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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
[Table view] |
Text
w MAR 0 i 1986 In Reply Refer To:
Docket: 50-298 Nebraska Public Power District' ATTN: J. ft. Pilant,fianager, Technical Staff-Nuclear Power Group P. O. Box 499 Columbus, Nebraska 68601 Gentlemen:
4 This forwards a copy of a letter from Promatec, dated February 17, 1986, for your information. This letter was a 10 CFR Part 21 report concerning, defective material used in fire stops and may be applicable to the installations in your facility..
Sincerely, Ordinal S!aned By J. E. Gagliardo J. E. Gagliardo, Chief Reactor Projects. Branch
Enclosure:
As stated cc w/ enclosure:
- Guy Horn, Division Manager of Nuclear Operations Cooper Nuclear Station P. O. Box 98 Brownville, Nebraska 68321 Kansas Radiation Control Program Director Nebraska Radiation Control Program Director bec distrib. by RIV:
RPB DR3P Resident Inspector R.-D. Martin, RA Section Chief, RPB/A. RSB R&SPB RIV File RIV:RPB JEGagliardo/lk 9/1/86 8603240010 860307 PDR S
ADOCK 05000298 pop 4g j
\
L
.- v PROGRESSIVE MATERIALS AND TECHNOLOGES. INC.
Q.100.020 February 17, 1986 D$@$b@
U.S. Nuclear Regulatory Comission FEB 19 5 611 Ryan Plaza Drive, Suite 1000 $
_ Arlington, Texas 76011 "
Attention: Mr. Robert Martin Administrator, Region IV
Reference:
10 CFR Part 21 - Notification of Defects Gentlemen:
Pursuant to the provisions of 10 CFR Part 21 - Reporting of Defects and Non-compliance, notification is hereby given of the existense of defective con-duit seals at Waterford 3 and other nuclear generating stations as identified herein. Final information leading to this report was obtained on February 13,1986 at 12:00 p.m. and verbal notification as required by 21.21 (2) was given on February 14, 1986 at 8:36 p.m. to Mr. David Powell, U.S. Nuclear Regulatory Comission, Washington, D.C.
Information contained in this report is based on fire tests performed on two (2) existing seal configurations and subsequent preliminary evaluations con-ducted by B&B PROMATEC, Incorporated and Louisiana Power & Light Company.
l Details are as follows:
1
- (1) PROMATEC conducted a series fire tests on two (2) penetration / conduit l
seal configurations that are presently installed at various nuclear l
generating stations in accordance with the requirements of ASTM E119, 814 and IEEE 634. The initial purpose of the tests was to ascertain the effects " pull rope" extending through conduit seals would have on
! the ability of such seals to perform their intended function. While
" pull rope" was shown not to be a factor in the ability of the seals to perform their intended function during initial tests, both conduit seals failed to perform properly causing the seal configuration them-selves to become suspect.
Additional tests were conducted with the same configurations deleting
" pull ropes" to determine design integrity of the seals. The config-urations and characteristics tested are as shown on attachments 1 l
- i_ g , a d -
'l' f ] y-
-- l "~l '
i P.O. BOX 4672
- HOUSTON, TEXAS 77210 e (713) 690-5240 l ..
Fcrm No: QC-13
, . LETTER OF TRANSMITTAL 03/01/a0 I ,
Rev 1 - 09/01/80
- .: h Rev 2 - 04/01/83 g :-: ('
FEDERAL EXPRESS Rev 3 - 09/25/94 021-052-732 (Ref. QCP 0006)
DEPARTMENT: na/tr TRANSMITTAL NUMBER: 100/928 TO: U.S. Nuclear Reaulatory Commission DATE: 2/18/86 JOB NO: MISC.
611 Ryan Plaza Drive. Suite 1000 RE:
Arlinoton. Tx. 76011 ATTN: Administrator, Region IV-Robert Mart in
. GENTLEMEN:
WE ARE SENDING YOU: (XX ) ATTACHED ( ) UNDER SEPARATE COVER
( ) DRAWINGS ( ) COPY OF LETTER ( ) SPECIFICATIONS
( ) QUALITY ASSURANCE PROGRAM ( ) QUALITY CONTROL PROCEDURES
( ) PRODUCTION PROCEDURES ( ) -
( )
COPIES DATE SERIAL NO. DESCRIPTION l 2 2/18/86 0.100.020 5 oace letter with 3 attih3 _.its l
l l
l-THESE ARE SUBMITTED: ( ) FOR APPROVAL ( ) AS REQUESTED l ( ) FOR REVIEW AND COMMENT (xx ) FOR YOUR USE ( ) RETURNED FOR CORRECTIO RE RKS: / s /
! COPY TO: SIGNED: MIhnr#/i M M/IN4 TITLE: bualityCdrolSeNb-[
~
iiii!!!!!!!!!!p5=:!!!!!!!!!!!!!!;;;;;5:155!!!!!!!!!;;;;;i!!!!!953555!!!!!!!!!!!!!!!!! !!!!!4!!!!!!!!!j;!!!![ji!!!!!!!5!!!!!!!!!!!!!!!!!!!!!!!!:;
l PLEASE NOTE: RETUN YELLOW ACKNOWLEDEENT CCPY TO B&B INSLLATION, INC. Include any Caneents in space provided.
TRANSHITTAL: ( ) COMPLETE ( ) NOT COMPLETE ( ) DISCREPANCIES NOTED BELOW Returned l by:
Title:
Date:
l l
, P.O. BOX 4672, HOUSTON, TEXAS 77210. (713) 690-5240
[ White (Original). Addressee; Yellow - ACKNOWLEDGEENT Return to Sender; Pink - File @DU
.Tu: Administrator, Region lV Q.100.020 from: Randal W. Brown Page 2 of- 5 and 2, and as further described below.
1.0 Test Penetration Characteristics One 8" x 8" blockout and one 8" x 20" blockout in a 12" thick concrete slab with two (2) conduit penetrators as described below and detailed on drawing no. B-519 (attachment 1).
1.1 4" diameter x 27" long steel conduit 1.2 40% actual fill of IEEE 383 rated cables. Cables were a total length of 62" and extended a minimum 36" absve the slab.
1.3 Conduit extended a minimum 1" above the top of the slab-and a minimum 12" into the furnace below the slab. Cable fill and mix within each conduit was similar- to the ANI/
MAERP requirement of one-third 16 CA/2 cond (Representing instrumentation cable), one-third 12 GA/7 cond '(Represen-
-ting control cable),' and one-third 300 MCM/1 cond (Repre -
senting power cable).
2.0 Penetration and Conduit Seal Characteristics 2.1 Materials used in installation consisted of:
2.1.1 Damming and cable separation - Alumina Silica F1--
berous Material (Bulk and Board).-
2.1.2 Penetration and conduit seal - Dow Corning 3-6548 Silicone RTV Foam i
2.2 Penetration and conduit seal configurations were as fol- '
lows:
2.2.1 Configuration 10976.1 - Conduit seal with a minimum i depth of 6" plus 1" damming as measured from tte top of the slab; penetration seal with a minimum depth of 10" plus 1" damming as measured from the top of l the slab.
2.2.2 Configuration 1097b.2 - Conduit seal' with a minimum depth of 6" plus 1" of doming as measured from the top of the al&5; pmtration seal with a 6" depth plus 1" of damming es measured from the top of the slab.
i l-
f To: Administrator, Region IV Q.100.020
, From: Randal W. Brown Page 3 of 5 3.0' Test Characteristics 3.1 Thermocouples were located in accordance with the require-ments of IEEE 634 and ASTM E119 as shown on drawing no.
B-520 (attachment 2).
3.2 The prepared test slab assembly was exposed to the standard time temperature curve established by ASTM E119 for a period of three (3) hours with the following results:
3.2.1 Configuration 1097b.2 - Thermocouple F-19 exceeded the maximum allowable with a temperature of 4010 F at 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 23 minutes and a three (3) hour reading of 6590 F.
3.2.2 - Configuration 1097b.1 - Thermocouple F-25 exceeded the maximum allowable with a temperature of 401o F at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 14 minutes and a three (3) hour reading of 4460 F.
3.3 While no flame through was noted on the unexposed side and hose stream tests did not cause openings, heat transmission as indicated by the field thermocouples exceeded the max-imum temperature requirement of 3250 F above ambient. An autopsy was performed and resulted in 'the discovery that both conduit. seals were reduced to ash.
3.4 Although the affected seals did not meet the full three (3) hour requirement for heat transmission, both configurations are operable up to the time periods referenced in para-graphs 3.2.1 and 3.2.2, respectively.
(2) The requirement to install conduit seals at the fire barrier was in-cluded in design specifications for various stations in order to comply with Branch Technical Position 9.5.1-29 (3). Preliminary investigations by Louisiana Power & Light Company and B&B PROMATEC indicate that the defective configurations are probably of a generic nature affecting an - unspecifit;d number of nuclear generating sta-tions.
The number and locations of all affected stations cannot be deter-mined by Louisiana Power & Light Company or B&B FR0fATEC as various utilities and sec1s contractors'may have design 6d and installed simi-
. lar configurations. Preliminary investigations by Louisiana Power &
Light and B&B PROMATEC has determined that the following stations and
F To: Administrator, Region IV Q.100.020 i From: Randal W. Brown Page 4 of 5 licensees are likely to be affected, as a minimum:
- WATERFORD 3......................... Louisiana Power & Light Co.
- CRAND GULF 1........................ Mississippi Power & Light Co.
- NUCLEAR ONE 1....................... Arkansas Power & Light Co.
- SHEARON HARRIS 1.................... Carolina Power & Light Co.
- WOLF CREEK.......................... Kansas Gas & Electric Co.
- CALLAWAY 1.......................... Union Electric Co.
Various organizations have participated in the design and installa-tion of penetration and conduit seals at the locations identified thus far. Evaluations to determine the number and locations of all defective seals is expected to be an extensive, time consuming opera-tion that would require the collective efforts of all affected orga-nizations. Evaluations are currently in progress by B&B PROMATEC and Louisiana Power & Light for Waterford 3.
(3) Other tests were conducted satisfactorily to provide potential cor-rective actions that may be taken for those seals determined to be unacceptable for the operability time periods previously referenced.
Possible corrective action measure include:
(a) Evaluation of affected conduit seals to determine if exception can be taken to the required three (3) hour rating.
(b) Rework of conduit seals that can not be excepted from a three (3) hour rating by installing:
l (1) Installing a 3" depth silicone RTV foam seal boxed off with 1" alumina silica board at the conduit termination point (attachment 3). This would also require the installation of an additional 6"' depth seal at the nearest accessible point on the continuous run side of the conduit.
I I (2) Installing an additional 6" depth conduit seal at the nearest accessible point on the continuous run side of the conduit.
Due to the apparent generic nature of this condition, it is requested that assistance and/or direction by the NRC t.e given in order that we may proceed in the proper manner.
I
F-To: Administrator, Region IV Q.100.020 8
from: Randal W. Brown Page 5 of 5 Please contact the writer at (713) 690-5240 at you earliest convenience.
~
Sincerly yours,-
PROMATEC andal W. Brown Quality Assurance Mangaer RWB/dmck at tachments: (1) Drawing Number B-519 (2)~ Drawing Number B-520 (3) Drawing Number B-505 cc: R. Block R. Pearson R. Werme G. Burt L. Spriggs B. Collier (LP&L)
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