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Category:CORRESPONDENCE-LETTERS
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 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 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 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 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 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 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 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 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 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 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 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 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 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) 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 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 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, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits 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 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld 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 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 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 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 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 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 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 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 ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 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 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 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 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 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 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 ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld 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 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 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 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 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 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 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 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 ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 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 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 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 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 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 ML18033B5031990-08-31031 August 1990 Forwards Financial Info Required to Assure Retrospective Premiums,Per 10CFR140 & 771209 Ltr ML20059E1741990-08-31031 August 1990 Informs That Plant Restart Review Board & Related Functions Will Be Phased Out on Date Fuel Load Commences 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 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 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 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 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 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 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 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) 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 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 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 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 ML20043G4901990-06-14014 June 1990 Forwards Tabs for Apps a & B to Be Inserted Into Util Consolidated Nuclear Power Radiological Emergency Plan 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) 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 ML18033B3651990-06-0808 June 1990 Forwards Revised Page 3.2/4.2-13 & Overleaf Page 3.2/4.2-12 to Tech Spec 289, RWCU Sys Temp Loops. ML18033B3391990-06-0404 June 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-259/90-08,50-260/90-08 & 50-296/90-08.Corrective Actions: Individual Involved Counseled on Importance of Complying W/Approved Plant Procedures When Performing Assigned Tasks ML20043D3251990-06-0101 June 1990 Responds to NRC 900502 Ltr Re Notice of Violation & Proposed Imposition of Civil Penalty.Corrective Actions:Snm Program Action Plan Being Developed & Implemented,Consisting of Improved Training for Control Personnel & Accountability ML18033B3551990-05-31031 May 1990 Forwards Response to 891219 Request for Addl Info on Hazardous Chemicals Re Control Room Habitability ML20043C1951990-05-30030 May 1990 Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues ML20043C0601990-05-29029 May 1990 Forwards Response to Violations Noted in Insp Repts 50-259/90-12,50-260/90-12 & 50-296/90-12.Util Admits Violation Re Access Control to Vital Areas,But Denies Violation Re Backup Ammunicition for Responders ML18033B3351990-05-25025 May 1990 Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability. Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issues Subj to Listed Conditions ML18033B3221990-05-21021 May 1990 Forwards Rev 1 to ED-Q2000-870135, Cable Ampacity Calculation - V4 & V5 Safety-Related Trays for Unit 2 Operation, as Followup to Electrical Insp Rept 50-260/90-13 Re Ampacity Program ML18033B3101990-05-18018 May 1990 Responds to NRC 900417 Ltr Re Violations Noted in Insp Repts 50-259/90-05,50-260/90-05 & 50-296/90-05.Corrective Action: Senior Reactor Operator Assigned to Fire Protection Staff for day-to-day Supervision of Fire Protection Program ML20043A6101990-05-15015 May 1990 Forwards Rev 16 to Security Personnel Training & Qualification Plan.Rev Withheld (Ref 10CFR2.790) ML20043A4091990-05-14014 May 1990 Forwards Rev 14 to Physical Security/Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20043A4081990-05-14014 May 1990 Forwards Rev 15 to Physical Security/Contingency Plan, Consisting of Changes for Provision of Positive Access Control During Major Maint & Refueling Operations to One of Two Boundaries.Rev Withheld (Ref 10CFR73.21) ML18033B2921990-05-0909 May 1990 Provides Info for NRC Consideration Re Plant Performance for Current SALP Rept Period of Jan 1989 - Mar 1990.Util Believes Corrective Actions Resulted in Positive Individual Changes & Programmatic Upgrades ML20042F7401990-05-0404 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' TVA Will Finalize Calculations for Switch Setpoints Prior to Units Restart ML20042F7701990-05-0404 May 1990 Provides Results of Review of Util 890418 Submittal Re Supplemental Implementation of NUMARC 87-00 on Station Blackout.Implementation of 10CFR50.63 Consistent W/Guidance Provided by NUMARC 87-00 ML20042F3721990-05-0202 May 1990 Forwards Corrected Monthly Operating Repts for Jan-June 1989 & Aug 1989 - Jan 1990.Discrepancies Involve Cumulative Unit Svc Factors & Unit Availability Capacity Factors ML18033B2631990-04-12012 April 1990 Forwards Response to NRC 900212 Request for Info Re Power Ascension & Restart Test Program at Unit 2.Util Has Refined Power Ascension Program to Be More Integrated & Comprehensive ML18033B2551990-04-0909 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Repts 50-259/89-16,50-260/89-16 & 50-296/89-16.Corrective Actions: Contractor Will Perform Another Check Function Review for Mechanical Calculations & Area Walkdowns Will Be Conducted ML18033B2431990-04-0202 April 1990 Responds to NRC 900302 Ltr Re Violations Noted in Insp Repts 50-259/89-43,50-260/89-43 & 50-296/89-43.Corrective Action: Surveillance Insp Revised to Prevent Removal of All Eight Emergency Equipment Cooling Water Pumps from Water 1990-09-19
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TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNESSEE 374o1 SN 157B Lookout Placo JUL 151988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Cen: ' emen:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260
) 50-296 BROWNS FERRY'dUCLEAR PLANT (BFN) - RESPONSE TO NRC INSPECTION AND ENFORCEMENT BULLETIN (IEB) 85-03 SUPPLEMENT 1 AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONCERNINC RESPONSES TO IEB 85-03 In responso to supplement 1, NRC Bulletin No. 85-03 dated April 27, 1988, TVA is providing the information requested in enclosure 1 to this letter. This information is provided under oath and affirmation as requested.
Enclosure 2 contains the information requested by letter from K. P. Bare to S. A. White dated April 1, 1988, regarding IEB 85-03 for BFN. The Apell 1, 1988 letter requested additional information to responses submitted in TVA letters dated May 13, 1986, Eaptember 13, 1986, and May 1, 1987.
Enclosure 3 includes revised table 1, originally presented.in the May 13, 1986 letter to J. N. Grace from R. Gridley with additional information provided in the September 30, 1986 letter to J. N. Grace from R. Gridley, for both high pressure coolant injection (HPCI) and reactor coro isolation cooling (RCIC) including maximum differential pressur6s and ad<titional valves to address inadvertent valve mispositioning. Differential pressuras have been provided based on preliminary calculations for inadvertent valve mispositioning. TVA will part,1cipate in the Bolling Water Reactor Owners Group (BWROC) and utilize worst caso differential pressures for each safety related valvo function as deturmined by BWROG generic methodology for inadvertent valve mispositioning.
These preliminary calculattors may be revised based on the BWROG methodology.
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8807260014 000715 PDR ADOCK 05000259 PNV ~
jj d G f An Equal Opportunity Empioyer .
t_.__
U.S. Nuclear Regulatory Comission { { g' Sumary statements of comitments contained in this submittal are provided in enclosuro 4.
If there are any questions, please telephono J. L. Turner at (205) 729-2853.
Very truly yours, TE ESSEE V LEY AUTHORITY R. Geldley, D1'ector Nuclear Licon.Ing and Regulatory Affairs Subscribedanjsworn bo(ore no on t is ./JNay of / 988.
0N Notary Public h
My Comission Expires Enclocures cc (Enclosuro):
Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Com lssion one White Flint, North 11555 Rockvillo Piko Rockville, Maryland 20852 Mr. F. McCoy, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Comission Region 11 101 Mariotta Street, NW, Suite 2900 Atlanta, coorgia 30323 Browns Ferry Resident inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611
ENCLOSURE 1 RESPONSE TO NRC BULLETIN NO. 85-03, SUPPLEMENT 1 DATED APRIL 27, 1988 Item a Review and document the design basis for the operation of each valve. This documentation should include the maximum dif ferential pressure expected during both opening and closing of the valve for both normal and abnormal events to the extent that the events are included in the existing, approved design basis (i.e. , the design basis documented in pertinent licensco submittals such as Final Safety Analysis Report analysos and fully approved operating and emergency procedures, etc.). In addition, when dotormining the maximum differential pressure for valves that can be inadvertently mispositioned, the fact that the valvo must be able to recover from such mispositioning should be included.
TVA Response Table 1 of TVA's response to NRC Bulletin 85-03 for BFN, which was originally presented in the May 13, 1986 letter to J. N. Craco from R. Celdley with additional information provided in the September 30, 1986 lottor to J. N. Crace from R. Cridley, has been revised to includo all motor oporated valves (MOVs) in the HPCI and RCIC systems. Enclosure 3 is the revised tablo 1 and includes applicable changes. ,
Table 1 has also boon revised to include inadvertent equipment operation to verify that required valves are able to recover t' rom an inadvertent mispositioning. Maximum differential pressures for recovering from inadvertent mispositioning have been included in the revision to tablo 1.
The HPCI portion of table 1 has been revised to ohow the normal position of MOV 73-81 as closed verses open. This reflects the changing of this valvo ;
position on DFN drawings and procedures.
Item b Perform action item b of the original bulletin for any additional valvos identified above.
1 The intent is to provido assurance that a pragram exists for rotecting and I setting valve operator Switenos to ensure a high rollability of safety system l valves. If changing the switch cottings is not sufficient to ensuro the capability for repositioning a particular mispositioned valvo, a justification for continued operation should be provided in the bulletin responso if tho l licensco does not elect to implement additional actions, cuch au !
administrativo or procedural controls or equipment modifications, to minimize the likelihood of valve malfunction.
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, 1 TVA Response l Establishment of correct switch sottings, which was previously completed as reported in the May 1, 1987 letter from R. Gridley, is being reperformed.
This is due to revision of TVA's General Construction Specification G-50 (Torque and Limit Switch Settings for Motor Operated Valves) approved December 18, 1987. '
This new revisten chanson the technique for setting torque switches. The old cathod for uetting torque switches used at least the minimum torque switch setting provided by the vendor. The new method sets torque switches using actual thrust values determined during valve testing.
The new settings are based upon calculations being supplied to TVA from the original valve sanufacturers. Theso calculationc includo required thrusts for both opening and closing valves under differential pressure. 'ho maximum thrust values and the limiting structural components for both opening and closing these valvec are also provided by the manufacturers I Reestablishme'.t of cor.ect switch settings (item b of NRC bulletin 85-03) will be completed by each respective unit's startup.
Items e and_d_
Pecrotm action item e and d of the ort t inal bulletin for any additional valves identified above.
Tyt Response The schedule for implamenting items e and d to addrens inadvertent va.1vo mispositioning will remain the same se previously committed to fa the May 1,1987 supplemental respo.tso to IE Bulletin 85-03.
1 Item e I Within 30 days of receipt of this supplement, sabmit a written report to the NRC that, for any additienal valsos: (1) provides the revised results of item a above and (2) contains a schedule for completion cf L'.e'ms b through d above, i
TVA Responso Enclosure 1 of this letter supplicA the infocmation to the request in item e.
Item f l
Envise the report requestod by the original bullot!n to include any addltlonal valves. This revised report shsLL bo submitted to the NdC within 60 days of e mplet ion of the program (or the tod'.tional valvos, j l
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. . -1 TVA Response The schedulo for issuing the final report addressing inadvertent valve mispositioning will remain as previously committed in the May 1, 1987 ,
response, 60 days af ter completion of the program for each respective unit.. .
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- ENCLOSURE 2 RESPONSE TO HRC REQUEST FOR ADDITIONAL INFORMATION DATED APRIL 1, 1989 IRB 85-03 Item 1 Revise table 1 of enclosure 1 of the responso dated September 30, 1986, to include the following MOVs, or justify their exclusion. As required by Action Item a of the bulletin, assume inadvertent equipment oporations. How would HPCI or RCIC injection bo ensured if these injcetion valve test valvos were to be (a) actuated inadvertently to the closed position upon intended initiation of the system or (b) left closed inadvartently?
(a) HPCI MOV 73-34 is shown normally open in Zonc E-3 of Drawing 47W610-73-1, revision D, and ac MOV 8 on page 68 of BWROG Report NEDC-31322 dated September 1986.
(b) RCIC HOV 11-37 is shown normally open in Zone E-4 of Drawing 47W610-71-1, revision B, and as MOV 8 on page 72 of the BWROG Report.
P TVA Response (a) High-pressure coolant injection (HPCI) motor operated valvo (MOV) 73-34 (Injection Valve Test Valve)
(b) Reactor core isolation cooling (hCIC) MOV 71-37 (Injection Valvo Tdst Valve)
The valves are included in the revision to table 1 to address inadvertent valve mispositioning.
Itom 2 Revise table 1 of enclosure 1 of the response dated September 30, 1986, to include the following MOVs, or justify their exclusion. According to pages 58 and 62 of the BWROG Report (for HPCI and RCIC respectively), cach of those vacuum breaker line isolation valves has a safety action for closing.
(a) HPCI MOV 73-64 is shown normally open in Zonc F-2 of Drawing 47W610-73-1, revision D, and as MOV III on Pago 71 of the BWROG Report.
(b) RCIC MOV 71-59 is shown normally open in Zone G-2 of Drawing 47W610-71-1, revision B, and as MOV VII on Pago 74 of the BWROG Report. ,
l TVA Responso (a) HPCI HOV 73-64 (Vacuum Dreaker Line Isolation Valvo)
(b) RCIC MOV 71-59 (Vacuum Breaker Lino Isolation Valvo) 1 These valves are included in the revision to tablo 1 for completeness but they l have no activo safety function. These valves are normally open and !
deenergized to inhibit inadvertent closuro, l l
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The Owner's Group Report (NEDC-31322) Lists these valves with an active safety function to close to provido the requlred isolation. These valves are not primary containment isolation valves at UFN. Any leakage following a loss of coolant accident (LOCA) will be controlled by two primary containment check valves (73-24,73-609 and 71-14,71-580) for HPCI and RCIC respectively.
These valves are included in operating instruction to be closed following a LOCA after HPCI and RCIC have been utilized and steam pressure has been reduced such that these systems are no longer required to function. The remote manual closure of these valves would serve to minimize leakage from primary containment but is not mandatory.
Item 3 Revise table 1 of enclotcre 1 of the response dated September 30, 1986, to includo HPCI MOV 73-36, or justify its exclusion. This CST Test Return Valve is shovn normally closed in Zot.e C-3 of Drawing 4 7W610-73-1, .evision D, and as MOV 6 on Page 68 of the BWROG Report. According to Page 55 of that report, this valve has no safety action; however, utilities are expected to report differential pressures for testing, per Note "c" on Page 66.
TVA Responso HPCI HOV 73-36 (Redundant Shutof f Test Valve to C'iT) . I Tnis valve has been added to table 1 for completeness but has no active"safety function. This valve is normally closed and is opened for testing HPC1/RCIC. ;
The dif ferential pressure, based on actual operating experience, has been Provided as requested. HPCI and RCIC will perform thelr-intended safety ,
function with MOV 73-35 and MOV 71-38 closed regardless of the poeition (open or closed) of MOV 13-36. )
Item 4 Revise table 1 of enclosure 1 of the responso dated September 30, 1986, to include values of differential pressure for opening the following valves, or ,
justify exclusion of these pressures. How would suction from the CST {
[ items 4(a) and 4(b)] or steam supply to the RCIC Turbine [1tems 4(c)) be '
ensured if these valves were to be (a) actuated inadvertently to the closed i position upon intended initiation of the system or (b) left closed '
inadvertently? I (a) HPCI MOV 73-40 (CST Suntion Valvo) is shown normally open in Zono B-S of l Drawing 47W610-73-1, revision D, and as MOV 3 on Page 68 of the BWROG Report.
(b) RCIC MOV 71-19 (C0T Suction Valvo) is shown normally open in Zono C-6 of Drawing 4 7W610-71-1, rettsion B, and Page 72 of the BWROG Report.
(c) RCIC MOV 71-9 (Trip and Throttle Valve) is shown normally open in Zono C-8 of Drawing 47W610-71-1, revision B, and as MOV X on Page 74 of the BWROG Report.
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TVA Response (a) HPCI MOV 73-40 (CST Suction Valvo)
(b) RCIC MOV 71-19 (CST Suction Valve)
(c) RCIC MOV 71-9 (Telp and Throttle Valvo)
Maximum opening differential pressures have been included in the revision to table 1 for the above valves to address inadvertent valve mispositioning.
Item 5 Reviso table 1 of enclosure 1 of the responso detod September 30, 1986, to include values of differential pressure for opening supprossion pool suction isolation MOVs 71-17 and 71-18, or justify exclusion of these pressures.
According to Pago 59 of the BWROG Report, these valves have safety actions for opening and closing. These valves are shown as MOVs 4 and 4a on Pago 72 of the BWROC Report.
TVA Response (a) RCIC MOV 71-17 (Suppression Pool Suction Valvo)
(b) RCIC MOV 71-18 (Suppression Pool Suction Valvo)
The maximum opening differential pressures are supplied in the revision to table 1. These valvos are remote manually opened by the operator on low CST level or high suppression pool level.
. Item 6 The proposed program for action b, c, and d of the bulletin is incomplete.
Provide the following details as a minimum:
(a) commitment to a training program for settlns switches and maintaining valva operators, (b) cammitment to justify continued operation of a valvo determined to bo inoperable, (c) description of a method possibly needed to extrapolato valvo stem thrust determined by testing at loss than maximum differential' pressure, (d) justification of a possible alternative to testing at maximum differential pressure at the plant, (e) consideration of pipe break conditions as required by the bulletin, (f) stroke testing when necessary to meet nulletin requirements, and (g) consideration of applicable industry recommendations in the preparation of proceduros to ensure maintenance of correct switch settings.
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TVA Response The following section provides additional information requested on our proposed program for action items b, c, and d of IE Bulletin 85-03,
- s. Training Program - All electrical and mechanical craft personnel are required to successfully complete training prior to independent maintenance of valvo actuators. This training includes Limitorquo salvo actuators, Rotock valve actuators, and MOVATS (Motor Operated Valve Analysis and Teeting System).
- b. Any valve that is determined to be inoperaato will bo justified for continued operation as applicable por plant technical specifications.
- c. Differential pressure testing has not been performed at less than tho
- calculated values of maximum differential pressure specified on table 1 of the TVA response to IE Bullotin 85-03 to date. Any test results at less than the maximum differential pressure specified in table 1 will-includo a justification in the final report. Justifications different from stem thrust extrapolation may be utilized.
- 3. Justification for testing at less than the maximum differential pressure, if applicable, will be supplied in the final report. Valvos will be justified on an individual basis due to the number of variables involved with each valve operator,
- e. Pipo break conditions were included in calculation of maximum differential pressure and establishment of correct switch settings as required by the bulletin. The methodology agrees with the approach defined in the BWROG report section 1.4.
- f. Stroke testing is currently being performed as part of valvo maintenanco procedures on each motor operated valvo to verify propor implemer.tation of switch sottings. Before a valvo operator is returned to servico, applicable valvo surveillance instructions are performed to verify operability.
- g. Industry recommendations for procedures to ensuro maintenanco of correct switch settings are considered by poroonnel involved in IE Bulletin 85-03. Browns Ferry utilizes the Nuclear Network and Operation Experience Reports to keep abreast of current industry practicos involving all phases of MOV work. Additionally, TVA has a MOV Users Group which meets periodically to address issues and problems associated I with MOVs.
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ENCLOSURE 3 TABLE 1 Valve Valve Max. Differential Normal Safety Function Pressure (lbjin'd)
Unique No. Description Position Description Opening Closing 73-2 HPCI steam Open Valve must close to 11051 1105 i solation isolate containment valve in case of a HPCI steam line break.
73-3 HPCI steam Open Valve must close to 11051 1105 isolation isolate containment valve in case of a HPCI steam ' ~
line break.
73-16 HPCI steam Closed Valve must open on HPCI 1105 supply valve initiation to supply __ ,
reactor steam to the turbine 73-26 HPCI suction Closed Must open to allow the 50.3 valve to the 40.6 HPCI pump to take suppression suction from the torus pool and must close if isolation of primary containment is required 73-27 HPCI suction C1csed Must open to allow the 50.3 41.5 valve to the HPCI pump to take suppression suction from the torus pool and must close if isolation of p-iman containment is required 73-30 HPCI minimum Closed Must both open and close 1361.8 1439.1 recirculation to provide adequate flow valve pump recirculation flow and adequate cooling flow to the reactor vessel respectively 73-341 HPCI Open Valve must remain open injection 1363.3 __
to inject water to the valve test reactor vessel.
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ENCLOSUdE 3
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TABLE I (Continued)
Max. Differential '
Valve valve Normal Safety function Pressure (1blin'd)
Unique No. Description Position Description Opening Closing 73-35 HPCI test Closed Must close on HPCI __ 1250
return to initiation to ensure condensate adequate flow to the reactor vessel.
73-36' Redundant Closed Valve has no safety __ 1250**
shutoff to function; redundant condensate shutoff to CST for MOVs ,
storage tank 73-35 and 71-38.
73-40 HPCI suction Open Valve must close when 43.6I 95.2 valve to the HPCI is aligned to condensate take suction from the storage tank. suppression pool.
73 -44 HPCI discharge Closed Must open on HPCI 1230.3 __
injection initiation to inject valve. water to the reactor vessel through the feedwater system,73-642 Vacuum breaker Open Valve must remain open 2 line isolation to prevent water from valve being drawn up into turbine exhaust line. .
73-81 HPCI steam Closed Must close to isolate __ 1105 supply bypass primary containment valve on a HPCI steam .,
line break.
f Valve is included for completeness; it has no motar-operated safety function.
utsed on actual operating experience in test return mode.
NOTE 1 - These valves and maximum differential pressures have been included to address inadvertent valve mispositioning.
NOTE 2 - This valve is blocked from inadvertent operation at the motor
, control center. .
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4 ENCLOSURE 3 TA8LE 1 (Continued)
Max. Dif terential Valve Valve Normal Safety Function Pressure (1blin'd)
Unique No. Description Position Description Opening Closing 71-2 RCIC steam Open Valve must close and 1105I 1105 isolation isolate containment valve on RCIC steam line break.
71-3 RCIC steam Open Valve must close and 11051 1105 i s olation isolate containment r-valve on RCIC steam line break.
71-8 RCIC steam Closed ' Valve must be open on 1105 __ .
supply valve RCIC initiation to supply reactor steam to the turbine.
71-9 RCIC Open Valve must spring close 11051 01 turbine on RCIC isolation signal stop valve to stop the turbine.
71-17 RCIC suction Closed Valve must close if 147.7 39.4 valve to the opened and containment suppression isolation is required.
pool 71-18 RCIC suction Closed Valve must close if 147.7 39.4 valve to the opened and containment
- suppression isolation is required.
pool 71-19 RCIC suction Open Valve must close when 140.91 37.5 valve to the RCIC is aligned to take s condensate
- p. suction f rom the storage tank suppression pool.
71-25 RCIC cooling Closed Valve must be open on 1342.9 water supply RCIC initiation to valve ensure an adequate cooling supply.
71-34 RCIC minimum Closed Must both open and close 1335.8 1469.7 recirculation to provide adequate pump
- flow valve recirculation firw and . ,
adequate system ..ow to the vessel, respectively.
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ENCLOSURE 3 TABLE 1 (Continued)
Max. Olfferenti 1 Valve Valve Normal Safety Function Pressure (1blin'4 d )
Unique No. Description Position Description Opening Closing 71-37I .RCIC injection Open Valve must remain open 13401 ~~
valve test to inject water to the valve reactor vessel.
71-38 RCIC test Closed Valve must close on an __ 1200**
return to initiation signal while condensate in the test return mode to enssee adequate flow to the reactor vessel. <
71-39 RCIC discharge Closed Valve must open on RCIC 1254.3 __
injection initiation to inject valve. water to the reactor vessel through the feedwater system.71-592 Vacuum breaker Open Valve must remain open 2 line isolation to prey t water f ronu-valve being di..m up in>c' turbine exhaust j 4ine, j e
at'
- Valve is included for completeness, it has no motor-operated safety function.
Based on actual operating experience in test return mode.
4 NOTE 1 - These valves and maximum differential pressures have been included to address inadvertent valve mispositioning.
NOTE 2 - This valve is blocked from inadvertent operation at the moter, control center.
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ENCLOSURE 4 COMMITHENTS MADE IN TilIS SUBMITTAL
- 1. Re-est ablistunent of switch sett.'.ngq wLil be completed by each respectLvo unit's startup.
.