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Category:CORRESPONDENCE-LETTERS
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability ML20217A5911999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issues Matrix Encl 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics ML20212J7431999-09-30030 September 1999 Forwards Insp Repts 50-266/99-15 & 50-301/99-15 on 990830- 0903.No Violations Noted.Inspectors Concluded That Util Licensed Operator Requalification Training Program Satisfactorily Implemented NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel ML20212K7651999-09-29029 September 1999 Forwards Insp Repts 50-266/99-13 & 50-301/99-13 on 990714-0830.No Violations Noted.Operators Responded Well to Problems with Unit 1 Instrument Air Leak & Unit 2 Turbine Governor Valve Position Fluctuation ML20212D5771999-09-15015 September 1999 Discusses Review of Response to GL 88-20,suppl 4,requesting All Licensees to Perform Ipeee.Ser,Ter & Supplemental TER Encl ML20211Q6451999-09-0808 September 1999 Forwards Operator Licensing Exam Repts 50-266/99-301OL & 50-301/99-301OL for Exams Conducted on 990726-0802 at Point Beach Npp.All Nine Applicants Passed All Sections of Exam ML20211Q4171999-09-0606 September 1999 Responds to VA Kaminskas by Informing That NRC Tentatively Scheduled Initial Licensing Exam for Operator License Applicants During Weeks of 001016 & 23.Validation of Exam Will Occur at Station During Wk of 000925 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump ML20211K5261999-08-31031 August 1999 Forwards Insp Repts 50-266/99-14 & 50-301/99-14 on 990726- 30.Areas Examined within Secutity Program Identified in Rept.No Violations Noted ML20211F6941999-08-27027 August 1999 Provides Individual Exam Results for Applicants That Took Initial License Exam in July & August of 1999.Completed ES-501-2,copy of Each Individual License,Ol Exam Rept, ES-303-1,ES-303-2 & ES-401-8 Encl.Without Encl NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months ML20211E8791999-08-24024 August 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Point Beach Nuclear Power Plant,Units 1 & 2.Licensees Provided Requested Info & Responses Required by GL 96-01 ML20211F1501999-08-24024 August 1999 Submits Summary of Meeting Held on 990729,in Region III Office with Util Re Proposed Revs to Plant Emergency Action Level Criteria Used in Classifying Emergencies & Results of Recent Improvement Initiatives in Emergency Preparedness 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached ML20210L9141999-08-0404 August 1999 Informs That Versions of Info Re WCAP-14787,submitted in 990622 Application for Amend,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210K5221999-08-0404 August 1999 Discusses Point Beach Nuclear Plant,Units 1 & 2 Response to Request for Info in GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 ML20210G6011999-07-30030 July 1999 Discusses 990415 Complaint OSHA Received from Employee of Wisconsin Electric Power Co Alleging That Employee Received Lower Performance Appraisal for 1998 Because Employee Raised Safety Concerns While Performing Duties at Point Beach NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal ML20210H0211999-07-28028 July 1999 Forwards Insp Repts 50-266/99-09 & 50-301/99-09 on 990528-0713.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210G2441999-07-26026 July 1999 Discusses 990714 Meeting with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 ML20209H5471999-07-14014 July 1999 Forwards Insp Repts 50-266/99-12 & 50-301/99-12 on 990614-18.One Violation Noted,But Being Treated as non-cited violation.Long-term MOV Program Not Sufficiently Established to close-out NRC Review of Program,Per GL 89-10 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20196J4161999-06-30030 June 1999 Discusses Relief Requests Submitted by Wisconsin Electric on 980930 for Pump & Valve Inservice Testing Program,Rev 5. Safety Evaluation Authorizing Relief Requests VRR-01,VRR-02, PRR-01 & ROJ-16 Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions ML20196D4931999-06-18018 June 1999 Forwards Insp Repts 50-266/99-08 & 50-301/99-08 on 990411- 0527.No Violations Noted.Operator Crew Response to Equipment Induced Challenges Generally Good.Handling of Steam Plume in Unit 1 Turbine Bldg Particularly Good ML20195J9471999-06-16016 June 1999 Discusses Ltr from NRC ,re Arrangements Made to Finalized Initial Licensed Operator Exam to Be Administered at Point Beach Nuclear Plant During Week of 990726 ML20196A2931999-06-16016 June 1999 Ack Receipt of Transmitting Changes to Listed Sections of Point Beach Nuclear Plant Security Plan & ISFSI Security Plan,Submitted IAW 10CFR50.54(p).No NRC Approval Is Required Since Changes Do Not Decrease Effectiveness ML20195J9251999-06-14014 June 1999 Discusses 990610 Telcon Between Wp Walker & D Mcneil Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Point Beach Nuclear Power Plant for Week of 990816 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 ML20206T3691999-05-17017 May 1999 Ltr Contract,Task Order 242 Entitled, Review Point Beach 1 & 2 Conversion of Current TS for Electrical Power Systems to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20206N5561999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Point Beach Npp.Organization Chart Encl ML20206P2551999-05-12012 May 1999 Forwards Handout Provided to NRC by Wisconsin Electric at 990504 Meeting Which Discussed Several Recent Operational Issues & Results of Recent Improvement Initiatives in Engineering ML20206N5331999-05-12012 May 1999 Forwards RAI Re & Suppl by Oral Presentation During 980604 Meeting,Requesting Amend for Plant,Units 1 & 2 to Revise TSs 15.3.12 & 15.4.11 ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure ML20206K0391999-05-0707 May 1999 Forwards Insp Repts 50-266/99-06 & 50-301/99-06 on 990223- 0410.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure NPL-99-0242, Submits Commitment Schedule Update,Per GL 95-07 Re Pressure Locking & Thermal Binding of safety-related power-operated Gate Valves.Unit 1 Block Valve Replacement Will Be Performed During Upcoming 1999 U1R25 Outage1999-04-27027 April 1999 Submits Commitment Schedule Update,Per GL 95-07 Re Pressure Locking & Thermal Binding of safety-related power-operated Gate Valves.Unit 1 Block Valve Replacement Will Be Performed During Upcoming 1999 U1R25 Outage NPL-99-0246, Forwards 1998 Annual Monitoring Rept, for Pbnps Units 1 & 2.Revised ODCM & Environ Manual Are Encl1999-04-27027 April 1999 Forwards 1998 Annual Monitoring Rept, for Pbnps Units 1 & 2.Revised ODCM & Environ Manual Are Encl ML20206C2361999-04-22022 April 1999 Forwards 1998 Annual Rept to Stockholders of Wepc Which Includes Certified Financial Statements,Per 10CFR50.71 NPL-99-0230, Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC1999-04-19019 April 1999 Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC 05000301/LER-1999-002, Forwards LER 99-002-00 Re Discovery That Cable Necessary to Provide Plant Parameter Required to Be Monitored for App R Safe SD Location Was Not Routed Independent of Appropriate Fire Zone.Commitments in Rept Indicated in Italic1999-04-16016 April 1999 Forwards LER 99-002-00 Re Discovery That Cable Necessary to Provide Plant Parameter Required to Be Monitored for App R Safe SD Location Was Not Routed Independent of Appropriate Fire Zone.Commitments in Rept Indicated in Italics NPL-99-0219, Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire1999-04-15015 April 1999 Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire 05000266/LER-1999-001, Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italics i1999-04-0808 April 1999 Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italics in Rept NPL-99-0174, Confirms Completion of Requested Actions in Accordance with Required Response of GL 96-01 for Unit 2.Confirmation of Completion for Unit 1 Was Provided in Ltr Npl 98-0591,dtd 9807141999-03-30030 March 1999 Confirms Completion of Requested Actions in Accordance with Required Response of GL 96-01 for Unit 2.Confirmation of Completion for Unit 1 Was Provided in Ltr Npl 98-0591,dtd 980714 ML20206B8231999-03-30030 March 1999 Forwards Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981103 for Point Beach Power Plant.One Deficiency Identified for Manitowoc County.County Corrected Deficiency Immediately NPL-99-0177, Forwards Decommissioning Funding Status Info for Pbnp,Units 1 & 2,per 10CFR50.751999-03-30030 March 1999 Forwards Decommissioning Funding Status Info for Pbnp,Units 1 & 2,per 10CFR50.75 05000301/LER-1999-001, Forwards LER 99-001-00,re Loss of Safeguards Electrical Bus During Refueling Surveillance Testing Which Resulted in Temporary Unavailability of One Train of Decay Heat Removal. Commitments Made by Util Are Identified in Italics1999-03-10010 March 1999 Forwards LER 99-001-00,re Loss of Safeguards Electrical Bus During Refueling Surveillance Testing Which Resulted in Temporary Unavailability of One Train of Decay Heat Removal. Commitments Made by Util Are Identified in Italics NPL-99-0122, Forwards Relief Requests RR-1-19 & RR-2-25,requesting Relief from Section XI of ASME B&PV Code, Rules for Inservice Exam of NPP Components, 1986 Edition,No Addenda.Requirements for Relief Apply to Third ten-yr ISI Interval for Units 1 &1999-03-0303 March 1999 Forwards Relief Requests RR-1-19 & RR-2-25,requesting Relief from Section XI of ASME B&PV Code, Rules for Inservice Exam of NPP Components, 1986 Edition,No Addenda.Requirements for Relief Apply to Third ten-yr ISI Interval for Units 1 & 2 NPL-99-0111, Informs NRC That IAW Provisions of ASME Boiler & Pressure Code,Section Xi,Paragraphs IWA-2430(d) & IWA-2430(e),WEPC Has Extended Third 10 Yr Interval for Pressure Testing Program at Pbnp,Unit 1 by 21 Months1999-03-0303 March 1999 Informs NRC That IAW Provisions of ASME Boiler & Pressure Code,Section Xi,Paragraphs IWA-2430(d) & IWA-2430(e),WEPC Has Extended Third 10 Yr Interval for Pressure Testing Program at Pbnp,Unit 1 by 21 Months NPL-99-0116, Forwards Proprietary & non-proprietary Revised Point Beach Nuclear Plant Emergency Plan IAW 10CFR50.54(q).Proprietary Plan Withheld1999-03-0101 March 1999 Forwards Proprietary & non-proprietary Revised Point Beach Nuclear Plant Emergency Plan IAW 10CFR50.54(q).Proprietary Plan Withheld NPL-99-0115, Forwards Proprietary & non-proprietary Revised EPIPs to Point Beach Nuclear Plant,Units 1 & 21999-03-0101 March 1999 Forwards Proprietary & non-proprietary Revised EPIPs to Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0114, Provides Results of Wepcs Insp,Replacement & Mechanical Testing of Reactor Internals Baffle Former Bolts During Recent Point Beach Refueling Outage1999-02-25025 February 1999 Provides Results of Wepcs Insp,Replacement & Mechanical Testing of Reactor Internals Baffle Former Bolts During Recent Point Beach Refueling Outage NPL-99-0086, Documents Commitment Change Which Is to Discontinue Actions Contained in Util Ltr Dtd 970613,after NRC Approval of LAR & Lower Containment Leak Rate Limit Is Implemented. Change Is Acceptable IAW Applicable Plant Procedure1999-02-24024 February 1999 Documents Commitment Change Which Is to Discontinue Actions Contained in Util Ltr Dtd 970613,after NRC Approval of LAR & Lower Containment Leak Rate Limit Is Implemented. Change Is Acceptable IAW Applicable Plant Procedure NPL-99-0101, Forwards Proprietary & non-proprietary Version of Rev 20 to EPIP 3.2, Emergency Response Organization Notification & Revised Index.Proprietary Info Withheld1999-02-19019 February 1999 Forwards Proprietary & non-proprietary Version of Rev 20 to EPIP 3.2, Emergency Response Organization Notification & Revised Index.Proprietary Info Withheld ML20203F7301999-02-10010 February 1999 Forwards Revs to Security Plan Sections 1.2,1.3,1.4,2.1,2.5, 2,6,2.8,6.1,6.4,6.5,B-3.0,B-4.0,B-5.0 & Figure R Dtd 990210. Evaluation & Description of Plan Revs Also Encl to Assist in NRC Review.Encls Withheld NPL-99-0067, Submits 30 Day Rept of Changes & Errors Discovered in ECCS Evaluation Models for Pbnp,Unit 21999-02-0202 February 1999 Submits 30 Day Rept of Changes & Errors Discovered in ECCS Evaluation Models for Pbnp,Unit 2 NPL-99-0064, Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement1999-02-0202 February 1999 Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement NPL-98-1032, Forwards Revs to Pbnp Security Plan Sections 1.1,1.2,2.1, 2.6,2.8,6.1 & 6.4 & Revs to Pbnp ISFSI Security Plan Sections 1.0 & 7.0,per 10CFR50.54(p).Encl Withheld1999-01-27027 January 1999 Forwards Revs to Pbnp Security Plan Sections 1.1,1.2,2.1, 2.6,2.8,6.1 & 6.4 & Revs to Pbnp ISFSI Security Plan Sections 1.0 & 7.0,per 10CFR50.54(p).Encl Withheld 05000266/LER-1998-029, Forwards LER 98-029-00,describing Discovery of Isolation of Autostart Feature for Svc Water Pumps from Unit 2,safeguards Buses During Modifications1999-01-26026 January 1999 Forwards LER 98-029-00,describing Discovery of Isolation of Autostart Feature for Svc Water Pumps from Unit 2,safeguards Buses During Modifications NPL-99-0031, Informs That Wepc Reviewed Contents of NEI to NRC & Have Verified Info Provided in Ltr Pertaining to WOG Member Plants Is Applicable to Pbnp.Attachment Responds to NRC Questions by Ref to Info in 981211 NEI Ltr1999-01-15015 January 1999 Informs That Wepc Reviewed Contents of NEI to NRC & Have Verified Info Provided in Ltr Pertaining to WOG Member Plants Is Applicable to Pbnp.Attachment Responds to NRC Questions by Ref to Info in 981211 NEI Ltr NPL-99-0004, Provides Status Update on Program Activities & Schedule for Final Resolution of Items Re Verification of Seismic Piping Class Interfaces for Point Beach Nuclear Plant,Units 1 & 21999-01-11011 January 1999 Provides Status Update on Program Activities & Schedule for Final Resolution of Items Re Verification of Seismic Piping Class Interfaces for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0012, Forwards Proprietary & Nonproprietary Revs to Epips. Proprietary Version of EPIPs Withheld1999-01-0808 January 1999 Forwards Proprietary & Nonproprietary Revs to Epips. Proprietary Version of EPIPs Withheld 1999-09-30
[Table view] |
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, -
l Wisconsin Electnc \
POWER COMPANY 231 W Mchigan. PO Box 2046 Milwaukee.Wi 53201 2046 (4'G) 2212345 VPNPD-96-011 February 9,1996 Document Control Desk )
US NUCLEAR REGULATORY COMMISSION Mail Station PI-137 Washington, DC 20555-0001 Ladies / Gentlemen:
DOCKETS 50-266 AND 50-301 RESPONSE TO GENERIC LETTER 95-07 i PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES i POINT BEACH NUCLEAR PLANT. UNIT 1 AND 2 l l
1 On August 17,1995, the NRC issued Generic Let,ter (GL) 95-07, " Pre.;sure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves." The GL requested that licensees perform, or confirm previous performance, of: i Within 90 days: l l
- 1. Perform a screening evaluation to identify valves which are potentially susceptible to pressure locking and/or thermal binding.
- 2. Document a basis for operability of potentia!!y susceptible valves, or take actions in accordance with Technical Specifications.
Within 180 days:
- 1. Evaluations of operational configurations of safety-related, power-operated (including motor, air, and hydraulically operated) gate valv.s for susceptibility to p: essure locking and thermal binding.
- 2. Further analysis, and any needed corrective actions, to easure that identified potentiaUy susceptible valves are capable of performing their current licensing basis safety functions.
The GL also requested that a summary description of the actions taken in response to the above 90-day and 180-day requested actions, be submitted within 180 days of the date of the Generic Letter.
9602200148 960209 PDR ADOCK 05000266 P PDR ) ().1/h 4.subsalandMiwwrunDuty Depntam
e Document Control Desk February 9,1996 Page 2 Wisconsin Electric Power Company has performed all of the requested actions discussed within the Generic Letter. The following provides a summary description of the information requested for the 180-day GL response.
The susceptibility evaluation began by developing a list of all air operated, motor operated, and hydraulically operated valves within the plant. From this list,110 valves were identified as being safety-related, power operated gate valves. An additional four (4) gate valves were identified as being safety-related, but manually operated. Four (4) other power-operated gate valves were identified as non-safety-related, but required to meet 10 CFR 50, Appendix R requirements for hot shutdown.
These 118 gate valves were screened for GL 95-07 susceptibility and are listed in Attachment 1.
The " Pressure Locking and Thermal Bin ling Workshop" held by NRC Region III on November 7,1995, provided the screening methodology utilized to identify which of the 118 gate valves are susceptible to pressure locking or thermal binding. The screening criteria used are listed in Attachment 2, while the valves identified as potentially susceptible are included in Attachment 3.
The screening of the 118 gate valves identified 42 as being potentially susceptible to thermal binding or pressure locking. These valves have been identified with "yes" in the GL 95-07 column of Attachment 3. Further evaluations of these 42 valves, identified as EVAL l-6 on Attachment 3, revealed that only the SI-860 A-D (Containment Spray Pump Discharge Redundant Isolation Valves) valves on each unit (eight (8) total valves) required long term corrective actions to ensure they could perform their safety functions. All other safety-related, power operated gate valves were shown to be unaffected by pressure locking or thermal binding through one of the evaluations listea in Attachment 3.
In addition to the eight (8) valves identified above, fourteen (14) gate valves, both manual and power operated, outside the scope of GL 95-07 were identified as susceptible to thermal binding or pressure locking while achieving cold shutdown.
The SI-860 A-D valves (eight (8) safety-related valves identified above) were noted to be susceptible to pressure locking during the performance ofInservice Tests (ITs) 05 A and 06A, " Containment Spray Pumps and Valves (Monthly)" Unit I and Unit 2 respectively. The long-term, permanent corrective action for the SI-860 valves was to revise the IT-05A and IT-06A to include cycling of the associated valve afler each containment spray pump is secured. This would eliminate any valve bonnet pressure buildup that the tests may have caused. These revisions were implemented with the issuance ofIT-05A, Revision 5 and IT-06A, Revision 5, dated January 8,1996. With these changes, the IT TEST POS entry os Attschment I becomes "NI", and the valves are placed in a condition which mitigates the susceptibility to pressure locking.
l
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Document Control Desk February 9,1996
, Page 3 In addition, PBNP Calculation 96-0062 contains the evaluation for operability of the SI-860 valves when the bonnets have been pressurized as a result of performing IT-05A and IT-06A. The calculation shows that with the bonnets of the SI-860 valves pressurized to the maximum available pressure, the valves l remain operable. Therefore, based on the evaluations and IT procedure revisions, the susceptibility of I the SI-860 valves to pressure locking has been adequately addressed.
The manually operated, low head, safety injection (low head SI to high head SI) suction cross-connect velves (SI-857 A and B for each unit), are susceptible to pressure locking after stopping the Residual Heat Removal (RHR) pumps, and attempting to open them to provide suction to the high head SI pumps. PBNP Calculation 96-0062 indicates that, while they remain operable, opening of the valves i may be diflicult and require some form of mechanical assistance. While they are manual valves, and not specifically a subject of GL 95-07 issues, we chose to consider them in our analysis and resolution efforts. Thus, evaluations are being initiated for possible bonnet reliefinstallation on these valves. In addition, the SI-857 valves are not susceptible to thermally-induced bonnet pressure rises since there is a 130 foot piping run between the hot RHR piping and the SI-857 valves, located at the suction of the '
high head SI pumps.
The power operated gate valves RH-700, RH-701 and RH-720 on each unit, (six (6) valves total),
provide RHR suction and return from the reactor coolant system. Since this function is not necessary to maintain hot shutdown per the PBNP safety analysis, they do not fall within the requirements of GL 95-07. However, to place the plant in a cold shutdown condition, such as for a normal refueling, l these valves would be required to open. For this reason, evaluations have been initiated to investigate l potential modifications which would enhance valve reliability. These evaluations will also be completed in the near future. ,
The Containment Spray Pump suction valves from the RHR heat exchanger HX-11, (Valves SI-871 A and B for each unit), were alsc identified as being potentially susceptible to pressure locking while proceeding to cold shutdown. The operation of these valves is not necessary to achieve hot shutdown conditions and would only be required for actions beyond the Emergency Operating Procedures (EOPs).
These valves are no longer used for lining-up low head SI to containment spray. We have performed analyses to show that the valves would open with bonnet pressurization due to IT testing, and that any thermally induced bonnet pressurization would occur slowly, allowing suflicient time for pressure to decay. Therefore, no further action will be taken for these valves.
The Power Operated Relief Valves (PORV) block valves, (RC-515 and RC-516 on each unit), were identified as being susceptible to thermal binding and pressure locking. The operation of the PORV l block valves is not necessary to achieve a hot shutdowa condition following a phnt accident. PBNP Memo 95-0430 contains the resolution of the potential thermal binding of these PORV block vahes. It
! concludes that the thermal binding of these valve.s will not result in a safety problem, and that suflicient l
. . _ ._ m._ _ _ . . _ . . __ _. _. _ _ .. _ _ _ . . _ _
Document Control Desk February 9,1996 Page 4 guidance exists for plant operators in the event thermal binding does occur. To address the potential of pressure locking of the block valves, PBNP Calculation 96-0062 shows that sufficient valve operator thrust margin exists such that the valves will open with the bonnet pressurized.
In summary, all safety-related, power operated gate valves have been screened and evaluated for susceptibility to the affects of pressure locking and thermal binding. All corrective actions identified for the safety-related gate valves have been completed, and several actions to enhance non-safety-related and manually operated gate valve reliability are currently in progress. Based on the actions we have taken on this issue, we believe that with the submittal of this letter, all requirements of Generic Letter 95-07 have been satisfactorily completed.
Please contact us if you have any questions or require any additional information.
Sincerely, j i
0- ,tr Bob Link Vice President Nuclear Power MDR/jg cc: NRC Resident Inspector i NRC Regional Administrator, Region III l
l Subscribed and sworn to before me this 94 day of Fd% 1996.
J j O m hiu bauN i (Nya$ Public, State ofWisconsin My commission expires: 8 * /D / 9 t,
~ _. . . __ __. _. .
j s
t
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! ATTACHMENT 1 i.
j The following provides a description of the fields used in this attachment:
l ,
Unit: Operating unit associated with the valve. '
- Number
- Valve identification number.
t Safety Function: Valve position required to perform its safety function.
l i
Open/Close -
Valve cycled during safety response.
- Close/(Open) - Valve remains closed to put unit into hot shutdown.
. Valve opened in some cases to reach cold shutdown.
l l Normal Position: Valve position maintained during normal plant operation.
IT Test Pos: This column is equivalent to the test or surveillance position. This position did not matter in most cases due to valve design, normal position, and system configuration. (Note: Equipment out of service during IT testing.)
NA -
. Position "not applicable", valve normally maintained open or maintained closed and not required to open. 1 i
NI -
"No Impact" would result from the IT testing that would be !
more severe than the normal operating position.
NIVD - "No Impact Due to Valve Design", since solid wedge gate valves are not susceptible to pressure locking.
NIBV - No Impact created by IT testing since valve has a bonnet vent.
NIMA - No impact on valve operation since valve is manually operated.
1 Closed - Valve is closed during IT testing and bonnet pressurization can occur.
c page1
1 ATTACHMENT 1 i Bonnet vent: The valves were reviewed to determine if a vent path for the bonnet is present. ,
Safety-related: Safety-related status of the valve.
Type: The type of gate valve. ?
Delta Temp.: Temperature transient that the valve will be exposed to. Either the piping l fluid temperature change or the valve environment. :
l l
l page 2
a ATTACHMENT 1-Mov.XLS Unet i NUMBER Safety Function Normal Position IT Test Pos Bonnet vent Safety Related TYPE DetteTemp P81 AF44006 open closed MVD no Yes Solid Wedge GATE VALVE eminent PS2 AF-04008 open closed MVD no Yes Solid Wedge GATE VALVE eminent
- P90 AF44009 open closed MVD no Yes Solid Wedge GATE VALVE eminent P80 AF-04016 open closed MVD no Yes Solid Wedge GATE VALVE emtnant PSO AF-04020 open closed MVD no Yes Solid Wedge GATE VALVE embient P90 AF-04021 open closed MVD no Yes Solid Wedge GATE VALVE embient P90 AF-04022 open closed MVD no Yes Solid Wedge GATE VALVE embient P90 AF-04023 operi closed MVD no Yes Solid Wedge SATE VALVE emtnant PSI CC-OO719 close open NA no Yes PereAel Seat i ouble Wedge GATE VALVE PB2 CC40719 close open NA no Yes Perosol Seat Double Wedge GATE VALVE P81 CC-00738A open closed M no Yes Flexible Wedge GATE VALVE embient PS2 CC-OO738A open closed M no Yes Flexible Wedge GATE VALVE embient PSI CC-OO7388 open closed M no Yes Flexible Wedge GATE VALVE embient PS2 CC-OO7388 open closed M no Yes Flexible Wedge GATE VALVE emtnent PS1 CC-OO754A close open NA no Yes Solid Wedge GATE VALVE PS2 CC-OO754A close open NA no Yes Solid Wedge GATE VALVE P51 CC-OO7548 close open NA no Yes Solid Wedge GATE VALVE PS2 CC-OO7548 close open NA no Yes Solid Wedge GATE VALVE P81 CC-OO759A close open NA no Yes Solid Wedge GATE VALVE PS2 CC-OO759A close open NA no Yes Solid Wedge GATE VALVE P81 CC407598 close open NA no Yes Solid Wedge GATE VALVE PS2 CC407598 close open NA no Yes Solid Wedge GATE VALVE P81 CV401128 open closed M no No Double Disc Flexible Wedge GATE VALVE emtnent PS2 CV401128 open closed M no No Double Disc Flexible Wedge GATE VALVE embient P81 CV40112C close open NA no No Double Disc Flexible Wedge GATE VALVE CV-OO112C close open NA na No Double Disc Flexitde Wedge GATE VALVE
. CV40270A close open NA r.o Yes Perellet Seat Double Wedge GATE VALVE PS2 CV40270A close open NA no Yes PeroRet Seet Double Wedge GATE VALVE P81 CV402708 close open NA no Yes Perellel Seat Double Wedge CATE VALVE PS2 CV402708 close open NA no Yes Peregel Seat Double Wedge GATE VALVE
, PSI CV40313 close open NA no Yes Double Disc Flexible Wedge GATE VALVE PS2 CV40313 close open NA no Yes Double Disc FlexitHe Wedge GATE VALVE P81 CV41298 close open NA no Yes Flexible Wedge GATE VALVE PS2 CV41298 close open NA no Yes Flexible Wedge GATE VALVE P81 CV41299 close closed NA no Yes Flexible Wedge GATE VALVE P82 CV41299 close closed NA no Yes Flexitdo Wedge GATE VALVE ,
P90 F043930 open closed MVD no Yes Solid Wedge GATE VALVE emtnent P90 F043931 open cloeod MVD no Yes Solid Wedge GATE VALVE __
o nbient PSI RC40427 close open NA no Yes PereRel Seat Double Wedge GATE VALVE PS2 RC-OO427 close ope, NA no Yes Perellet Seat Doutde Wedge GATE VALVE l PSI RC40515 open/close open/ closed M no Yes Flexible Wedge GATE VALVE 400 F Pf2 RC-OO515 open/ciose open/ closed M no Yes Flexitde Wedge GAN, VALVE 400 F PSI RC-OO516 open/close open/ closed M no Yes Flexitdo Wedge GATE VALVE 400 F PS2 RC-OO516 open/close open/ closed NI no Yes FlexitNo Wedge GATE VALVE 400 F PSI RC40598 close closed NA no Yes Pereget Seat DoutWe Wedge GATE VALVE PS2 RC-OO598 close closed NA no Yes Peregel Seat Double Wedge GATE VALVE
ATTg g NT 1 i
i Unit NUMBER Safety Function Normal PositWe IT Test Pos Bonnet Vent Safety Related TYPE DetteTemp P81 14C-OO599 close closed NA no Yes Perellet Seat Double Wedge GATE VALVE PS2 14C-OO599 close closed NA no Yes Perellel Seat Double Wedge GATE VALVE -
PS1 RH40700 closenopen) closed NAANI) no Yes Paretel Seat Double Wedge GATE VALVE 250 F j PB2 MH40700 closenopen) closed NARNI) no Yes Perenel Seet Double Wedge GATE VALVE 250 F !
PS1 RH40701 closedopen) closed NARNI) no Yes Flexible Wedge GATE VALVE 140F P92 l#400701 closeMopen) closed NANNI) no Yes Flexible Wedge GATE VALVE 140F P91 MH-OO720 closenopen) closed NASM) no Yes Flexible Wedge GATE VALVE 140 F PS2 I4H40720 closenopen) closed NARNil no Yes Flexible Wedge GATE VALVE 140 F P90 ftS-SA40009 close open NA no Yes Flexible Wedge GATE VALVE 540 F P90 RS-SA40010 close open NA no Yes Flexible Wedge GATE VALVE 540 F PS1 SI40825A open open NA no Yes Double Disc Flexible Wedge GATE VALVE PS2 Sl40825A open open NA no Yes Double Disc Flexible Wedge GATE VALVE ;
P91 SI408258 open open NA no Yes Double Disc Flexible Wedge GATE VALVE P92 SI-008255 open open NA no Yes Double Disc Flexible Wedge GATE VALVE S140826A open closed NIBV yes Yes Double Disc Flexible Wedge GATE VALVE embent PB_1_
PS2 SI-00826A open closed NIBV yes Yes Double Disc Flexible Wedge GATE VALVE embient ,
P81 S1408288 open open NA yes Yes Double Disc Flexible Wedge GATE VALVE PS2 SI-008268 open open NA yes Yes Double Disc Flexible Wedge GATE VALVE ,
P81 St-00826C open open NA yes Yes Flexible Wedge GATE VALVE PS2 Sl40826C open open NA yes Yes Double Dise Flexible Wedge GATE VALVE ;
PB1 SI-OOS41 A close open NA no Yes PeroRei Seat Double Wedge GATE VALVE !
P52 S140841A close open NA no Yes Perellel Seat Double Wedge GATE VALVE ,
PB1 SI-00841:.1 close open NA no Yes Perenel Seat Double Wedge GATE VALVE [
S540841 B close open NA no Yes Parenel Seat Double Wedge GATE VALVE f82 PS1 Sl408l51 A open closed NIBV yes Yes Pere 9el Seat Double Wedge GATE VALVE 150 F !
PS2 SIP '4' open closed N18V yes Yes Perellel Seat Double Wedge GATE VALVE 150 F ,
PS1 5440s open closed NIBV yes Yes Perellet Seet Double Wedge GATE VALVE 150 F t PB2 S8408518 open closed NIBV yes Yes Perenel Seat Double Wedge GATE VALVE 150 F ,
PS1 St40852A op+n closed NIBV yes Yes Peregel Seat Double Wedge GATE VALVE 200 F l PS2 S840852A open closed NIBV yes Yes Perenel Seat Double Wedge GATE VALVE 200 F ,
PS1 S6-003528 open closed NISV yes Yes PereHet Seat Double Wedge GATE VALVE 200 F PS2 St-008628 open closed NISV yes Yes Peregel Seat Double Wedge GATE VALVE 200 F j PB1 5840856A close open NA no Yes PareRel Seat Double Wedge GATE VALVE {
l PS2 Sl40856A close open NA no Yes Perstel Seat Double Wedge GATE VALVE P91 SS-008568 close open NA no Yes Perstel Seet Double Wedge GATE VALVE
.PS2 58408568 close open NA no Yes Paratel Seat Double Wedge GATE VALVE i PB1 SI-00857A open closed NIMA no Yes Double Disc Flexible Wedge GATE VALVE e abient i PS2 St40857A open closed NilWA no Yes Double Disc Flexible Wedge GATE VALVE embient PS1 SI-00857B open closed NIMA no Yes Double Disc Flexible Wedge GATE VALVE embient PS2 S5408575 open closed NIMA no Yes Double Disc Flexible Wedge GATE VALVE embient
- PB1 5840860A open closed NI no Yes Perellel Seet Double Wedge GATE VALVE emeient i PS2 St-00860A open closed M no Yes Perenel Seat Double Wedge GATE VALVE embient !
P91 S&408608 open closed M no Yes Perstel Seat Double Wedge GATE VALVE embient PB2 55408608 open closed M no Yes Parenel Seat Double Wedge GATE VALVE embent PB1 Sl40860C open closed NI no Yes Perellel Seat Double Wedge GATE VALVE embent PB2 SI-OO860C open closed NI no Yes Parenel Seat Double Wedge GATE VALVE embient
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a .. . .
ATT g gNT 1 Unit NUMBER Safety Function Normal Position IT Test Pos Bonnet Vent Safety Related TYPE DetteTemp 561 Sl40860D open closed NI no Yes Perenel Seat Double Wedge GATE VALVE embient
-PS2 Sl40860D open closed NI no Yes Paratel Seat Double Wedge GATE VALVE embient PB1 Sl40866A close open NA no Yes Perstel Seat Double Wedge GATE VALVE PS2 Sl40866A close open NA no Yes Paratel Seat Double Wedga GATE VALVE PS1 Sl406668 close open NA no Yes Peratel Seat Double Wedge GATE VALVE PS2 51408668 close open NA no Yes Pereuel Seat Double Wedge GATE VALVE PS1 SI-OO670A close open NA no Yes Double Disc Flexible Wedge GATE VALVE PS2 Sl40870A close open NA no Yes Double Disc Flexible Wedge GATE VALVE PS1 Sl408708 close open NA no Yes Double Disc Flexible Wedge GATE VALVE PS2 Sl408708 close open NA no Yes Double Disc Flexible Wedge GATE VALVE PB1 Sl40871A close/(open) closed NA/(closed) no Yes Pereuel Seat Double Wedge GATE VALVE embient (300)
PS2 Sl40871A close/topen) closed NA/(closed) no Yes Perstel Seat Double Wedge GATE VALVE embient (300)
PB1 Sl40871B close/(open) closed NA/(closed) no Yes Perstel Seat Double Wedge GATE VALVE embien". (300)
PS2 S1408718 close/lopen) closed NA/(closed) no Yes ParaNel Seat Double Wedge GATE VALVE embient (300)
P81 Sl46896A close open NA no Yes Double Disc Flexible Wedge GATE VALVE PS2 S140896A close open NA no Yes Double Disc Flexible Wedge GATE VALVE PS1 Sl408968 close open NA no Yes Double Disc Flexible Wedge GATE VALVE PS2 Sl408968 close open NA no Yes Double Disc Flexible Wedge GATE VALV3 PBO SW42816 close open NA no Yes Solid Wedge GATE VALVE P90 SW42817 close open NA no Yes Solid Wedge GATE VALVE PB1 SW42880 close open NA no Yes Solid Wedge GATE VALVE PS2 SW42880 close open NA no Yes Solid Wedge GATE VALVE PS1 SW42907 open closed N1 no Yes Solid Wedge GATE VALVE embient P92 SW42907 open closed NI no Yes Solid Wedge GATE VALVE embient PB1 SWC2908 open closey N1 no Yes Solid Wedge GATE VALVE embient PS2 SW42908 open closed NI no Yes Solid Wedge GATE VALVE embient 4
t a
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l ATTACHMENT 2
)
W ETY RELATED POWER OPERATED GATE VALVE- ]
PRESSURE LOCKING AND THERMAL BINDING SUSCEPTIBILITY CRITERION i
1 mammmer Valve Normal Safety Position Test or Evaluate Position Surveillance Susceptible Position Within Scope of GL 95-07 Normally Closed Open Closed Yes Normally Closed Open Open Yes Normally Closed Closed Closed No
- Normally 11osed Closed Open No
Closed 'Yes Nomally Open Open Open No Normally Open Closed Closed No *
'Normally Open Closed Open No *
= Licensees should be aware of the potential for thermally-induced pressure transients resulting in bonnet over pressurization. j
I ATTACHMENT 3 The following provides a description of the fields used in this attachment:
Unit: Operating unit associated with the valve.
Number: Valve identification number. j Sudden Pressure: A review of the system design to determine if a sudden pressure drop could occur with the valve closed, trapping pressure in the j bonnet, l 1
Pressure: Maximum expected differential pressure.
Flow: Expected flow through valve when open.
Temperature: Maximum expected temperture of fluid.
Valve Size: Nominal valve size. l l
GL 95-07: Valve is potentially susceptible using the screening method of the NRC. When a screening shows "no(yes)", this indicates the valve is l not susceptible to achieve hot shutdown, but would be susceptible !
to achieve cold shutdowa. l l
EVAL 1: The valve is determined unaffected if the flexible wedge valve is supplied with a bonnet vent and no delta temp. occurs except that j resulting from ambient changes, j EVAL 2: The valve is determined unaffected since the parallel seat double i wedge gate valve has a bonnet vent.
EVAL 3: The valve is determined unaffected since the solid disc valve does not experience a delta temp. except that resulting from ambient changes.
EVAL 4: The valve is determined unaffected since the flexible wedge valve does not experience a delta temp. except that resulting ,
from ambient changes and does not experience a sudden I depressurization. I page1 ;
4
4 ATTACHMENT 3 I I
EVAL 5: PBNP Calculation 96-0062 contains the evaluation / calculations performed to ensure that the trapped bonnet pressurization does not
- cause an excessive opening load on the SI-857 and SI-860 valves.
i f EVAL 6: PBNP Memo 95-0430 and PBNP Calculation 96-0062 describe the evaluations performed to ensure thermal binding will not occur, and
- actions taken to prevent thermal binding. The evaluation also i describes tnat operating instructions exist to safely recover should a problem occur, i I i
i i
l l
I 1
l 4
1 4
j !
j N
1 l
page 2
, .= * ,
ATT g NT 3 Unit NUMBER jSudden Pressure Pressure Flow Ternperature Velve Site GL 9547 Evel1 Fvel 2 f: vel 3 Evel4 Evel5 Evel6 P81 AF-04006 no 105 400 80 6 yes ok PS2 AF-04006 no 105 400 80 6 yes ok P90 AF44009 no 105 200 80 4 yes ok P90 AF-04016 no 105 200 80 4 yes ok P90 AF-04020 no 1405 200 100 3 yes ok P90 AF-04021 no 1405 200 f00 3 yes ok P90 AF-04022 -
1405 200 700 3 yes ok P90 AF-04023 2. T405 200 100 3 yes ok PSI CC40719 30, 132 570 727 6 no PS2 CC-00719 M 192 570 127 6 no PS1 CC-00738A ., 160 2765 f17 to yes ok PS2 CC-00738A no 160 2765 717 10 yes ok PSI CC-007368 no 160 2765 177 10 yes ok PS2 CC-007388 no 160 2765 ff7 10 yes ok P81 CC 00754A no 145 230 127 4 no PS2 CC-00754A no 145 230 127 4 no PS1 CC-007548 no- 145 230 127 4 no PS2 CC407548 no 145 230 127 4 no PS1 CC40759A no 145 230 127 4 no
.PS2 CC40759A no 145 230 127 4 no PSI CC-007598 no 145 230 127 4 no PS2 CC-007598 no 145 230 127 4 no P81 CV-001128 no 87 120 127 4 yes ok 42 CV-001128 no 87 120 127 4 yes ok P81 CV40112C no 80 120 127 4 no PS2 CV-00112C , no 80 120 127 4 no P81 CV-00270A no 1985 15 520 2 no PS2 CV40270A no 1985 15 520 2 no PS1 CV402708 no 1985 15 520 2 no PS2 CV-002708 no 1985 15 520 2 no
.P81 CV40313 no 148 16 142 3 no PS2 CV40313 no 148 16 742 3 no PS1 CV41298 no 1985 120 520 3 no PS2 CV41298 no 1985 120 520 3 no PSI CV-u1299 no 1985 30 520 2 no PS2 CV41299 no 1985 30 520 2 no P90 FO-03930 no 90 8 715 1 yes ok P90 R)43931 no 90 8 ff5 1 yes ok PS1 RC-00427 no 1985 50 520 2 no PS2 RC-00427 no 1985 50 520 2 no P81 RC-00515 yes 2485 blowdown 653 3 no(yes) ok PS2 RC-00515 yes 2485 blowdown 653 3 notyes) ok PS1 RC-00516 yes 2485 blowdown 653 3 no(yes) ok PS2 RC40516 yes 2485 blowdown 653 3 notyes) ok PS1 RC-00598 no 1985 0 520 2 no P82 RC40598 no 1985 0 520 2 no Page 4
+ , .. + ,
ATT g NT 3-I ,
Urut NUM8ER Sudden Pressure Pressure l Flow Temperature Velve Sire GL 9547 Evel1 Evol2 Evel 3 Evel 4 Evol 5 Evol6 PSI RC40599 no 1985 0 520 2 no PS2 RC-00699 no 1985 0 520 2 no P91 RH40700 yes 1982 3100 610 10 no(ves)
PS2 RH40700 yes 1982 3100 610 10 notvesi P81 RH40701 no 1990 3100 610 10 no(ves)
PS2 RH40701 no 1990 3100 610 10 no(yes) .
PS1 RH40720 yes 564 3100 553 10 no(yes)
PS2 RH40720 yes 564 3100 553 10 nc{yes)
P90. RS-SA40009 no 1050 blowdown 540 3 no P90 RS-SA-00010 no 1050 blowdown 540 3 no =
PB1 Sl40825A no 30 1230 85 12 no PS2 SI-00825A no 30 1230 SS 12 no
.PB1 Sl408258 no 30 1230 SS 12 no P82 Sl408258 no 30 1230 95 12 no a
PSI S840826A no 30 1230 745 8 yes ok
- PS2 St-00826A no 30 -1230 145 8 yes ok Pet S1408268 no JO 1230 145 8 no PS2 $l408268 no 30 1230 145 8 no PS1 S140S26C no 30 1230 745 8 no PS2 Sl40826C no 30 1230 145 8 no P91 SI-00841 A no 1990 8228 553 10 no PS2 Sl40841A no 1990 8228 553 10 no PB1 SI-008418 no 1990 8228 553 10 no PS2 Sl408418 no 1990 8228 553 10 no P81 S140851 A no 73 2200 340 10 yes ok PS2 S840851A no 73 2200 340 10 yes ok PB1 SI-008518 no 73 2200 340 10 yes ok PS2 58408518 no 73 2200 340 10 yes ok PB1 S840852A yes 1996 1560 615 4 yes ok PS2 Sl40852A yes 1996 1560 615 4 yes ok PSI S6408528 yes 2008 1560 815 4 yes ok PS2 Sl408528 yes 2008 1560 615 4 yes ok PSI S840856A no 437 2200 700 10 no PS2 Ss40856A no 437 2200 100 10 no PCs1 Sl408568 % 437 2200 700 10 no PS2 S8408568 no 437 2200 700 10 no
.P81 SI-00857A yes 207 1320 340 6 yes ok PS2 Sl40857A yes 207 1320 340 6 yes . ok j P81 S8408578 yes 207 1320 340 6 yes ok PS2 58408578 yes 207 1320 340 6 yes ok PSI S8408 COA yes 458 1320 100 6 yes ok PS2 SI40860A yes 458 1320 700 6 yes ok l
PB1 St-008603 yes 458 1320 700 6 yes- ok P82 SI-009608 yes 458 1320 700 6 yes ok P81 S840860C yes 458 1320 700 6 yes ok PS2 St-00860C yes 454 1320 700 6 yes ok i
Page 5
___- -____-_----__ ___ - - - - ___ - _ - _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ - _ _ _ _ - _ _ _ _ - - = _ _ _ _ _ _ - _ _ _ _ _ _ - - - - - - - - -
e em = ,
ATTACHMENT 3 mov.xtS e
UnR NUMBER Sudden Pressure Pressure Flow Temperature Velve Sire GL 9547 Evel 1 Evel 2 Evel 3 Evel 4 Evel 5 Evol6 P81 51408600 yes 458 1320 700 6 yes ok PS2 $140860D yes 458 1320 100 6 yes ok i P81 Sl40866A no 1745 1230 100 4 no PS2 SI-00866A no 1745 1230 100 4 no P81 Sl408868 no 1745 1230 TOO 4 no PS2 Sl408668 no 1745 1230 700 4 no P81 Sl40870A no 130 1320 85 6 no PS2 Sl40870A no 130 1320 35 6 no P81 SO408708 no 130 1320 95 6 no PS2 Sl408708 no 130 1320 95 6 no P81 Sl40871 A no 207 1320 340 6 rwHyos)
PS2 SI-00871 A no 207 1320 340 6 notyes)
PSI S8408718 no 207 1320 340 6 no(yes)
PS2 58408718 no 207 1320 340 6 notyes)
P81 Sl40896A no 130 1230 95 6 no '
PS2 Sl40896A no 130 1230 95 3 no PS1 Sl4)08968 "no 130 1230 SS 6 no PS2 Sl408968 no 130 1230 35 6 no P90 SW42816 no 98 673 SO 6 no P90 SW-02817 no 105 276 SO 6 no P81 SW42880 no 105 858 SO 6 no PS2 SW42880 no 105 791 SO 6 no P81 SW42907 no 98 4800 SO 12 yes ok PS2 SW42907 no 38 4800 SO 12 yes ok P81 SW42908 no 98 4800 SO 12 yes ok PS2 SW42iir08 no 98 4800 SO 12 vos ok Page 6
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