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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:INCOMING CORRESPONDENCE
MONTHYEARML20217G7401999-10-14014 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 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 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 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 ML20210P6761999-08-10010 August 1999 Requests That Following Changes Be Made to Distribution on NRC Correspondence 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) 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 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-1999-004, 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 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 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 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 ML20207A0701999-05-19019 May 1999 Forwards Rev 3 to CNS Strategy for Achieving Engineering Excellence, Which Provides Effective Tool for Overall Engineering Work Mgt.Commitments Made by Util,Encl ML20206R7601999-05-17017 May 1999 Forwards Annual Radiological Environ Rept,Radiological Environ Monitoring Program,Jan-Dec 1998,per TS 5.6.2 ML20206P9681999-05-13013 May 1999 Forwards Monthly Operating Rept for Apr 1999 for Cooper Nuclear Station.Rept Includes Documentation of Challenges to Safety/Relief Valves ML20206J0741999-05-0404 May 1999 Forwards Rev 14 to CNS QA Program for Operation, Per 10CFR50.54(p) & 10CFR50.71.None of Changes Represent Reduction of Commitments.Summary of Changes,Encl ML20206J2331999-05-0303 May 1999 Forwards CNS Annual Radioactive Effluent Release Rept for 1998 & Offsite Dose Assessment Manual ML20206F2021999-04-30030 April 1999 Informs That NPPD Now Anticipates LAR Committed in Will Be Submitted by 990615.Operability Evaluations Presently in Effect Ensure That ECCS Pumps Are Operable But Nonconforming & Are Capable of Fulfilling Safety Functions ML20206E5461999-04-29029 April 1999 Forwards Cooper Nuclear Station Occupational Radiation Exposure Rept for 1998. Numbers Reported Reflected Tabulation of All Personnel on Site by Work & Job Function. Repts Will Be Corrected & Resubmitted by 990701 ML20205K1151999-04-0101 April 1999 Submits Extension of Commitment Date for Rev to Plant Strategy for Achieving Engineering Excellence from 990331 to 990519.Licensee Requires Addl Time to Finalize & Approve Rev 3 to Plant Strategy for Achieving Engineering Excellence ML20205E4331999-03-31031 March 1999 Forwards First Biennial Rept of Financial Assurance for Decommissioning for Cns,Per 10CFR50.75(f)(1) ML20205A0561999-03-23023 March 1999 Provides Info Detailing Property Insurance Coverage Maintained by NPPD & Midamerican Energy Co for Cns,In Compliance with 10CFR50.54(w)(3) 05000298/LER-1999-001, Forwards LER 99-001-00,including List of NRC Commitments Made by Util1999-03-22022 March 1999 Forwards LER 99-001-00,including List of NRC Commitments Made by Util ML20204G8811999-03-22022 March 1999 Forwards CNS Inservice Insp Summary Rept,Fall 1998 Refueling Outage (RFO-18), IAW Provisions of 10CFR50.55a. Analytical Evaluation for RPV Shell Weld Indications & Augmented Exam Results of RPV Also Included ML20204J4841999-03-19019 March 1999 Requests NRC Review & Approval of CNS ISI Relief Request (RR) PR-04,rev 1.ISI RR PR-04,rev 0 Required CNS to Perform Visual Insp of RPV Head Flange Seal Leak Detection Line. Approval Is Required Because Test Methodology Was Changed 05000298/LER-1998-013, Forwards LER 98-013-01 Re Missed Surveillance of Secondary Containment Isolation Valve.List of NRC Commitments Encl1999-03-16016 March 1999 Forwards LER 98-013-01 Re Missed Surveillance of Secondary Containment Isolation Valve.List of NRC Commitments Encl ML20204C9641999-03-15015 March 1999 Forwards Monthly Operating Rept for Feb 1999 for Cooper Nuclear Station.Rept Includes Documentation of Challenges to Srvs,Per TS 5.6.4 ML20207J5811999-03-10010 March 1999 Forwards Rev 1 to Calculation Nedc 98-024, APRM - RBM Setpoint Calculation ML20207F9661999-03-0101 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-298/98-08.Corrective Actions:Circumstances Surrounding Four Examples Have Been Discussed with Individuals Involved & Counseled,Where Appropriate ML20203C6961999-02-0808 February 1999 Forwards fitness-for-duty Program semi-annual Performance Rept for Period of 980701-1231,per 10CFR26.71(d) ML20202H6721999-02-0202 February 1999 Informs of Changes in Schedule Affecting Four Commitments in ,By Greater than One Month & Notifies of Plans to Issue Rev 3 to Strategy for Achieving Engineering Excellence ML20202E2231999-01-28028 January 1999 Forwards Response to NRC 980603 RAI Re NRC Ongoing Review of IPEEE for Cooper Nuclear Station,Submitted 961030 ML20199K6721999-01-19019 January 1999 Requests Extension of Present Due Date to 980202,as Addl Time Is Required to Resolve Issues Raised on Corrective Actions During Senior Mgt Review of Insp Rept 50-298/98-15 05000298/LER-1998-011, Forwards LER 98-011-00,per 10CFR50.73(a)(2)(v).Commitments Made by Util,Encl1999-01-19019 January 1999 Forwards LER 98-011-00,per 10CFR50.73(a)(2)(v).Commitments Made by Util,Encl ML20199E6281999-01-14014 January 1999 Forwards Monthly Operating Rept for Dec 1998 for Cooper Nuclear Station.Rept Also Includes Documentation of Challenges to Safety/Relief Valves,Iaw TS 5.6.4 ML20206P4171998-12-31031 December 1998 Informs of Extended Completion Due Date of Third Commitment Re EOP Calculations,Per Licensee 980723 Response to Violations Noted in Insp Rept 50-298/98-02.Date Has Been Extended to 990228 ML20199D2251998-12-30030 December 1998 Forwards 1998 CNS Simulator Certification Rept,As Required by 10CFR55.45.Rept Describes Performance Tests Conducted from 1995-98,discusses Performance Test Discrepancies from 1995-98 & Provides Revised Test Plan for 1999-2002 ML20198K2491998-12-23023 December 1998 Discusses RAI Re Response to NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps ML20205A4411998-12-17017 December 1998 Forwards Initial Exam Outline for RO Written Exam to Be Given Week of 990208.Preliminary Copies of License Applications for Candidates Encl ML20196C4011998-11-20020 November 1998 Forwards Rev 1 to Cooper Nuclear Station COLR Cycle 19. Licensee Discovered That COLR Submitted with Contained Incorrect Max Average Planar Linear Heat Generation Rate Curves Specified in Figures 1 to 4 1999-09-20
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A6891990-09-12012 September 1990 Forwards Evaluation of Environ Qualification of Okonite T95/35 Tape Splices in Instrumentation Applications at Facility,Per 900813 Request.Tape Splices Fully Qualified for Use in Plant Instrumentation Circuits in Harsh Environ ML20028G9041990-08-28028 August 1990 Forwards Fitness-for-Duty Program Performance Data for Jan-June 1990.Util 900705 Ltr Provided Addl Info to NRC Re Panel of Drugs Included in Testing Program.Info Re Cutoff Levels for Benzodiazepine in Ltr Incorrect NLS9000369, Forwards Endorsement 80 to Maelu Policy MF-70 & Endorsement 96 to Nelia Policy NF-200,reflecting Shutdown Credit for Most Recent Outage for Nuclear Liability Insurance for Plant1990-08-27027 August 1990 Forwards Endorsement 80 to Maelu Policy MF-70 & Endorsement 96 to Nelia Policy NF-200,reflecting Shutdown Credit for Most Recent Outage for Nuclear Liability Insurance for Plant ML20056A7801990-08-0202 August 1990 Forwards Owners Data Rept for ISI & Owners Rept for Repairs & Replacements NLS9000308, Forwards Info to Demonstrate Util Ability to Obtain Funds for Payment of Deferred Insurance Premiums.Supporting Documentation Encl1990-08-0101 August 1990 Forwards Info to Demonstrate Util Ability to Obtain Funds for Payment of Deferred Insurance Premiums.Supporting Documentation Encl NLS9000196, Responds to Violations Noted in Insp Rept 50-298/90-09. Corrective Actions:To Ensure Future Clarity,District Will Revise Procedures to Clearly Indicate Acceptability of Okonite in Instrumentation Applications1990-07-31031 July 1990 Responds to Violations Noted in Insp Rept 50-298/90-09. Corrective Actions:To Ensure Future Clarity,District Will Revise Procedures to Clearly Indicate Acceptability of Okonite in Instrumentation Applications NLS9000268, Forwards Endorsement 79 to Maelu Policy MF-70 & Endorsement 95 to Nelia Policy NF-2001990-07-10010 July 1990 Forwards Endorsement 79 to Maelu Policy MF-70 & Endorsement 95 to Nelia Policy NF-200 ML20055F3701990-07-10010 July 1990 Informs That Acceptance Criteria for Startup Physics Tests Have Been Met for Recent Cycle 14 Startup,Per NLS9000260, Requests Rev to List of Carbon Copies on NRC Correspondence to util.Marked-up Ltr Showing Revs Encl1990-07-0909 July 1990 Requests Rev to List of Carbon Copies on NRC Correspondence to util.Marked-up Ltr Showing Revs Encl ML20044A8331990-07-0606 July 1990 Informs of New Official Title for Ga Trevors,Effective 900701 NLS9000254, Notifies That Util Fitness for Duty Program Includes Drug Screening for Addl Drugs Over Min Panel of Drugs Required by 10CFR26.Drugs & Testing Cutoff Levels Listed1990-07-0505 July 1990 Notifies That Util Fitness for Duty Program Includes Drug Screening for Addl Drugs Over Min Panel of Drugs Required by 10CFR26.Drugs & Testing Cutoff Levels Listed NLS9000192, Forwards Rev 8 to Updated SAR for Cooper Nuclear Station. Rev 6 to QA Program Transmitted on 900406 Ref in App D.Next Rev to Updated SAR Will Be Submitted on or Before 9107221990-07-0202 July 1990 Forwards Rev 8 to Updated SAR for Cooper Nuclear Station. Rev 6 to QA Program Transmitted on 900406 Ref in App D.Next Rev to Updated SAR Will Be Submitted on or Before 910722 ML20043J0651990-06-22022 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Item 4.1 of Generic Safety Issues 75 Not Applicable to Plant NLS9000217, Submits Followup Response to Insp Rept 50-298/89-34 Re Physical Security Program.Util Completed Safeguards Info Audit of Each Contractor Holding Safeguards Info.Contractor Surrendered All Safeguards Info Documents on Plant to Util1990-06-19019 June 1990 Submits Followup Response to Insp Rept 50-298/89-34 Re Physical Security Program.Util Completed Safeguards Info Audit of Each Contractor Holding Safeguards Info.Contractor Surrendered All Safeguards Info Documents on Plant to Util ML20043G6381990-06-15015 June 1990 Forwards Monthly Operating Rept for May 1990 & Corrected Operating Rept for Apr 1990 for Cooper Nuclear Station ML20043G1101990-06-14014 June 1990 Responds to NRC 900515 Ltr Re Violations Noted in Insp Rept 50-298/90-12.Corrective Actions:Individual Senior Technician Status Rescinded & Procedure Describing Qualification Requirements,Including Health Physics Experience,Written ML20043G6471990-06-13013 June 1990 Forwards Decommissioning Funding Plan,Per 10CFR50.75 & Decommissioning Trust Fund Agreement Between Util & Firstier Bank,Lincoln Dtd 900601 ML20043G4581990-06-13013 June 1990 Forwards Endorsements 72-78 to Maelu Policy MF-70 & Endorsements 88-94 to Nelia Policy NF-200 ML20043G3891990-06-13013 June 1990 Forwards Endorsements 14 & 15 to Nelia Policy N-41 & Maelu Policy M-41,respectively ML20043F4981990-06-0505 June 1990 Forwards Changes to Proposed Rev 6 of Plant QA Program for Operation Policy Document Submitted in 900406 & 19 Ltrs ML20043C4381990-05-31031 May 1990 Forwards Change to QA Program for Operation Policy Document for Review & Approval,Per 10CFR50.54(a)(3) ML20043C3091990-05-30030 May 1990 Responds to NRC 900430 Ltr Re Violations Noted in Insp Rept 50-298/90-15.Util Does Not Believe That Violation Existed & Therefore No Corrective Action Required.Inservice Testing Program Being Enhanced as Result of Insp ML20043C7081990-05-25025 May 1990 Forwards Rev 6 to Inservice Testing Program for ASME Class 1,2 & 3 Components, as Committed in Util 890926 Response to Generic Ltr 89-04.Summary Listing of Changes Also Encl NLS9000198, Forwards Public Version of Nebraska Public Power District Cooper Nuclear Station 1990 Evaluated Exercise,9007251990-05-23023 May 1990 Forwards Public Version of Nebraska Public Power District Cooper Nuclear Station 1990 Evaluated Exercise,900725 ML20043B6551990-05-18018 May 1990 Forwards Response to Insp Rept 50-298/90-05 Re Safety/Security Interface Issue.Response Withheld (Ref 10CFR73.21) ML20042F7371990-05-0303 May 1990 Forwards Tech Spec Bases Section 3.12.C, Svc Water Sys, in Response to SSFI Repts 50-298/87-10 & 50-298/89-03 & Implementation of Design Change 90-009, Automatic Isolation of SW-MOV-37MV on Low Svc Water Pressure, for Review ML20042F2821990-05-0101 May 1990 Clarifies Initiating Conditions Listed in 900316 Ltr Re Review of 890919 Rev 11 to Plant Emergency Plan.Gaseous Release Emergency Action Level Established as High Alarm on Effluent Monitor ML20042F1491990-04-30030 April 1990 Provides Response to NRC Safety Evaluation Concerns Re Util Response to Generic Ltr 88-01.Licensee Will Conform to NRC Position on Reporting Requirements ML20042F1481990-04-30030 April 1990 Provides Results of Quarterly Local Leak Rate Test on Containment Purge & Vent Valves at Plant ML20042E4601990-04-12012 April 1990 Forwards Rev IX to Reg Guide 1.97 Instrumentation List to Correct Errors Identified During NRC Insp (Insp Rept 50-298/90-01) ML20042E2031990-04-0606 April 1990 Suppls 900122 Response to Insp Rept 50-298/89-34.Completion Date for External Audits Extended to 900531 ML20042E0791990-03-27027 March 1990 Forwards Annual Radiological Environ Operating Rept 1989. ML20012D9571990-03-23023 March 1990 Submits Supplemental Response to Util 890417 & 0803 Responses to Station Blackout rule,10CFR50.63.Util Reserves Right to Review Final Issue of NUMARC 87-00,App D Prior to Implementation ML20012D9671990-03-20020 March 1990 Lists Present Levels of Property Insurance Coverage,Per 10CFR50.54(w)(1).Policy Expiration Date for Coverage Is 900501.Util Presently Involved in Insurance Renewal Process ML20012C6951990-03-15015 March 1990 Notifies NRC of Intent to Defer Response to Generic Ltr 89-19,per 900306 Approved Scheduler Extension.Response Will Be Submitted on or Before 900504 ML20012C6931990-03-15015 March 1990 Submits Final Response to Generic Ltr 88-14, Instrument Air Supply Problems Affecting Safety-Related Equipment. Final Item,Verification That Mfg Air Quality Requirements for Essential Components,Completed ML20011F5631990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-298/89-31.Corrective Actions:Numbered Lead Seal Installed & Logged When Found Missing on 891113 & Procedure 0.9 Reviewed W/Personnel ML20011F8111990-03-0202 March 1990 Forwards Corrections to Rev 24 to Plant Safeguards Plan.Rev Withheld (Ref 10CFR73.21) ML20012A5061990-02-26026 February 1990 Forwards Proprietary GE11 LTA Fuel Bundle Description for Cooper Nuclear Station Reload 13,Cycle 14. Util Plans to Load Four Fuel Assembly Lead Test Assemblies as Part of Plant Reload 13.Encl Withheld (Ref 10CFR2.790) ML20012C7801990-02-23023 February 1990 Forwards Comments on Questions & Answers Associated w/900221 Exam.Recommends That Comments Be Considered in Written Exam & Serve as Basis for Refining Exam Answers ML20011F6531990-02-21021 February 1990 Lists Property Insurance Coverage Carried by Util W/Nelia & Maelu W/Expiration Dates of 900501 ML20011F1131990-02-15015 February 1990 Requests Relief from Commitment to Continue motor-operated Valve Testing Under Program Established in Response to NRC Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transient Due to Improper Switch Settings. ML20011F0321990-02-14014 February 1990 Responds to NRC 900118 Ltr Re Violations Noted in Insp Rept 50-298/89-37.Corrective Actions:Plant Svcs Procedure 1.6, Warehouse Marking & Tagging Will Be Revised to Delete Requirement of Placing Hold Tag W/Work Item File ML20006C5391990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Applicable HX Performance Evaluation Procedures Will Be Revised by 901231 & Ultrasonic Testing Will Be Performed ML20006A5031990-01-22022 January 1990 Forwards Response to Insp Rept 50-298/89-34.Response Withheld (Ref 10CFR73.21) ML20006A8191990-01-16016 January 1990 Forwards Endorsement 71 to Maelu Policy MF-70 & Endorsement 87 to Nelia Policy NF-200 ML20006A9641990-01-16016 January 1990 Forwards Endorsement 5 to Nelia Certificate NW-107 & Maelu Certificate MW-43 ML20006A5091990-01-16016 January 1990 Forwards Endorsement 13 to Nelia Certificate N-41 & Endorsement 13 to Maelu Certificate M-41 ML20005G5621990-01-0808 January 1990 Forwards Monthly Operating Status Rept for Dec 1989 & Revised Operating Status & Unit Shutdown Data Repts for Nov 1989 for Cooper Nuclear Station ML20005E8661990-01-0404 January 1990 Forwards Rev 25 to Safeguards Plan.Changes Reflect Improvements to Main Vehicle Gate,Restrictions on Warehouse Searches & Distribution Changes for Annual Security Audits. Rev Withheld (Ref 10CFR73.21) 1990-09-12
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GENERAL OFFICE
. Nebraska Public Power District * "% Rnase ^nt""
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CNSS903571 ,
March 2, 1990 'r L' U. S. Nuclear Regulatory Commission L-Attention: Document Control Desk Washington, DC 20555
Subject:
NPPD Response to inspection Report 50-298/89-31 f_'
Gentlemen:
L' This letter is written in response to your letter dated January 31, 1990, which transmitted Inspection Report No. 50 298/89 31. Therein, you identified two violations. The following is a statement of each violation and our S respective response in accordance with 10CFR2.201. With regard to the Notice of Violation, paragraph A, " Failure to Follow Procedures / Inadequate -
Procedures", each specific finding and the associated response has been segregated for clarity.
Sy tement of Viola 112.D A. Failure to Follow Procedures /Inadeaunte Procedures Criterion V of Appendix B to 10 CFR Part 50 states, that,
" Activities affecting quality shall be prescribed by documented ,
instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."
Four instances were identified in which license: cersonnel either "
15 failed to follow procedures or in which licensee procedures were
;_ inadequate. -
A. Failure to Follow Procedures /Inadeaunte Procedures ITEM 1. Cooper Nuclear Station (CNS) Operations Procedure 2.0.2,
" Operations Logs and Reports," Revision 13, required that =
$ valve LV 123W-11, Core Spray pump 1B suction from the Torus, be sealed in the open position.
Contrary to the above, on November 13, 1989, the inspector observed that valve LV 123W-11 was in its required open position but was not sealed as required.
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. CNSS903571 March 2, 1990 USNRC page 2 Reason for Violation The reason for the missing seal could not be determined. A seal was in place on September 12, 1989, when the sealed valves were last audited. ,
Between September 12, 1989, and November 13, 1989, no maintenance was performed in the vicinity that would have involved the subject valve.
Corrective Steos Which Have Been Taken And The Results Achieved A numbered lead seal was installed and properly logged immediately after it was found missing on November 13, 1989.
Corrective Steos Vhich Vill Be Taken To Avoid Further Violations A following audit, performed on December 14, 1989, discovered no additional discrepancies. Based on the positive results of the December 14, 1989 audit and previous quarterly audits the only remaining action is to review the procedural requirements for the audit to verify clarity and adequacy.
Date When Full Comoliance Will Be Achieved Compliance was achieved on November 13, 1989 with the replacement of the missing seal. Any necessary procedural upgrades resulting from the committed procedural review will be completed by July 1,1990.
Statement of. Violation A. Failure to Follow Procedures /Inadenuate Procedures IYEM 2. CNS procedure 0.9, " Equipment Clearance and Release Orders,"
Revision 9, Section IV.A.1 required that personnel obtain an equipment clearance and release order for work or operation of CNS systems requiring that the system (or portion of the system) not be operated or that it be placed in a specific configuration (not normal) for the safe conduct of the work or operation.
Contrary to the above, the team identified the following four instances in which appropriate clearances were not used -
I to tag the equipment taken out of service as required:
- a. MVR 89 2189 replaced the service water flow indicator (SV FI 385A). Both mechanical tubing and electrical leads had to be disconnected and reconnected but were not tagged.
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. CNSS903571-March 2; 1990 i
f USNRC
; Page 3 l i
! b. MVR 89 2728 lifted and relocated limit switch rotor f leads on Drywell Spray Loop A Inboard Isolation Valve ;
L RHR MO M013A. The lifted leads were not tagged as
!: required, and no electrical clearance was established, t
! i F
- c. MWR 89-2876 removed the motor from steam supply to augmented off gas downstream shutoff valve (RHR.MO.
921MV) to extract stainless steal lockwire that was L jamming the motor drive. No electrical clearance was i set for disassembly of the valve actuator,
- d. NWR 89 3206 repaired Service Water Solenoid Pilot 7 Valve SW.SOV SPV857, including replacement of a wetted ;
solenoid. No clearance was set for the electrical i circuitry involved.
Reason For Violation f Circumstances associated with each of the above MWRs are as follows:
MVR 89 2189 - Service Water Flow Indicator Performance of work under MVR 89 2189 is not considered to have been accomplished in violation of procedure 0.9, " Equipment l Clearance and Release Orders". During the initial work planning, the foreman and the technician deterWined that the NWR, with the ,
Shift Supervisor's approval, provided adequate control for the safe conduct of this corrective maintenance function. A clearance order was not required because this local flow indicator could be isolated using.the installed local instrument valves. The instrument in question was a low pressure fluid instrument with no l other attached equipment. Note that with regard to the statement ,
J of violation, the local flow indicator has no electrical leads i
attached. During performance of the maintenance activity, the ,
valves were under the direct control of a qualified technician.
MVR 89 2728 - Limit Switch leads ;
I A clearance order _to implement MWR 89 2728 repairs should have
'i been established. This is considered to be a failure to follow L.-
specific procedural requirements by the involved craft.
MVR 89-2876 - Jammed MOV Motor t
A clearance order to implement MWR 89-2876 repairs should have been established. This is considered to be a failure to follow specific procedural requirements by the involved craft.
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I CNSS903571
; March 2, 1990
; USNRC Page 4 L
i gyR 89 3206 - Solenoid Replacement
! Electrical isolation of this specific solenoid pilot valve was not practical since it would have resulted in de energizing other components supplied from the same source which were required to be operable. This concern is considered to be caused by inadequate procedural guidance.
In summary, the reasons for the violacion are a failure to follow procedures and inadequate procedural guidance regarding equipment release and clearance orders. -
Corrective Steps Which Have Been Taken And The Results Achieved ,
Using the aforementioned MWRs as examples, the specific requirements of CNS Procedure 0.9, Equipment Clearance and Release Orders, detailing the responsibilities of CNS personnel for obtaining Equipment Clearance and Release Orders for work or operation of CNS systems has been reviewed with both Instrument 6 Control and Maintenance Department personnel.
The purpose for the procedure and the various steps involved in procedure implementation and the consequences for failure to comply were emphasized. ,
Corrective Steps Which Will Be Taken To Avoid Further Violations ,
CNS Procedure 0.9 will be revised to include procedural guidance for the performance of work in those situations where it is necessary to work on or near energized electrical equipment, and who must approve the conduct of such work. In regard to procedure adherence concerns, this event will be reviewed in the next Industry Events Training course for 16C
- l technicians, Maintenance and Operations personnel.
Date When Full Comoliance Will Be Achieved full compliance will be achieved by July 1, 1990.
Statement of Violation A. Failure to Follow Procedures /Inadeounte Procedures
- I ITEM 3. Cooper Nuclear Station, " Quality Assurance Program for Operation, Policy Document," Revision 5, dated June 7,1989, Section 2.13, committed the licensee to follow the guidance of ANSI N45.2.2 1971. ANSI N45.2.2-1972, " Packaging, Shipping, Receiving, Storage, and Handling of Items for Nuclear Power Plants."
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! March 2, 1990 l USNRC j i
Page 5 t I l
! Section 2.7.1 of this standard defines Level A items as I those items exceptionally sensitive to environmental conditions and require special measures for protection from one or more of the following effects: temperature, humidity ;
and vapors, physical damage, and airborne contamination.
; Section 6.4.1 of the standard prescribed for items in
[ storage the requirements for periodic inspection and examination and the subsequent documentation of the results.
Section 6.6. required preparation of written records that include such pertinent information as storage location, ,
t inspection results, protection, and personnel access. !
r Contrary to the above, Plant Services Procedure 1.7,
" Warehouse Storage," Revision 5, dated December 23, 1987, did not comply with these ANSI requirements in that: !
- a. No temperature or humidity limits were identified for protection of the Level A storage items,
- b. No provisions were implemented for recording temperature and humidity conditions for Level A items.
- c. Requirements for periodic inspections and examinations >
were specified, but not implemented.
Reason For Violation Plant Services Procedure 1.7, " Warehouse Storage", did not contain a specific requirement for recording temperature and humidity conditions, nor for periodic inspections and examinations. Therefore, the reason for the violation is considered to be lack of adequate procedural guidance. It ehould be noted that a monthly inspection of the warehouse facility is performed in accordance with CNS Procedure 0.11, " Station Inspections". Comments or concerns resulting from this inspection are documented on the " Monthly Manager and Supervisor Tour Report", which is an attachment to Procedure 0.11.
Corrective Stens Which Have Been Taken And The Results Achieved i
A review of ANSI N45.2.2 was performed to identify those Class A storage y requirements to be included in the procedure. Subsequently, a survey of other power plants was conducted to determine typical paraneter limits.
Based on these efforts, calibrated thermometers have been temporarily installed in the Class A storage area and a sling psychrometer has been obtained. Procedures have been temporarily changed to establish interim temperature and humidity limits and to require their monitoring on a periodic basis.
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CNSS903571 l March 2, 1990 USNRC :
Page 6 ;
The temporary change also provides for recording of the monitored
. parameters and, additionally, establishes requirements for periodic inspections of the warehouse, including documenting the conditions found.
Corrective Steps Which Will Be Taken To Avoid Further Violations Plant Services Procedure 1.7 will be revised to:
- 1) Identify the temperature and humidity limits for the CNS warehouse
" Level A" storage area.
- 2) Add a data log to document the specified parameters, i
- 3) Include a specific warehouse inspection report.
Date When Full Compliance Will Be Achieved
. Full compliance will be achieved by July 1,1990.
Statement of Violation A. Failure to Follow Procedures /Inadeouate Procedures ITEM 4. Plant Services Procedure 1.6, " Warehouse Marking and Tagging," Revision 5, dated June 4,1988, Sect!on V.3.2.a(2) ,
required that parts scheduled for future troubleshooting or evaluation shall be identified with a " HOLD" tag.
Contrary to these requirements, on December 4, 1989, the ,
inspectors observed untagged electrical parts on a dolly in the licensee's warehouse. Similarly, ASCO solenoid valves located in Level A storage had an " ACCEPT" tag attached to the valves, which were marked to indicate that the shelf-life of the internal components had expired, and that it was l necessary to get a rebuild kit prior to installing the ,
valves in the plant. The " HOLD" tag required by the above procedure was not attached to the valves.
1 This is a Severity Level IV violation. (Supplement 1)(298/8931 01)
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4 CNSS903571 .I March 2, 1990 l USNRC ;
' Page 7 .t
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Et& Eon For Violation ,
i In both cases, the reason for the violation was failure to adhere to i procedural requirements by the responsible CNS personnel. !
The untagged electrical components were on a dolly awaiting disposition '!
instructions from Engineering. The components would not have been l released from the warehouse without those instructions. These i components should have been tagged upon their entry into the warehouse, !
[- but had not been, in anticipation of prompt instructions from Engineering.
t With regard to the ASCO valves, the " ACCEPT". tag identified the necessity to install a rebuild kit prior to installation of the valves.
the valves would not have been released from the warehouse prior to !
installation of the rebuild kits. However, the valves should have been l affixed with " HOLD" tags when it was determined that the valves needed f I
to be rebuilt due to the shelf life limit.
Corrective Steos Which Have Been Taken And The Results Achieved l The untagged electrical material located in the varehouse had previously i been removed during design change activities. Subsequent to the inspection, the material was either dispositioned off site, or appropriately tagged and returned to storage. ,
The ASCO solenoid valves identified with an expired shelf life were affixed with " HOLD" tags and relocated to the " HOLD" area. ?
These situations have been discussed with warehouse personnel and the procedural requirements were reviewed. Warehouse personnel have been directed to comply with the current procedural requirements which specify promptly tagging all components upon entry into the warehouse and not accepting components returned to the warehouse unless properly ,
identified.
Corrective Stens Which Will Be Taken To Avoid Further Violations Plant Services' Procedure 1.6,." Warehouse Marking and Tagging", will be '
revised to further clarify that components (such as the noted ASCO valves) with expired shelf life material, shall be retagged to a " HOLD" status and segregated to the designated " HOLD" area, '
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- 4 CNSS903571.
[ March 2, 1990 j L USNRC Page 8 I L -
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o Date When Full Comn11ance Vill Be Achieved i L The station is presently in full compliance. Plant Services Procedure I
-1,6 will be revised and SORC approved by July 1,1990. l u
i Statement of violation B. Emilure to Perform Reauired Ouality Control Inenections ;
Criterion X of 10 CFR 50, Appendix B, requires that "A program for I inspection of activities affecting quality shall be established P and executed by or for the organization performing the activity to i verify conformance with the documented instructions, procedures, ;
and drawings for accomplishing the activity. Such inspection !
shall be performed by individuals other than those who performed ;
the activity being inspected. Examinations, measurements, or j tests of material or products processed shall be performed for !
each work operation where necessary to assure quality. If
' mandatory inspection hold points, which require witnessing or' f inspecting by the applicant's designated representative and beyond 'i c which work shall not proceed without the consent of its designated
, representative are required, the specific hold points shall be -{
indicated in appropriate documents."
Quality control (QC) Procedure 12.5, "CNS QC Functions," Revision l 4, was established to implement this requirement and required that i
-QC inspections be performed on maintenance activities such as critical reassembly steps, critical measurements and clearances, l and verification of valve timing and timing clearances.
Contrary to the above, on May 16, 1989, licensee personnel performed maintenance, MVR 89 2344, on the emergency diesel ,
generator cam which included critical reassembly steps, critical measurements and clearances, and verification of valve timing and timing clearances. However, QC inspections of these activities '
were not performed.
This is a Severity Level IV violation. (Supplement I)(298/8931-02)
Reason For_ Violation While QC inspections of the maintenance activities were not performed in accordance with the requirements of Quality Control Procedure 12.5, "CNS QC Functions," the required examinations and measurements were performed and were verified to be correct under the direction of a vendor technical representative. The necessary quality checks were performed by the technical representative as evidenced by his signature after each critical job function performed.
CNSS903571 ,
March 2, 1990
- _USNRC i Page 9 :
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r The individual initially assigning QC to this job assumed that due to i the presence of the vendor technical representative, QC sign off upon completion of critical job functions constituted adequate QC verification.
Corrective Stees Which Have Been Taken And The Results Achieved 1
The work package was reviewed to ensure that the factors affecting quality were adequately addressed. This review revealed that the discrepancy described in the statement of violation pertained only to the application of QC Procedure 12.5 sign off requirements. All technical requirements were met. Requirements associated with QC '
verification as prescribed in QC Procedure 12.5 have been discussed and re+ emphasized with Maintenance Department personnel.
Corrective Steos Vhich Will Be Taken To Avoid Further Violations l
l An effort is presently underway to upgrade the existing Maintenance Procedure 7.0.1, " Work Item Tracking Corrective Maintenance", by segregating the procedure into functional areas. As a result of this upgrade, improved adherence to functions such as QC will be facilitated.
This program upgrade will be completed by September 1, 1990.
Date When Full Compliance Will Be Achieved The station is presently in full compliance.
Should you have any questions concerning this matter, please contact my office. -
Sincerely, G. A. revors Division Manager of ,
Nuclear Operations GAT:CRH:bjs cc: U. S. Nuclear Regulatory Commission Regional Office - Region IV NRC Resident Inspector Cooper Nuclear Station
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