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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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GENER AL OFFIM Nebraska Public Power District ' ' ' fE"$3837"M1U#** ""'
March 22,1979 Director, Nuclear Reactor Regulation Attention: Mr. Thomas A. Ippolito, Chief Operadng Reactors Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Reload 4, Cycle 5 Reload Licensing Submittal -
Request for Additional Information Cooper Nuclear Station NRC Docket No. 50-298, DPR-46
Dear Mr. Ippolito:
Your letter of March 13, 1979, transmitted a request for additional information relating to Nebraska Public Power District's January 31, 1979 Reload License Application. Enclosed please find the District's response to these four questions. These questions were informally received from the Staff February 23, 1979.
As stated in our application, the current refueling schedule still allows for plant startup on April 27, 1979; therefore, approval of the reload submittal is respectfully requested prior to that date.
Should you require additional inIormation, please do not hesitate to contact me.
Sincerely yours, kt
- . I. Pilant Director of Licensing and Quality Assurance IMP /jw
- srs22/3 Enclosure j
I i
79032704 9
Mr. Thomas A. Ippolito March 22, 1979 Page 2 STATE OF NEBRASKA)
)
PLATTE COUNTY )
Jay M. Pilant, being first duly sworn, deposes ar.d says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to suitnit this information on behalf of Nebraska Public Power Distr':t; and that the statements in said application are true to the ha* if his knowledge and belief.
b My'M. P11 ant Subscribed in my presence and sworn to before me t..is 22nd day of March, 1979.
j NOTARY PUBpC My Commission expires October 14, 1980.
EMEAL BITART Stats et setranta MARLYN R. HOHNDoAF
_ thCesent 4 oct, t4,1380
ATTACHMENT I REQUEST FOR ADDITIONAL INFORMATION COOPER NUCLEAR STATION UNIT 1, RELOAD 4 Question 1 The staff stated in Section 6.2.2 of its safety evaluation of the Generic Reload Fuel Application (which you have referenced in your reload application) that " Additional Data should be submitted by GE to the staff for review, to justify the conservatism of the GEXL correlation for the second and subsequent cycles of operation of the retrofit 8x8 bundles, when local peaking factors may increase sufficiently to cause non-conservative CPR calculations." Your reload submittal has not addressed this issae. Accordingly, we request you provide either directly or through reference, adequate information which speaks to this concern. Your response should include:
The extent to which individual heater rods are instrumented in steady-state critical power tests for the retrofit fuel design.
For each test bundle provide measured and predicted results in tabular form for the various test conditions.
Provide trend plots (measured critical power / predicted critical power vs.
hIN, G, P, critical power, test bundle) .
Maximum R-Factor for each test bundle (new and old R-Factor definitions) .
Thermocouple locations (rod-by-rod and axially).
Spacer-grid locations.
Provide power and heat flux for all plots of tranrient CPR cases.
Response
General Electric Company will respond to this request on a generic basis. This response will be contained in a letter, R. E. Engel (GE) to Robert L. Tedesco and Darrel G. Eisenhut (NRC), " Additional Info rma tion , 8x8R Fuel GETAB R-Factors", to be issued 3-31-79.
Question 2 The staff stated in its evaluation of the Generic Reload Fuel Application that it is acceptable to reanalyze only a relative few limiting transient events as part of reload safety analysis. The basis for the selected events stems in part from previous (e.g. FSAR) analysis results (consequences). Furthe rmo re , the relative consequences of all of the anticipated transient events considered (in the FSAR) is based on specific equipment performance characteristics and reactor protection system characteristics. It is not known whether the proposed reduction in the low pressure main steam line isolation valve setpoint (from 850 psig to 825 psig) will cause the currently non-limiting pressure regulator failure event to bece.e a limiting event. We require that you 7:ceide sufficient information that shows the pressure regulator failure event remains non-limiting, even with the proposed setpoint change. An accep ;able response would be to provide the transient ACPR (for each fuel type) for a pressure regulator failure transient analysis which models the proposed technical specification change.
Response
The proposed reduction in the main steam line low pressure isolation setpoint from 1850 psig to 1825 psig will not increase the severity of the pressure regulator failure opening event. This trar.sient is initiated by a sudden reduction in pressure demand signal. This signal causes the turbine control and bypass valves to begin opening resulting in a rapid drop in core pressure. This pressure decrease results in increased void formation. The rapid insertion of negative reactivity due to the increased void content results in a rapid power decrease. The rapid pressure / power decay is terminated by the closure of the main steam isolation valves. Lowering the setpoint will actually result in a larger power decay before the transient is terminated, the resulting peak heat flux will be lower and the CPR response of this transient will actually be improved (reference SAR Figure XIV-5-8).
Question 3 Provide the ACPR result for a fuel loading error consisting of mislocating an 8x8R bundle in a 7x7 cell.
Response
The NRC has accepted the reload submittal format contained in NEDO-24011A, Rev. 0 which provides for reporting only the most limiting bundle loading error.
In the event the NRC imposes new criteria which will make the mislocated 8x8R bundle limiting, the District will provide the results of the analysis of this event.
Question 4 It is the staff's position that adequate start-up physics testing be performed following each plant refueling in order to assure that the core conforms to the design. i.e. that the actual (measured) reload core configuration is consistant with the analyzed reload core configuration. The staff currently has a study underway for the purpose of generically establishing requirements for minimum BWR start-up physics test programs. Although this effort is not yet complete, we have concluded at this juncture that, in order to be acceptable, BWR start-up test programs, must include each of the following (or acceptable equivalents):
A. A visual inspection of the core including a photoL;aphic or videotape record.
B. A check of core power symmetry-by checking for mismatches between symmetric detectors.
C. Withdrawal and insertion of each control rod to check for criticality and mobility.
D. A comparison of predicted and measured critical insequence rod pattern for nonvoided conditions.
In view of the importance the staff places on the above four BWR start-up physics program elements, we request that you provide a commitment to include them (or acceptable equivalents) in the Cooper Station Unit 1, Reload 4 start-up program.
Additionally, in order that we may adequately assess the characteristics of the Cooper Station Unit 1 Cycle 5 start-up test program, we request that you provide the following information:
A description of the core loading verification (inspection) procedures to be followed for the core refueling including the number of independent checks to be made of a) the actual core loading, b) the intended core loading and c) the consistency between the two.
A description of each start-up physics test (including those indicated above).
The acceptance criteria and basis for each test (including those indicated above) which provides assurance that the actual core confo rms to the design.
The actions to be taken for each test (including those indicated above) whenever the acceptance criteria are not satisfied.
Response
Nebraska Public Power District will perform the four start-up physics tests described in Attachment II in the Cooper Nuclear Station Reload 4 start-up p rog ram.
ATTACHMENT II COOPER NUCLEAR STATION REL0s 4, CYCLE 5 START-UP PHYSICS TEST PROGRAM
CCRE LOADING VERIFICATION I. pURp0SE The core loading verification is performed after the core is fully loaded to assure that the core is constituted as per the design loading plan.
II. DESCRIPTION The core loading verification consists of the following three distinct phases:
A.
A scan of the core with a television camera is =ade by operations personnel located on the fuel handling bridge. The fuel asse:bly serial number Control and Root via orientation is observed and co==unicated to the phone. The Control Root verifies the correctness of the information (or asks for a reread). The person located in the Control Roce has a ec=puter generated =ap of fuel assembly serial numbers versus location. The personnel on the fuel bandling bridge =ust correctly identify the serial nu:ber and orientation before moving to the nett fuel assembly. The person located in the Control Room will or.ly verify cor:setness (or ask for a reread);
he does not co==unicate the gerial number to the personnel on the fuel handling bridge. .
B.
Concurrently with the above verification a video tape is =ade and the appropriate blocks of a blank core =ap are filled in with the fuel assembly serial numbers and orientations by,a representative of the Reactor Engineering Staff. The Reactor Engineering repre-se:tetive is viewing the verification on a monitor located r~e=otely from that used by the personnel on the fuel handling bridge and is also in continuous contunication with both the fuel' handling bridgc and the Control Room. He must agree with the fuel assembly serial number and orientation as identified by the personnel on the fuel handling question.
bridge or he calls for a reread of any fuel asse=bly in He also marks the beginning of each row scanned with voice identification on the video tape for subsequent review. The core cap produced during the video caping is then checked against a computer generated core cap of the design loading for correctness.
C.
After the whole core has been scanned and taped, the video tapes are reviewed by a three =an team (different personnel than partic-ipated in the above two phases) as a final check. Teat menber ene is responsible for operating the tape recorder and observing fuel assembly ,erial numbers; member one also serves as a quality con-trol check 'or member two's activities. Tean cember two views the tape and calls out the fuel asse si,.
in sequence. serial numbers and orientation Tea. ec=ber three writes down the called fuel assembly serial numbers in the appropriate block of a blank core nap. Member three also indicates on the core cap that the orientation is cor cet after member two verifies that the spring clip location is acceptable (orientation as it should be). After cach rcw is revieued and the fuel assembly serial numbers entered on the map, member three rec .
back the recorded fuel assembly seri:1 numbers and member two verifies these nu=bers against a cceputer zenarated core map of the design ionding.
III. ACCE?TANCE CRITERIA The core e.ust be leaded according to the design loading pattern (or a fuel vendor approved variation thereof to acco==odate dis-charged leaking fuel asse=blies).
IV.
ACTIO :S TO BE TAFE:i IF CRITERIA NOT SET The core will be rearranged to conform to the design leading pattern areasthe and of core loading verification will be redone for the affected the core. -
CO:ITROL RCD CRITICALITf A 'D MOSILITf CHECR I. PL*RPOSE This test is performed to assure that all fuel asse=blies are properly loaded and that all control rods are operable.
II. DESCRIPTIO:I This test will be performed af ter the core loading verification has been co=pleted; this will provide assurance that an inadvertent crit-icality will not occur due to fuel assemblies being =islocated (it is very unlikely that a fuel leading error could result in a situation where criticaliev cos'.d be achieved with a single control red being withdrawn). Perfor:ance of this test will assure that there are no fuel asse=blics loaded so as to affect the move =ent of a control red.
If =ove=ent of a control rod is affected, it could be caused by such things as a rotated fuel asse=bly, a fuel asse=bly not being properly seated, et2. Each control rod in the core will be withdrawn and in-serted tc assure that it can be =oved' with normal drive pressure. Also, the nuclear instrumentation will be monitored during the =ovement of each control red to verify suberiticality.
IIT. ACCEPTA2:CE CRITERIA Each ce= trol rod must be exercised (fully withdrawn and inserted) one at a tL=e to verify cobility under nor=al drive pre'ssure (nor=al drive pressure is plant dependent); suberiticality will also be verified.
I7. ACTIONS TO 3E TAKEN IT CRITERIA NOT MIT For those control rods that will no" move under nor=al drive pressure, appropriate repairs or adjustments will be made so that the nor=al drive pressure criterien can be =et. If criticality was to be achieved by the withdrawal of a single control rod, the concrol rod would be inserred and all further startup activities would cease; the fuel loading verification would be redone and no further red cove =ents vould occur until che situation was satisfactorily resolved.
INITIAL CRITICALITY PREDICTION
- 1. PURPOSE This test is performed to cenpare the predicted and reasured insequence critical red pattern for nonvoided conditions.
II. DESCRIPTION The initial critical control rod pattern in the cold Xenon free con-dition will be predicted at the beginning of each fuel cycle using data supplied by the fuel vendor. Control rod wor:hs will be deter =ined frca rod worth curves provided for the shutdown cargin de: castration.
The reactor will be brought cri:ical utili:ing the ccatrol red sequance deter =ined by the fuel vendor such that the withdrawal of the analyti-cally strongest control red will occur before criticality is at:sined.
A =oderator te=perature correction (supplied by the fuel vendor) will be applied if criticality eccurs at grea:er than SS 7. The actual and predicted critical red pat: erns will be ec: pared.
III. ACCEPTE CE CRITIRIA Acceptance criteria of +0.5% ak/k and -1.5% will be applied. The
+0.5% ak/k criterion is taken from the see:icn of the Technical Spec-ifications describing reportable occurrences (Reactivity Anomalies).
The -1.5% ak/k criterien is arbitrarily set so as to be consisten: with the 2% ak/k window allowad for the steady sta:e pcuer reactive ano=aly check (11% ak/k). .
- 17. ACTIONS TO BE TAKEN IF CRITERLA NOT SET ,
If criticality occurs 0.5% ak/k before the predic:ed'cri:ical position, actions vill be taken to deter =ine the cause and the event will be reported as per Technical Specificatica require ents. If criticality occurs more than 1.5% ak/k after the predicted cri:ical positica, actions 2111 be taken to deternine the cause of the event. In both cases, this actica would probably censist of requesting the fuel vendor to recheck the red worth curves provided and if necessary, have the fuel vender renormali:e his ccre simulator calcula:icns so that more accurate rod worth curves can be provided. Startup would continue and all ther=al li= ins would be closely monitored to assure cenpliance udth all Technical Specification Liciting Conditions of Cperation.
, TI? SY}CE 2Y CHECK I. ?"?}0SE This test is performed to measure the total TI? syn =etry and to compsre the readings of individual sy==etric pairs of T1?'s.
II. DESCRI?TIO:i Typically, during a refueling outage, fuel is both removed and shuf-fled to acco==cdate the, core loading plan for the subsequent cycle.
Also, local power range conitors (LPRM's) are replaced as necessary due to their having reached end of life conditions. This test deter-nines the cagnitude of the TI? system and neutron flux asynnetrics af ter the core has been rec =nstituted according to the loading plan.
The reactor will be above 75% thernal power and operating with an ec:an: sy==e:ric rod pattern for the performance of this test.
Addi-ticnally, the reactor core should be at steady-state conditions es-re::ially free of .Tanon transients and enpected to rc:ain at stcady-state conditi=ns for the duration of the tes:ing. Da:a vill be taken u-4:ing the TI? syste= hardware and statisticall; analy:ed using
=eticds provided by the fuel vendor.
Ill. AC.TJ2:CI CRITERIA 1 criterion of 12% will be applied to the total T1? reading uncertainty; this 12% criterion translates into a criterion of 10.55," for total TI?
ins-- -=
uncertainty (randos noise and geometric cc=ponents). These values were deter =ined utilizing General Electric developed =ethods for deternicing the total precass co puter uncertainty.(NE00-20310). A cri: erica of 23% will be applied to the individual sy=:etric pairs; this was deter ' ed by =altiplying 6.5% by /2 by 2.5 standard deviations.
The 6.5% value is the total TI? instru=ent uncertaint'y that corresponds to a total TIP reading uncertainty of 8.7%; 8.7% total TI? reading un-cer:ain:y is that value used in reload licensing submi::als.
I',' . ACTIC::S TO 3E TAKE': IF Ch.AIA NOT SET Startup activities would continue and all thermal limits would be closel-
/ =onitored to assure co=pliance with all Technical Specifica-tion Li= icing Conditions of Operation. The responsible test engineer vould exa=ine the test data and analysis r.ethod carefully for errors.
If no enors are found, the TI? system hardware would be checked with e=phasis initially being placed on the checkout of TIP axial calibra-tion and align =ent. If faults are found, they would be corrected and the tests repeated. Another thing that could be checked if no faults are discovered would be the fuel channel location history for those channels located around the affected TI?'s; channel bowing due to non-unifor: neutron flun levels can affect the water gap dimensions around the TI? detector. This would in turn affe:: the power calculated for one =c=ber of a sy==etric TIP pair; analysis by Cenaral Electric has denenstrated that the probability is high that thermal liaits will be af f ected conservatively by such TI? asyn=e: ries. If no hardware faults or calculational errors are focnd, operation would continue and all ther=al liaits would be closaly onitored.