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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
[Table view] |
Text
I hh Nebraska Public Power District November 26, 1986
Mr. Robert D. Martin, Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
Subject:
Revised Response to IE Bulletin No. 85-03 Cooper Nuclear Station NRC Docket No. 50-298, DPR-46
Reference:
- 1) Letter from L. G. Kuncl to R. D. Martin dated May 15, 1986, " Response to IE Bulletin No. 85-03 Cooper Nuclear 8tetion"
- 2) Letter from J. E. Gagliardo to J. M. Pilant dated July 22, 1986, requesting additional information on IEB 35-03
Dear Mr. Martin:
Pursuant to the requirements of IE Bulletin 85-03, Nebraska Public Power District (NPPD) submitted Reference 1 on motor-operated valves in the High Pressure Coolant Injection and Reactor Core Isolation Systen.s at Cooper Nuclear Station (CNS). In this submittal, the District stated it was following the BWR Owner's Group efforts in identifying any BWR-unique aspects of the Bulletin and would consider implementing any guidelines that resulted. The Owner's Group effort is now complete and NPPD is revising its submittal to incorporate the developed methodology and to provide the additional information requested in Reference 2. Changes in the submittal are indicated by revision bars in the margins.
The District has reviewed this submittal against the information presented in IE Notice 86-93 "IEB 85-03 Evaluation of motor-operators identifies improper Torque Switch Settings." It was concluded that the notice was not applicable since CNS has no installed Rotork valve actuators.
If you have any questions regarding this submittal, please contact my office.
Sincerely ,
W Jay M. Pilant Technical Staff Manager Nuclear Power Group 8612O20072 861126 JMP/gs:rt25/3(4) PDR ADOCK 05000298 Enclosure G PDR cc: '
ocument Control Desk w/ enclosure /
U.S. Nuclear Regulatory Commission h
I '
l NEBRASKA PUBLIC POWER DISTRICT f COOPER NUCLEAR STATION I
i Revised NPPD Response to Initial Requirements of IE Bulletin 85-03 1
l November 26 , 1986 l
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1.0 INTRODUCTION
The. objective of this report is to revise the Nebraska Public Power District's May 15, 1986 report in response to IE Bulletin 85-03.
IE Bulletin 85-03 pertains to motor-operated valve common mode failure resulting from improper switch settings during plant transients and accidents. The requirements of this bulletin can be broken down into two phases. Phase I requires the licensee to identify and document the design basis for all safety related motor-operated valves in high pressure systems, establish a tentative schedule for implementation of Phase II, and submit this information to the NRC by May 15, 1986. The second phase includes valve testing under actual design pressures or providing justification for alternate method, establishment and
-implementation of a switch-setting program, and preparation of a final report to be submitted to the NRC by November 15, 1987.
NPPD's initial response to the Phase I requirements of IE Bulletin 85-03 for Cooper Nuclear Station was submitted to the NRC by May 15, 1986. In this' submittal, the district stated it would follow the BWR Owner's Group efforts on discerning any BWR unique aspect of this bulletin. Subsequently, NPPD has participated in the BWROG meetings and, as a result of several clarifications and changes, is revising its licensing response to incorporate the methodology developed in BWR Owner's Group Report.[2]
R/85-03 Response, P263 Page 2 In addition, information requested by the NRC in Reference 3 is also addressed below:
o Method to Estimate Switch Settings Vendor design specifications . and component / system operational requirements will be reviewed to identify the various parameters that affect switch settings.
The maximum delta P values listed in Table 2-1 will be used to calculate the maximum required thrust and maximum required stem torque for each valve listed.
This required torque.value will be used in conjunction with the characteristics of the torque switch spring pack to determine the correct set points for the torque switches for each valve. The required operation of each valve will be analyzed to determine the correct limit switch set points.
o Switch Setting Verification A network of testing instrumentation will be utilized to detect and record dynamic baseline signatures of critical parameters (i.e., valve cycle time, torque and limit switch actuation points, developed thrust, running load and dynamic motor current).
This network of testing instrumentation will be similar to that evaluated by NUREG/CR-4380. This baseline signature information, which can be stored electronically as well as in hard copy form, will be used to develop motor running load threshold values.
p These threshold values can be monitored periodically to identify and trend Motor Operated Valve performance.
^
l This network of testing instrumentation will allow dynamic torque / limit switch actuation point signature traces to be obtained periodically to verify correct
- . switch setpoints are being maintained.
1.1 Background
As a result of several events at nuclear power plants during which motor-operatcd valves (MOVs) failed to function on demand, IE Bulletin 85-03 was issued. The purpose of this bulletin is to l
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o R/85-03 Responso, P263 Page 3 request licensees to develop and implement a program to ensure that switch settings on certain safety-related motor-operated valves are selected, set, and maintained correctly. These switch settings should accommodate the maximum differential pressures expected on these valves during normal as well as abnormal events within the design basis of the station.
In general, licensees are required to implement a program to ensure that torque switch, torque bypass features, position limit switches, and overload relays for active motor-operated valves of high pressure safety-related systems are selected, set, tested, and maintained properly. To achieve these objectives, the following tasks were identified as being required by IE Bulletin 85-03:
(1) Review and document the design basis for the operation of each valve. This documentation should include the maximum differential pressure expected during opening and closing in both normal and abnormal events.
(2) Establish the correct switch settings, including a program to review and revise, as necessary, the methods for selecting and setting of all switches.
(3) Change the individual valve settings as appropriate and demonstrate operability by testing the valves at
(
the maximum differential pressure. If the maximum differential pressure cannot practicably be tested, provide justification, including the alternative to maximun differential pressure testing. In addition, stroke test the valves, to the extent practical, to verify proper imp.'.ementation of the switch settings.
(4) Prepare or revise procedures to ensure that correct switch settings are determined and maintained through the life of the plant. These procedures are to be consistent with the requirements of Item 3.2 of
R/85-03 Response, P263 Page 4 Generic Letter 83-28. These procedures should include provisions to monitor valve performance to ensure the switch setting is correct.
(5) A written report to the NRC containing the results of Item (1) above, including a program and schedule to accomplish Items (2) through (4) is to be submitted by May 15, 1986. Items (2) through (4) are to be completed by November 15, 1987, and a report submitted to the NRC 60 days subsequent to the completion of these activities.
1.2 Report Overview Section 2 of this report describes the methodology and process used to identify motor-operated valves in high-pressure systems at CNS. Table 2-1 includes a list of MOVs required to be addressed in response to IEB 85-03.
Section 3 includes a description of the valve testing pro-gram to be completed and a tentative schedule for this program.
A bar chart depicting the schedule is also provided. Section 4 provides a list of references used in performing the analysis.
e
R/85-03 Response, P263 Page 5 2.0 ANALYSIS METHODOLOGY The objective of this section is to describe the process used to identify motor-operated valves in response to IE Bulletin 85-03. The analysis methodology also identifi'es the designed differential pressure and the maximum differential pressure expected during opening and closing of the selected valves during design basis events.
NRC inputs and methodology adopted by the Boiling Water Reactor Owner's Group (BWROG) were utilized to select safety-related motor-operated valves in high pressure systems. Vendor design documents and formulation recommended in the BWROG report [2] were then employed to determine the design and maximum expected differential pressure for each MOV.
2.1 Definitions The following terms have been used in the report and are defined herein for clarification:
Motor-Operated Valve (MOV) - The entire valve assembly, which includes the valve, the' valve operator, and the motor; no further distinction will be made.
High Pressure System - A system that experiences peak nuclear pressure while performing its required safety function.
Single Failure - Single equipment failure or inadvertent equipment operation such as inadvertent valve closure or opening.
Normal Event - The normal BWR operating states and planned operations such as power operation or refueling, from which transients, accidents, and special events are initiated.
R/85-03 Response,-P263 Page.6 Abnormal Event - Plant transients and accidents caused by
. component failure, personnel error, or design basis events' (DBE).
2.2 Component / Operational Requirements Identification From the BWR09 deport, the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems were
. identified as the focus' of this response for Cooper Nuclear Station. Please note that the BWROG Report provides a generic response to IEB 85-03 that is applicable to the spectrum of BWR/3, BWR/4, BWR/5, and BWR/6. Thus, a number of system and piping arrangements addressed in the BWROG Report (i.e., HPCS -
. high pressure core ' spray). have been reviewed and found not i . applicable to Cooper Nuclear Station. The safety functions of the HPCI and RCIC systems are to provide reactor coolant makeup during plant accidents and transients, and to automatically isolate in the event of a steam supply line break. It was indicated in the BWROG Report that HPCI and RCIC are not required
, to perform active safety action / function during normal events.
In the original IEB 85-03 submittal, MOVs and their required operation were selected based on the assumption that single equipment failures and inadvertent equipment operation (such as 4
inadvertent valve closures or opening) that are within the plant
' design basis should be considered. Thus, a normally open MOV, which must remain open to achieve system safety function, was considered to be an active component. However, in this revised IEB 85-03 submittal, system analysis methodology prescribed in the BWROG Report has been adopted and HPCI and RCIC systems are J
4
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R/85-03 Response, P263 Page.7 assumed in their normal standby condition at the start of a design basis event. This assumption was made based on the low probability of the system being in a test mode or out of service during the occurrence of an abnormal event. Thus the required active safety actions of the MOVs are established assuming the systems are in their normal standby condition unless the event can result in the valves changing position.
2.3 Summary of Revisions Based on the methodology modification identified in Section 2.2, a number of valves and their required active operation were revised f;om the May 15, 1986 submittal. A summary of revisions made along with their justification is provided below, o RCIC-MOV-MO 15, 16 and HPCI-MOV-MO 15, 16 - HPCI and RCIC Steam Inboard and Outboard Isolation Valves Valves normally open and required to remain open to provide core cooling supply. Thus, their only required active operation is to close following a system steam line break.
o RCIC-MOV-MO 18 and HPCI-MOV-MO 17 - System Suction from Emergency Condensate Storage Tank Isolation Valve Valve normally open and required to remain open to provide pump suction from ECST. Thus, their only
, required active operation is to close when system pumps are taking suction from the torus.
o RCIC-MOV-MO 20 and HPCI-MOV-MO 20 -
System Pump Discharge Block.
Valves normally open and required to remain open to provide core cooling supply. Not primary containment isolation valves, thus they do not have any required active operation.
7, R/85-03 Response, P263 Page 8 o RCIC-MOV-MO 30 and HPCI-MOV-MO 21 - System Pump Test
[ Bypass to Emergency Condensate Storage Tank
, Valves normally' closed and required to remain closed to prevent diverting core cooling supply. It has no required active operation.
o HPCI-MOV-MO 19 - HPCI Injection f, Valve normally closed and required to open to provide core cooling supply. Not a primary containment isolation valve, thus its only required active operation is to open.
The list of active MOVs along with their component description is provided in Table 2-1.
2.4 System Differential Pressure The design differential pressure and the maximum
) differential pressure expected during a design basis event were identified for each MOV. The design differential pressure was obtained from the original vendors' component design specification [1] [4] and can be found in Table 2-1.
Formulation developed in the BWROG Report were then utilized to derive the maximum expected differential pressure each MOV will experience during a design basis event. The calculated maximum expected differential pressure are presented in Table 2-1.
R/85-03 Response, P263 Page 9 3.0 SCHEDULE FOR PHASE II ACTIVITIES The objective of this section is to establish a tentative schedule for implementation of Phase II activities consistent with the requirements of IE Bulletin 85-03. Tasks required to complete the Phase II effort are identified. In addition, plant outages scheduled for 1986 - 1988 are included since valve test-ing will have to be performed during plant shutdown conditions.
NPPD reserves the right to deviate from requirements it imposes upon itself in this section, if required due to unforeseen operation constraints.
In order to complete Phase II activities, the following tasks must be performed:
(1) Using the results from Phase I (Table 2-1), establish the correct switch settings. This includes a program to review and revise as necessary the methods and procedures for selecting and setting all switches for the required valve operation (open, close). It should be noted that all torque switches in opening circuits of valves identified in Phase I are jumpered and, therefore, are not of any concern. In addition, overload relays for the valves of concern are wired for alarm only.
(2) Provide justification for continued operation (JCO) in accordance with the CNS Technical Specifications for valves considered " inoperable" as a result of Task 1.
(3) Change valve switch settings if necessary, to
- hose established in Task 1. Prior to any switch setting adjustment, a summary of findings as to valve operability vill be prepared.
(4) Demonstrate valve operability by testing the valves that have an active safety function at the maximum differential pressure (MDP) calculated in Phase I (see Table 2-1) or provide justification for alternate
,a TO L R/85-03 Response, P263 Page 10' method _of determining operational readiness. As indicated in IEB 85-03 (page 5), those valves whose only active safety action is to close to isolate a break in the line_ containing the valve.(i.e., HPCI-MO-15, 16 and RCIC-MO 15, 16) are not required to be tested.. Table 2-1 provides the list of valves, involved in Phase II.
(5) Stroke test each valve to the extent practical.
(6) Prepare or revise procedures, as necessary,.to ensure that correct switch settings are ' determined and maintained.
(7) Submit a report to the NRC summarizing the results of Tasks 1 through 6 above. This report'will include a verification of completion of Phase II activities consistent with the requirements of IEB 85-03.
Several Phase II tasks - specified in the previous section must be performed during plant shutdown. The following is a list of the scheduled outages during 1986-1988:
Year . Duration 1986 October 5 - December 20 1987 None 1988 February 28 - April'10 NPPD will attempt' to demonstrate the operational readiness of these valves during the 1986 outage. However, because of the existing time constraints and other major plant modifications, which-have been previously planned, it may not be possible to safely complete the required testing for all valves listed in' Table 2-1 during this outage. Therefore, NPPD anticipates that
" valve testing will be completed during the following outage,
R/85-03 Response, P263 Page 11 scheduled for the period of February to April 1988. The final report required by Phase II will be submitted within 60 days of the completion of the required actions.
In order to comply with the requirements of IE 85-03, NPPD has prepared a tentative schedule for completion of Phase II activities. Table 3-1 includes a bar chart depicting the pro-posed schedule. l i
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. R/85-03 Response, P263 Page 12
4.0 REFERENCES
- 1. Anchor Equipment Company, List of MOVs and Their Respective Design Specifications. Contract No. E69-7, 1969.
- 2. General Electric BWR Owner's Group Report on the Operational Design Basis of
, Selected Safety-Related Motor-Operated Valves, NEDC-31322, September, 1986.
- 3. Letter from J. E. Gagliardo (NRC) to J. M. Pilant (NPPD) dated July 1986.
- 4. Crane Company drawings K-7190 and K-8104, Contract E69-4, 1969.
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9 Enclosure 1-P263 NPPD-CHS IEC 85-03 RESPONSE TABLE 2-1 MOV Data Summary Table (RCIC)
Component Design Max. Expected Required Identification Component Operational Requirements Differential Operational Active l Code (CIC) Description Pressure Differential Operation Comment Pressure RCIC-MOV-MOIS RCIC Steam Open for Core 1146 pst 1091 psi Close Valve not required Inboard Isolation Cooling Supply to be tested at Close for System Steam manimum OP Line Isolation RCIC-MOV-M016 HCIC Steam Open tur Core 1146 psi 1U91 psi Close Valve not. required l Outboard 1%nlation Cooling _ Supply to be tested at Close for System Steam maximum O P Line Isolation RCIC-MOV-M010 RCIC Supply from Open/Close for Core 50 psi 14 psi Close Emeroency Conden- Cooling Supply sate Storage Tank RCIC-MOV-MO2O System Pump Open for Core Cooling 1925 pst 1212 pst None Valve not required l Discharge Block Supply to be tested at i maximum dP RCIC-MOV-M021 RCIC Injection to Open for Core Cooling 1925 psi 1222 psi Open Reactor l Supply RCIC-MOV-M027 RCIC Pump Minimum Close/Open for Core 1500 psi 1335 pst Open Flow Recirc to Cooling Supply 1338 psi Close Torus RCIC-MOV-MU3d RCIC Test Close for Core 1925 psi 1212 pst Hone valve not required Return to ECST Cooling Supply to be tested at manimum 6P RCIC-MOV-MO41 RCIC Supply from Close/Open for Core 50 psi H8 pst Open Tarus Cooling Supply 65 psi Close RCIC-MOV-M0131 RCIC Steam Supply Open fnr Core Cooling 1146 pst 1091 psi Open to RCIC Turbine Supply RCIC-MOV-M0132 Auxiliary Cooling Open for Core Cooling 1500 psi 1311 pst Open Supply Supply Page t of 2 an -
6
4
~
Enclosure 1 -
p263 NPPD-CNS ,
IEB 85-03 RESPONSE TABLE 2-1 MOV Data Summary Table (HPCI)
Component Design . Man. Espected Required Identification Component Operational Requirements Differential Operational Active Code (CIC) Description Pressure Differential Cperation Ccmment Pressure HPCI-MOV-M014 Steam Supply to Open for Core Cooling 1146 psi 1091 psi -Open Turbine Supp1y HPCI-MOV-M015 Steam Supply Open for Core 1146 pst 1091 psi Close Valve not required Inboard Isol.ition Cooling Supply to be tested at Close for System Steam Line Isolation maximum d P HPCI-MOV-M016 Steam Supply Open for Core 1146 psi 1091 psi Close Valve not required Outboarel !sonation Cooling Supply to be tested at Close for System Steam Line Isolation maximum OP HPCI-MOV-M017 Pump Suction from Open/Close for Core 150 psi 14 psi Close Emergency Conden- Cooling Supply sate Storage Tank HP C I -MOV- M019 HPCI Injection Open/Close for Core 1325 pst 1118,2 psi Open Cooling Supoly HPCI-MOV-M020 Steam Pump l Open for Core _1925 psi 1212 psi Discharge Block None Valve not required l Cooling Supply to be tested at maximum O P HPCI-MOV-M021 HPCI Pump Test Close for Core 1925 pst 1212 psi None Bypass to ECST Valve'not required Cooling Supply to be tested at manimum O P 1
HPCI-MOV-M025 HPCI-P-MP Minimum Close/Open for Core Flow Bypass Line 1500 psi 1014 ps i_ Open CoolinD Supply 1030 psi Close Isolatton HPCI-MOV-M058 HPCI Pump Suction Close/Open for Core 150 pst 98 pst Open from Suppression Cooling Supply 64 psi Pool Close l
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TABLE 3-1 COOPER NUCLEAR STATION hEBRASKA PUBLIC POWER DISTRICT IE BULLETIN 85-03 RESPONSE PROPOSED SCHEDULE FOR COMPLETION OF PHASE II ACTIVITIES SCHEDULED OUTAGES l l
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1 I I
I l l l l l l 1 l l TASK l 1 i i i i i l l l l l l
- 1. ESTABLISH PROGRAM l. I I J l l t I i l i I I I
- 2. WRITE JCOs l l . I l J l l l I (if necessary) I I i i 1 1 I I I I I I I I I I I I I. I l .I l 1 1
- 3. WRITE SUWARY OF l l l l l l FINDINGS AND CHANGE l l l l l l l l I l l l I SWITCH SETTING l I I I I I I I I I
- 4. VALVE TESTING, I l. ,I l l l - l .l
~
. I l l i l I l l l l PRESSURE
! ! I I I I I I I VALVE TESTING, l l l l l l I
- 5. l l '
STROKE l l l l l l I I l l 1 I I I I I I I
- l. I I I I, I l
- 6. WRITE / REVISE SWITCH I l l i I I i l l SETTING PROCEDURE I I i I I I I I l~ l I
- 7. FINAL REPORT l l l !. I I I l .I I I I l~ l i i i ~l l I I I I I ! I I I I I I I I i i l I I I I I I I I I i June Jan. June Jan. June l 1986 1987 1988 1 l
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