviewed to determine if it described acceptable methods for meeting the criteria of the Standard
. Review Plan (SRP) Section 13.5.2, Appendix A, Subsection 4.0. Our review identified the need for additional information in the following areas:
2.1 Control Room Staffing and Division of Responsibilities As Is Applies
- To the Use of E0Ps To minimize confusion, delay, and errors in the execution of E0P steps,
- the following concerns should be addressed in the P-SWG (See NUREG-0899, l Section 5.8, for additional guidance):
(a) E0Ps should be structured so that they can be executed by the l minimum shift staff and the minimum control room staffing required I
by the Technical Specifications.
(b) Instructions for structuring the E0Ps should be consistent with the roles and responsibilities of the operators.
(c) Action steps should be structured so as to minimize movement of personnel (carrying out actions at the same locations at the same l time) around the control room while carrying out procedural steps.
(d) Action steps should be structured to avoid unintentional duplication of tasks.
2.2 Section 2.4.b Procedure Revisions Page 2 of the P-SWG states that revisions to the E0Ps will be made in accordance with the P-SWG and Administrative Procedure 1.3. The PGP or the Administrative Procedure 1.3 should state that E0Ps will be revised i ' due to design changes, changes to the Technical Specifications, changes to other procedures referenced by the E0Ps, or changes to the control room.
See NUREG-0899, Section 6.2.4, for additional guidance.
2.3 Section 7 Reproduction E0P reproduction is discussed in Section 7, on page 30 of the P-SWG.
However, since all copies of the E0Ps must be clearly legible, the quality of the reproduced copies of the E0Ps should elso be addressed in the writer's guide. See NUREG-0899, Section 6.2.2 for additional guidance.
2.4 Section 6.2 Page Arrangement For readability, especially to the plant operating staff, it is important that page margins are sufficient for reproduction and binding. Therefore, you should consider addressing margin size in Section 6.2, on page 24 of the P-SWG.
2.5 List of Effective Page Revisions Page ii, " List of Effective Page Revisions", lists pages iii, 43 and 44 as Rev. O, while on the actual pages they are listed as different revisions. Please correct these discrepancies.
3.0 VERIFICATION AND VALIDATION PkOGRAM The description of the Verification and Validation Program was reviewed to determine if it described acceptable methods for meeting the criteria of SRP Section 13.5.2, Appendix A, Subsection 5.0 and Subsections 3.3.3 and
- 3.3.4. Our review identified the need for additional information in the following areas:
3.1 E0P Verification and Validation Programs Discuss how the deviations from and additions to the EPGs (that are of l safety significance) are to be verified and validated. This is needed to determine whether the E0Ps are technically correct. See SRP Section 5.3.1.1 for additional guidance.
3.2 Items to be Verified and Validated
. The PGP should describe the specific items (i.e., provide checklists) that are to be verified and validated. This should include appropriate l items from both the P-STG and the writer's guide. See SRP Section 5.3.1 for additional guidance.
3.3 Identification of participants in Verification and Validation Programs The E0P verification program states that independent engineering organization verification and human factors review are a part of the verification process.
Procedure writers and operations personnel should also be included as members of the verification team. The criteria for selection of these individuals and the roles and responsibilities of these individuals should also be specified. See SRP Sections 5.3.2 and 5.3.3 for additional guidance.
3.4 Use of Scenarios The CNS validation program states that "the team will select and develop scenarios which best exercise each E0P." The validation program should be expanded to include a description of the criteria that will be used to select the scenarios to be run during the validation process. The criteria should be developed on the basis of what is needed to validate the procedures and should ensure that single, sequential, and concurrent failures are included. See SRP Section 5.3.4 for further guidance.
3.5 Simulator Verification and Validation For the parts of the E0Ps that cannot be validated on the simulator, the
. criteria for selecting any additional validation that may be needed and the methods to be used, such as a control room walk-through or a mock-up walk-through, should be described. See SRP Section 5.3.5 for further guidance.
3.6 Plan for Correcting and Revising E0Ps The verification and validation program should include the criteria or methods that will be used for determining the need to reverify and
, revalidate any changes in the E0Ps, resultant from either the verification and validation program or from subsequent E0P revisions.
3.7 Compatibility of E0Ps With Minimum Staffing f
l The E0Ps will require a certain number of operators to carry out the various activities and steps as specified. The verification and validation program should indicate that the E0Ps will be exercised, during simulator exercises or control room walk-throughs, with the minimum control room staff size required by the facility Technical Specifications.
3.8 Correspondence Between E0Ps and Instrumentation and Controls The verification and validation program must determine if the instruments and controls are the ones that are referred to in the E0Ps, are available in the control room and are adequate. A discussion of this should be included in the PGP.
l 3.9 Control Room Operator Information and Control Needs The PGP should describe an adequate method to identify plant-specific information and control needs to be used as a basis for performing the tasks specified in the technical guidelines. The description should l
i
. include a discussion of the process used to identify plant-specific parameters and other plant-specific information and control capability needs and describe how the characteristics of needed instruments and controls will be determined. These processes can be described in the detailed CRDR Program Plan.
4.0 TRAINING PROGRAM The description of the Training Program was reviewed to' determine if it i described acceptable methods for meeting the criteria of SRP Section 13.5.2 Appendix A. Subsection 6.0. Our review identified the need for further information in the following areas:
4.1 Use of Simulator Exercises Although the PGP states that a generic simulator will be used for operator training, the training program description should be expanded to address the following items:
(a) Discuss the method to be used to train the operators in areas where the simulator is not like the control room or does not react like the plant. For the parts of the E0Ps that cannot be run on the simulator, the PGP should describe the method that will be used to cover areas missed in the simulator exercises. See SRP Section 6.3.2 for additional guidance.
(b) Indicate the use of a wide variety of scenarios, including multiple (simultaneous and sequential) failures, to fully exercise the E0Ps on the simulator and thus expose the operators to a wide variety of E0P uses. See SRP Section 6.3.2.5 for additional guidance.
4.2 Use of Control Room Walk-throughs Although the PGP. states tnat walk-throughs will be used for operator training, the trainin the following items (g program See SRP Section description 6.3.3 for should be expanded additional guidance):to address (a) Discuss the extent that the E0Ps will be covered by all operators, particularly if walk-throughs will be used to train aspects of E0Ps not taught in the simulator.
(b) Indicate the use of a wide variety of scenarios to fully exercise the E0Ps during the walk-throughs.
4.3 Indication That All Operators Will Be Trained The PGP should include a commitment to train all operators on all E0Ps prior to E0P implementation. See SRP Section 6.4 for additional guidance.
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4.4 Indication That Operators Will Be Evaluated The training program states that further training needs wi'l be determined from the operators' performance. The PGP should state that operators' knowledge of and performance on the use of the E0Ps will be evaluated during and after initial training, during training on revisions to the E0Ps, and during refresher training. See SRP Section 6.5 for additional guidance.
4.5 Training Program Description The PGP notes that problems with the E0Ps may be detected during training or retraining programs. The PGP should state the process by which NPPD plans to deal with any discrepancies discovered during the implementation of the training program. The changes made as a result of any discrepancies should be revalidated and reverified.
4.6 Use of Classroom Instruction The training program states that if operational considerations do not allow control room walk-throughs and a simulator is not available, training on major revisions will be conducted during classroom instruction. Therefore, provide a basis to justify that classroom instruction will provide an acceptable level of training on major revisions. ,
a