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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 ML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to 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 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 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 ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212K9661999-09-30030 September 1999 Forwards Safety Evaluation Accepting plant-specific Safety Evaluation Rept for USI A-46 Program Implementation at Cooper Nuclear Station ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl 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 ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program 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 ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl 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 ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance 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 ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants 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 ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date 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 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 ML20210K6071999-08-0202 August 1999 Submits Withdrawal of Proposed License Amend Re Secondary Containment Isolation Description & Refueling Accident Analysis Results ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 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) ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties 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 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event 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 ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses 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 ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl 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 ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept 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) ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 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 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 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 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 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 ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days 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 ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License 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 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 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 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5741990-09-19019 September 1990 Forwards Rev 2 to Browns Ferry Nuclear Plant Cable Issues Supplemental Rept Corrective Actions,Sept 1990. Rept Revised to Clarify Cable Bend Radius & Support of Vertical Cable & Document Resolution of Jamming Issues ML20064A6871990-09-18018 September 1990 Requests Closure of Confirmatory Order EA-84-054 Re Regulatory Performance Improvement Program ML20059L4931990-09-17017 September 1990 Provides Addl Info Re 900713 Tech Spec Change 290 Concerning Hpci/Rcic Steam Line Space Temp Isolations,Per Request ML20064A6851990-09-17017 September 1990 Responds to NRC Recommendations Re Primary Containment Isolation at Facility.Background Info & Responses to Each Recommendation Listed in Encl 1 ML18033B5171990-09-17017 September 1990 Forwards Addl Info Re 900524 Tech Spec Change 287 on Reactor Pressure Instrument Channel.Schematic Diagrams Provided in Encl 2 ML20059K2971990-09-14014 September 1990 Responds to NRC 900208 SER Re Conformance to Reg Guide 1.97, Rev 3, Neutron Flux Monitoring Instrumentation. TVA Endorses BWR Owners Group Appealing NRC Position Directing Installation of Upgraded Neutron Flux Sys ML20064A6891990-09-12012 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 ML20059H3861990-09-10010 September 1990 Forwards Corrective Actions Re Radiological Emergency Plan, Per Insp Repts 50-259/89-41,50-260/89-41 & 50-296/89-41. Corrective Action:Plant Manager Instruction 12.12,Section 4.11.3.1 Revised ML20059E1741990-08-31031 August 1990 Informs That Plant Restart Review Board & Related Functions Will Be Phased Out on Date Fuel Load Commences ML18033B5031990-08-31031 August 1990 Forwards Financial Info Required to Assure Retrospective Premiums,Per 10CFR140 & 771209 Ltr ML20059D7061990-08-28028 August 1990 Requests That Sims Be Updated to Reflect Implementation of Program to Satisfy Requirements of 10CFR50,App J.Changes & Improvements Will Continue to Be Made to Reflect Plant Mods, Tech Spec Amends & Recommendations from NRC 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 ML20063Q2431990-08-20020 August 1990 Responds to 900807 Telcon Re Rev to Commitment Due Date Per Insp Rept 50-260/89-59 Re Electrical Issues Program ML18033B4931990-08-20020 August 1990 Suppls Response to Violations Noted in Insp Repts 50-259/90-14,50-260/90-14 & 50-296/90-14.Corrective Actions: TVA Developed Corporate Level std,STD-10.1.15 Re Independent Verification ML20063Q2441990-08-17017 August 1990 Advises That IE Bulletin 80-11 Re Masonry Wall Design Implemented at Facilities.Design Finalized,Mods Completed, Procedures Issued & Necessary Training Completed.Sims Data Base Should Be Updated to Show Item Being Implemented ML20063Q2451990-08-17017 August 1990 Provides Revised Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants & Notification of Commitment Completion ML20059A4861990-08-16016 August 1990 Responds to Verbal Commitment Made During 900801 Meeting W/Nrc Re Control Room Habitability.Calculations Performed to Support Util 900531 Submittal Listed in Encls 1 & 2 ML20059A5141990-08-16016 August 1990 Provides Response to NRC Bulletin 88-008,Suppl 3 Re Thermal Stresses in Piping Connected to Rcs.Util Does Not Anticipate Thermal Cyclic Fatique Induced Piping,Per Suppl 3 to Occur in Plant.Ltr Contains No Commitment ML18033B4821990-08-14014 August 1990 Submits Revised Response to Violations Noted in Insp Repts 50-259/89-16,50-260/89-16 & 50-296/89-16.Extends Completion Dates for Commitments to 901203 ML18033B4831990-08-13013 August 1990 Responds to NRC 900713 Ltr Re Violations & Deviations Noted in Insp Repts 50-259/90-18,50-260/90-18 & 50-296/90-18. Corrective Actions:Craft Foreman Suspended for Three Days & Relieved of Duties as Foreman ML18033B4811990-08-10010 August 1990 Responds to NRC 900710 Ltr Re Power Ascension Testing Program.Four Hold Points Selected by NRC Added to Unit 2 Restart Schedule ML18033B4801990-08-0808 August 1990 Forwards Response to SALP Repts 50-259/90-07,50-260/90-07 & 50-296/90-07 for Jul 1989 - Mar 1990 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 ML18033B4371990-07-13013 July 1990 Forwards Corrected Tech Spec Page 3.2/4.2-45 to Util 900706 Application for Amend to License DPR-52 Re ADS ML18033B4331990-07-13013 July 1990 Requests Temporary Exemption from Simulator Certification Requirements of 10CFR55.45(b)(2)(iii) ML20044B2121990-07-13013 July 1990 Clarifies Util Position on Two Items from NRC 891221 Safety Evaluation Re TVA Supplemental Response to Generic Ltr 88-01 Concerning IGSCC in BWR Stainless Steel Piping.Insp Category for Nine Welds Will Be Changed from Category a to D ML20055F6091990-07-12012 July 1990 Provides Response to NRC Bulletin 88-003 Re Insp Results. No Relays Found to Have Inadequate Latch Engagements. Therefore,No Corrective Repairs or Replacement of Relays Required ML18033B4251990-07-10010 July 1990 Forwards Cable Installation Supplemental Rept,In Response to NRC Request During 900506 Telcon.Rept Contains Results of Walkdowns & Testing Except Work on Ongoing Cable Pullby Issue ML20055F3701990-07-10010 July 1990 Informs That Acceptance Criteria for Startup Physics Tests Have Been Met for Recent Cycle 14 Startup,Per 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 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 ML18033B4241990-07-0606 July 1990 Advises That Util Expects to Complete Implementation of Rev 4 to Emergency Procedure Guidelines by Mar 1991.Response to NRC Comments on Draft Emergency Operating Instructions Encl ML20044A8331990-07-0606 July 1990 Informs of New Official Title for Ga Trevors,Effective 900701 ML18033B4201990-07-0505 July 1990 Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3. Util Has Concluded That Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issue,Subj to Listed Conditions 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 ML18033B4091990-07-0202 July 1990 Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-259/89-53,50-260/89-53 & 50-296/89-53.Corrective Actions: Condition Adverse to Quality Rept Initiated & Issued to Track Disposition of Deficiency in Chilled Water Flow Rates 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 ML20043H3511990-06-14014 June 1990 Forwards Corrected Pages to Rev 15 to Physical Security Contingency Plan,As Discussed During 900606 Telcon.Encl Withheld (Ref 10CFR73.21) ML20043G4901990-06-14014 June 1990 Forwards Tabs for Apps a & B to Be Inserted Into Util Consolidated Nuclear Power Radiological Emergency Plan 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 ML20043F4951990-06-11011 June 1990 Advises That Facilities Ready for NRC Environ Qualification Audit.Only Remaining Required Binder in Review Process & Will Be Completed by 900615 1990-09-19
[Table view] |
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NLS8800063 February 22,-1988
- U.S. Nuclear Regulatory Commission
. Document Control Desk Washington, D.C.-20555 Gentlemen:-
Subject:
Supplemental Submittal; Proposed Change No. 48 to the Cooper Nuclear Station Technical Specifications NRC-Docket No.-50-298, DPR-46
References:
- 1) Telecopy from W. O. Long to M. T. Boyce, dated January.13, 1988, Transmittal of NRC Questions on Proposed Change No. 48.
- 2) Telephone Conversation, B. Elliot (NRC), K. Walden, J. Meacham, M. Boyce, G. Smith, and P. Ballinger (NPPD) and T. Caine (GE), January 19,11988, . Discussion of NRC
-Questions on Change No. 48. _
- 3) -Letter NLS8700560, from L. G. Kuncl to U.S.NRC, dated October 28,1987, "Proposed Change No. 48 to the Cooper Nuclear Station Technical Specifications."
- 4) Letter NLS8700310, from G. A. Trevors to U.S. NRC, dated July 6,1987, Submittal of GE Report MDC-103-0986, dated May.1987, "Cooper Nuclear Station Reactor Pressure Vessel Surveillance Materials Testing and Fracture Toughness Analysis."
Attachment 1 provides Nebraska Public Power District's responses to the NRC questions transmitted in Reference 1. The District's responses also reflect the' clarifications to the questions made during the January 19 conference call (Reference 2). The NRC questions refer to Proposed Technical Specification Change No. 48, Reference 3, and GE Report MDC-103-0986, Reference 4.
Enclosed as Attachment 2 are revised Technical Specification pages 155 and 156, showing an increase of 2'F in the non-beltline portions of the curves of Figures 3.6.1.a anci 3.6.1.b. The 2*F increase in maximum RTunT for the ASTM A 508 forgings resulted from a reanalysis of the data in Ecordance with Branch Technical Position MTEB 5-2, as discussed in Reference 2. The no significant hazards consideration evaluation previously submitted in Pro)osed Change No. 48 remains applicable, since this added 2*F change moves tie non-beltline portion of the curves in the conservative (higher required minimum temperature) direction.
8803040073 860222 p
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Page 2' FCbruary 22. 1988 Also enclosed, in response to NRC Question 1 on the GE fluence evaluation, is a copy of General Electric (GE) Report NED0-24793, "Browns Ferry Unit 3 In-Vessel Neutron- Spectral Analysis." .This report-describes the origin of.
neutron spectrum and cross-section data -used in the GE! fracture toughness analysis.
Should you have any questions regarding the attached. responses, or require further information, please contact this office.
Sincerely,
/ s G. 4. Trevors Division Manager Nuclear Support GAT /mb:mh25/3 (CHNG48)
Attachment cc: NRC Regional Office Region IV Arlington, TX NRC Resident Inspector Office Cooper Nuclear Station B. Elliot (NRC) t J
m - -
Att:chment 1 t3 NLS8800063 P gi1 ef 11 RESPONSES TO NRC QUESTIONS Estimate of Initial RT NDT
-Question 1 How many heats of ASME SA 533 Grade B Class 1 low alloy steel were evaluated to develop the relationships:
a) 2'F/ft.-lb.,
.b) the difference in longitudinal and transverse charpy energies is 30*F7
Response
The Charpy energy curve slope of 2*F/ft-lb is an upper bound estimate, based on test results of 24 A533 plates reported in Welding Research Council (WRC)
Bulletin 217 [1] and evaluation of 22 plates of SA 533 reported in the LaSalle FSAR [2). The 30*F conversion factor is based on the results in WRC Bulletin 217.
Question 2 How many heats of ASTM A 508 Class 2 low alloy steel were evaluated to determine the difference in longitudinal and transverse charpy properties is 30'F7
Response
There was little data available to establish the longitudinal-to transverse conversion for A508, so the 30'F factor for A533 was used, assuring that the resulting RT NDT values were consistent with A508 NDT values (3). For the sake of prompt response, additional A508 data has not been collected and evaluated at this time. Instead, the A508 forging data for the Cooper vessel have been reanalyzed using Branch Technical Position MTEB 5-2 [4].
The A508 forging (closure flange and nozzle) materials were subjected to Charpy tests at one temperature, 10'F. For all forgings except one steam nozzle forging, NDT values were documented as well. Branch Technical Position MTEB 5 2, Section B.1.1 (4) states, "If limited Charpy V-notch tests were performed at a single temperature to confirm that at least 30 ft-lbs was obtained, that temperature may be used as an estimate of the RT provided that at least 45 ft lbs was obtainedifthespecimenswerNongitudinallyoriented. If the minimum value 'obtained was less than 45 ft-lbs, the RT NDT may e est mated as 20*F above the test temperature."
This procedure was applied to the A508 forging data, as summarized in Table 1 on page 6 of 11. The maximum RTNDT is 30'F, compared to the non beltline RT limit f 28'T used in the pressure temperature curves.
NDT
-1 d
Att:chment 1 to NLS8800063 P;go 2 cf 11 The 2'F increase in RT impacts the non beltline portions of the curves in Figures 3.6.1.a and 3N1.b of the Technical Specifications. Revised Figures 3.6.1.a and b are included as Attachment 2, updated to reflect the 2'F RT in rease. These revised pages replace the previous curves submitted wi$TProposed Change No. 48. These two figures also appear as Figures 2-1, 2-2, 2-3, 7-5, 7-6, and 7-7 of GE Report MDE 103 0986. Also included in this Attachment as page 8 of 11 is a revised Table 7 3 from MDE-103 0936, showing the revised temperature values in the non beltline region of Figures 3.6.1.a and 3.6.1.b.
Question 3 How many heats of Combustion Engineering weld metal fabricated with Linde 1092 flux were evaluated to determine that the lower limit of its NDT temperature is -50'F?
Response
The 50'F limit set for weld metal was an administrative lower limit for RTND , based on the determination that the RT determined from Charpy energy wasbigherthantheweldNDT. This appears t b he NRC to be an unacceptable basis for the -50'F RT values assumed for the Cuper welds. The NRC NDT recommendation is to use the RT upper bound value used in pressurized thermalshock(PTS) evaluations,"w$ichis:
Upper Bound RT NDT
~ "*"" NDT + #'
where Mean RT 56*F, and Ng ,17.p, ,,
Upper Bound RT ~~ '
NDT This increase in initial RT w for which weld chemistry data were unavai1Ne,ould to cause becomeweld the Heat 12420, limiting beltline material prior to 32 EFPY, However, a review of PTS evaluation data showed that a Linde 1092 weld was made with Heat 12420 in the beltline at Salem Unit 1 [5).
This is identical to the CNS weld. The as-welded chemistry for Heat 12420, 1092 Flux Lot 3708 at Salem Unit 1 is 0.22% Cu and 1.02% Ni. Phosphorus information was not provided. For the purposes of using Regulatory Guide 1.99, Revision 1, a phosphorus content of 0.020% is assumed. This chemistry data was used, along with the -22'F initial RT NDT' L" #***"*1"***
the weld metal fabricated with Linde 1092 flux.
Table 2 on page 7 of 11 shows the adjusted reference temperature (ART) for the limiting plate and the beltline welds. As shown, using the chemistry data from Salem 1, the welds are less limiting than the plate, even considering the higher initial RT In fact. Veld Heat 12420 could have a copper content as high as 0.28% witN.t becoming limiting. Therefore, the pressure-temperature curves in the surveillance report, and submitted in Change 48, are considered bounding for the beltline.
2
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. 'Attcchment l~ta N1.54800063.-
-Paga 3'ef 11 ~{
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vf .-Question 4 >
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i
.Are_the relationships 1in 1) and 2) mean values or upper bound? -Was there a
! statistical evaluation of the,deta?
, .e ;
RResponse: -
- ( . Refer,to Questions 1-~nd a 2.
.l 9
Fluence Evaluation :
- Question 1. <
How were the cross-sections, E>1MeV, for the copper and iron wires determined? l
.What spectra were used-for the iron 54 and copper-63 reactions? -
. Response- l Fe 54 (n.p) Mn 54 and Cu 63 (n.a) Co 60 cross section values for Cooper'were !
obtained from cross section functions and reaction rate ratios developed from '
- i. itest measurements. These measurements were taken from neutron energy spectral !
determinations for,BWRs and for the GE Test Reactor at Vallecitos. GE Report j NEDo 24792 [6), enclosed. describes the experiment in which neutron spectra - !
were determined at eight locations between the core shroud and the vessel inside wall at the Browns Ferry 3 plant. From this experiment, data functions "
were' derived _ relating cross section to water gap (distance from fuel to vessel
~
wall) for BWRs.- The use of test measurements to determine cross sections is .I expected to be more accurate than a method which uses a calculated spectral 'l s hape.
Question 2 i
Do the 2-signa deviations reported on pp 4-3 include uncertainties for I counting, weighting, water gap and capsule location with respect to the core and the pressure vessel? If it does not, what is the 2-signa deviation for j[
-the dosimetry estimates including all sources of uncertainty?
l Response ;
The 2a uncertainty reported includes uncertainties in determining the flux l from the dosimeter flux wires (e.g., counting, weighting, cross sections, ;
etc.).- The uncertainty associated with the lead factors is not reported, and ;
was not calculated. Instead, the lead factors were computed using conservative assumptions to assure that the vessel flux predicted from the l dosimeter results is conservative. The computational model used to determine -
lead. factors assumed the minimum vessel diameter and allowed for no water gap between the dosimeter o g the jnside vessel wall. The computational value of j dosimeter flux, 0.96x10 n/cm , 18 88 expected, slightly less than the i measured flux of 1.05x109n/cm 2. Therefore, combining the measured flux with [
its uncertainty factor of 1.25 and the conservative lead factor, gives a i conservative estimate of flux at the vessel 1/4 T. !
i e
j 1
3
Att:chment 1 to NLS8800063 Pega 4 cf 11 Question 3 Did your boundary condition input into the computer codes (DOT and SN1D) account for albedo neutrons at kT? Do the course mesh used in the computer programs provide adequate solutions for the neutron flux?
Response
The boundary conditions used in the computer codes did not account for albedo neutrons at the 1/4T. Comparisons of flux decrease through the vessel wall were made between the DOT two dimensional model, which stopped at the 1/4 T, and the SN1D one-dimensional model, which extended several centimeters further into the vessel vall. The rates of flux decrease at the 1/4 T in each model match closely, indicating insignificant flux build up due to reflected neutrons. Past flux analyses which modelled the entire vessel wall thickness, the biological shield wall and the annulus between have shown the reflected neutron contribution at the 1/4 T to be insignificant for neutron ener5 ies
>1MeV. There are lower energy neutron groups where reflected neutrons may be significant, but the >1MeV flux is not significantly affected.
! The flux computation is a combination of two dimensional and one-dimensional models. The two dimensional model aesh is described in the surveillance report. The one-dimensional model had about 110 radial intervals (versus 43),
with about 15 intervals for the vessel vall (versus 4). This combination of a somewhat coarse two dimensional model and a finer one-dimensional model provides adequate flux solutions, as shown by the agreement within 9% with the Cooper flux wire test results.
Pressure Temperature Curves Question 1 Where are thermocouples located that will be used to measure the minimum metal temperature of the beltline and closure flange (vessel and head) regions i during the leak and pressure tests (Figure 7 5)? During these tests what is the difference in temperature between the thermocouplca and the beltline and closure flange locations? Do administrative controls iden*ify to the operator which thermocouples must exceed the PT curves in Figure 7-6'.
Response
Figure 1 to this Attachment provides g'.neral locations of the thermocouples i
attached to the pressure vessel, fl.nge, and head regions. As shown, thermocouples are located at various locations on the vessel shell, flange, and heads, although none are placed on the vessel beltline region. Table 3 is a tabulation of all thermocouples which are read out on recorders in the Control Room.
Metal temperature on the beltline regions will be correlated with an existing vessel shell thermocouple (TE-69 J1) reading during the next cutage prior to performance of the hydrostatic pressure test. This vessel shell thermocouple reading, with the determined correction factor, will be used by the Control Room Operators to monitor beltline temperature during subsequent hydrostatic pressure testing. Separate thermocouples will be used to measure the metal temperature of the bottom head region. The vessel bottom head region is at a lower temperature than the remainder of the pressure vessel due to the influx 4-l 1
Attcchment 1 e,o NLS8800063 P:go 5 cf 11 of cooling water for the Control Rod Drive hydraulic units and the poor mixing characteristics brought about by the internal structure configuration of the region.
The District recognizes that different pressure-temperature limitations apply to certain pressure vessel regions and that appropriate thermocouples must be monitored for each identified vessel region. The appropriate thermocouple outputs will be identified to plant Operators for monitoring vessel temperatures and procedurally controlled during hydrostatic testing and other plant evolutions where thermal and pressurization limitations apply.
5-L
_ Attcchment' 1 to NLS8800063 2 , ..g ',-
Pcg3 6 cf -11' 3
4 '
Table 1 f.
INITIAL RTST ESTINATES FOR COOPER-VESSEL A508 CLASS-2 FORGINGS t.
'u Minimum.
Charpy Test -Charpy L- . Temperature. Energy NDT' RT NDT.
c - onant (*F) -(ft-lbg1 M Q
? -
-Head Flange ,10 74 -
20- '20 a Vessel Flange 10 62 10 10 Mozzles t
.; Recire. Outlet 10 58 0- .10 Recirc. Inlet' 10 35 10 30 Steen Outlet 10 -- 31 N/A 30 Feedwater 10 48 0 10 Core Spray 10 45 0 10 Head Spray 10 69 0 10 Vent 10 74 0 10 q Jet Pump Instrument 10 134 -10 10 CRD Ret. urn in 87 19 to l
l 1
1 l
l i
, i l
- The RTNDT was taken as 20'F because of the NDT. RTNDT Per MTER 5-2 is 10'F.
i
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- = - - -
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A t ta:hme2L 1 te CLS8800063 e ., Paga 7 cf 11.
i
/ Table 2 ADJUSTED REFERENCE TEMPERATURES FOR BELTLINE MATERIALS AT 32 EFPY Survalliance Initial 1092 Test RT HDr . Shift ART l 'i ligat Flux Lot 1Gu 12., Factor (
C2274 1 - 0.20 0.010 2.39 14 157 171
. I r
l Welds:
l I
27204 &
l l 12008 3724 0.19 0.013 1.62 22 110 88 12420 3724 0.22" 0.020b 1.62 -22 151 ' 129 I
, i l i b
12420 3708 0.22" 0.020 1,62 22 151 129 l
21935 3869 0.20 0.016 1.62 22 125 103 Hypothetical Veld:
, 0.28 0.020 1.62 -22 188 166
- Based on data from Salem 1 PTS evaluation, b
Assumed upper limit for weld process.
9
Attachrent 1 to NLS8800063
,, PsTs 8 of 11 Revissd Tabis 7-3 GE Report MDE-103-0986 Table 7-3
- PRESSURE-TEMPERATURE,VA1.UES FOR FICURE 7-6 (CURVE B) AND 7-7 (CURVE C)
. Pressure Curve B Curve C (esi) Temo. (*F) Temo. (*F) Remarks 0 80' 80 Boltup Temperature 48 80 80 Non-beltline limits Curve C i 50 80 82 60 80 94 70 80 102 80 80 110 90 80 117 95 80 120 Non-beltline' limits Curve.B 100 84 124 110 89 129 120 94 134 130 99 139 140 104 144 150 108 148 160 112 152 170 115.5 155.5-180 ~119 159 190 122 162 200 125 165 210 127.5 167.5 220 130 170 230 132.5 172.5 i 240 135 175 250' 137 177 260 139 179 270 141 181 280 143 183 290 145 185
-300- 147 187 Increment pressure 20 psi 320 150 190 340 153 193 360 157 197 380 160 200 400 162.5 202.5 420 165 205 440 168 208 460 170 210 480 172 212 500 174.5 214.5 520 176.5 216.5 540 178.5 218.5 550 179.5 219.5 Beltline becomes limiting 560 181 221 580 184.5 224.5 7-11 !
m: .
, , , +
Attschment 1 to'NLS8800063-
- Pcga 9 of-11~
L1 - TABLE 3-
- Recorder TR-90
. Thermocouple
-Recorder Input- ' Thermocouple Location ' Identification Black' ; Vessel Flange: TE-69-A2 Red. Vessel Wall Adjacent .to Flange TE-69-82
. Recorder TR-89 Thermocouple:
-Recorder Input Thermocouple Location Identification ^
- 00 'Feedwater Nozzle N4B End- .TE-69-D1 01- Feedwater' Nozzle'N4B Inboard <TE-69-D2-L 02 Feedwater Nozzle N4D End. 'TE-69-El L' '03 Feedwater: Nozzle N4D Inboard TE-69-E2 04 Vessel Top Head' Adjacent to Flange TE-66-Al-05 Vessel; Top Head. Flange. TE-66-B1-06 -Vessel Bottom Drain Line 'TE-106 07 , Vessel Wall Below Feedwater Nozzle TE-69-J1 08 Vessel Wall Above Botton Head TE-69-H1
, 09 Vessel Above Skirt Junction 1TE-69-Fl' 10 -Vessel Botton Head TE 69-L1 Ell- Vesnel Skirt Near Junction TE 69 K1 9-
Attachm:nt 1 to NLS8800063 Page 10 of 11 2 MAGNETIC ALLY CLAMPED TO HE AD 2 TO HEAD FLANGE iVESSEL HEAD (2) M w
HEAD FLANGE ]o o A
TE-69-A2 O ll
[ TE-60-82 O VESSEL FLANGE C a. $ a.
2 2 e e U 1 U E E
_g VESSEL SHELL ,
N MS) 34 LOCA flONS C
( THERMOCOUPLE TR 2 INPUTS 89 F.W.
HOZZLE TR 12 INPUTS 90 9-21 P ANEL VESSEL SKIRT
( /
t \
\ /
l DOTTOM HE AD
/N s ,/ - DR AiN tine X
[ s i t t Y
l TO CLE ANUP SYSTEM t
l l THERMOCOUPLE PAD LOCATIONS l
FIGURE 1
'Attichm2nt 1 to'NLS8800063:
Pags 11 of 11,
.-REFERENCES
.[1] Hodge, J . M . ', "Properties of Heavy Section Nuclear Reactor Steels,"
- . Welding Research Council Bulletin 217,- July.1976.
~
-[2] .LaSalle ' County ~ Station Final Safety Analysis Report, Response to'NRC
~
Question'121.11,-Amendment 46, August.1979.
1[3] .LaSalle County Station Final Safety Analysis Report, Response to NRC
,, Question'121.17, Amendment 54, January 1981.
[4] Nuclear: Regulatory ' Commission Branch - Technical Position MTEB 5-2, "Fracture Toughness requirements," Revisions 1, July 1981.
[5] Pressurized Thermal Shock Evaluation for the Salem Units, Public Service Electric & Gas Company Report NRJ-060, Revision 0, January 1986.
[6]' Martin, G. C., "Browns Ferry Unit 3 In-Vessel Neutron Spectral-Analysis',"
3 General Electric Company Report NEDO-24793, August 1980.
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