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MONTHYEARML20247D3371989-05-19019 May 1989 Advises That Util 890303 Proposed Alternate Schedule for Completing Item 1.b to NRC Bulletin 88-011 Not Approved.Nrc Expects That Efforts Will Be Accelerated to Meet Completion Dates as Committed to by Westinghouse Owners Group Project stage: Other ML20059M0411990-09-25025 September 1990 Identifies No short-term Safety Concerns Re Thermal Stratification,Per 890531 Response to NRC Bulletin 88-011, Presurizer Surge Line Thermal Stratification Project stage: Other ML20065U3141990-12-18018 December 1990 Requests Extension of Analysis Completion Date Until 910501 Per Item 1.d of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification Project stage: Other ML20081G6511991-06-0707 June 1991 Discusses Plant Specific Thermal Stratification Analysis Results & Completion Date Extension Request for Completion of Action Item 1.d of NRC Bulletin 88-011 Project stage: Request 1990-12-18
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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
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Wisconsin Eik>ctnc POWER COMPANY 5
231 w Menwn Po b ;m Mwee w 5r01 9mm M VPNPD 18 4 NRC 0 5 4 June 7, 1991 U.S. NUCLEAR REGULATORY COMMISSION Document Control Desk Mail Station P1-137 Washington, D.C. 20555 Gentlemen:
DOCKET NOS. 50-265 AND 50-301 ,
PLANT SPECIFIC THERMAL STRATIFICATION ANALYElg RESULTS AND COMPLETION DATE EXTENSION REOUE3T FOR COMPLETION OF ACTION ITEM 1.d_QE NRC IE BULLETIN 88-11 (TACK NOS. '2155 AND 72156).
POINT BEACH NUCLEAR PLANT UNITS 1 AND 2
References:
- 1) Wisconsin Electric Power Company Letter No.
VPNPD-89-314, dated 05/31/89, to the NRC on the subject of " Submittal of Justificacion for Continued Operation Regarding Pressurizer Thermal Stratification, Point Beach Nuclear Plant Units 1 and 2".
2)_ Letter from the NRC to C. W. Fay, dated 09/25/90, on the subject of "NRC Bulletin No.
88-11, Pressurizer Surgo Line Thermal Stratification - Evaluation of WOG Bounding Analysis (Tack Nos. 72155 and 72156).
- 3) Wisconsin Electric Power Company Letter No.
VPNPD-90-498, dated 12/18/90, to the NDC on the subject of " Request for Extension of analysis Completion Date per Item 1.d of NRC IE Bulletin 88-11".
In a letter dated December 18, 1990, Wisconsin Electric Power Company (WE) notified the NRC that we would not meet the completion date specified for the reporting requirements in Action Item 1.d of IE Bulletin 88-11 for Point Beach Nuclear Plant (PBNP) Units 1 and 2 (Reference 3). The letter stated that WE had elected to proceed with the thermal stratification analysis independent from the Westinghouse Owners Group (WOG) detailed generic analysis, and that this analysis was currently under way. WE committed to an analysis 910613023G 910607 PDR ADOCK 05000266 .Y l P PDR l
. , i Document Control Dook June 7, 1991 Page 2 j l
completion dato of May 31, 1991 because of the complexity and refinomonta required to completo the analysis. This letter providos a summary of the analysis results to dato, and a request for a revised completion schedulo for the items remaining for fulfillment of all the reporting requirements of the bulletin.
WE was informed by Westinghouso Electric Corporatjon in M1y 1990 that PDNP Units 1 and 2 would not be completely bounded by the WOG generic detailed analysis as documented under WCAP-12639 ontitled "Wostinghouse Owners Group Prosaurizer Surgo Lino Thermal Stratification Genoric Dotalled An31ysis Program MUHP-1091 Summary ;
Report", dated Juno 1990. The piping configuration chosen for tho l water solid hoatup/cooldown (H/C) analysis group (which is i conservative for PBNP) did not demonstrato codo compliance for pipe i stress and fatigue when the Strosr Intensification factor for the ,
long radius elbows utilized at PBNP were applied to the fivo-diamotor bonds analyzed in the Westinghouse model. Mostinghouse indicated with a high degree of confidence that PBNP would demonstrato code compliance with a plant specific analysis. ,
Pursuant to this notification, WE elected to perform a plant I specific analysis for each unit at PBNP, and applied for an ;
extension to May 31, 1991 for completion of the reporting :
requirements in Action Item 1.d of the bulletin.
Tho plant specific analyses have boon completed by sargent and Luady, and incorporato the actual design for each unit at PDNP. [
The detailed analyscs include the as-built system layouts, support design and configuration, pipo fittings and materials, carthquake i design, and all applicable design and stratification transients for the surgo lino piping. In order to maintain conservatism and ;
consistency with the WOG generic detailed analysis, definitions and I characteristics of stratification, the number of ovents, l magnitudos, and number of cycles used in the analf sos are the samo as the generic definitions and transients developed by the WoG program in-WCAP-12639. ;
The plant specific design and thermal stratification analysis results demonstrate that the curgo lino is within Codo pipe stress and fatiguo allowables for the 40-year design life of the plant for both Units, with the exception of the Integral Wolded Attachment i (IWA) lug / collar design for PDNP Unit 1 pipe whip rostraints R2, :
R4, and R5. The attached document entitled " Wisconsin Electric Power Company Point Beach Nuclear Plant Units 1 and 2 Pressurizor Surgo Line Thermal Stratification Analysis Results and Plant Specific Responso for NRC IE Bulletin 88-11" provides a summary of the pipo stress and fatiguo analyses for Codo compliance. The worst cdLo Cumulative Usage Factor (CUF) of 1.901 for the Unit 1
,- __ . . . . _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ . _ ~ . _ _ _ _ . - -. _ _ . _ . ~ - , - , .
4
, 1 f
Document Control Desk June 7, 1991 l Page 3 l 3
IWas occurs at R4, and allows for an additional 37 heatup and
' cooldown sequences before the CUT excoods 1.0. The highest CUF at locations other than the IWAs is 0.755 for Unit 1 and 0.875 for Unit 2 at the reducer to pressurizer safo end wold.
Since the Unit 1 IWAs do not satisfy Code fatiguo requirements (utilizing conservativo analysis techniques), WE will proceed with !
4 a refined analytical evaluation of the IWAs. If wo determino that
' a modification is necessary to resolve this issue, we will adviso
, you of the installation schedule. We have also determined that it will be necessary to review past operating logs and strip charts to validate the operating history of the plant. From interviews with the operators and proceduro reviews, wo had concludod that tho 210'F Delta-T limit for the water solid H/c method is a i conservativo limit for PBNP. However, a sample chock of the 1989 Unit I hoatup showed that although the system Delta-T was lower ;
than the 210'F limit, it was higher than the limit previously indicated by the plant operators. WE is proceeding at this time with initiating a further review of past records, and modifying our H/C procedures to assure that the 210'F limit is not exceeded in the future. WE will adviso you of the results of the refined analytical evaluation and our record review as soon as the work is completed. WE anticipato completing those effortn before the end of 1991.
WE has concluded that PBNP can safely continuo to oFarato at full power under the JCO submitted to the NRC in May, 1989 (reference 1). The basis for this JCO was the generic bounding '
analysis performed under WCAP-122'7. The plant specific detailed analyses completed for each urit .t PBNP demonstrate the applicability cf this JCO for coruinued full power operation. The JCO allowed for a maximum of ten Juditional H/C cycles froa the date of submittal in May 1989. PBNP has experienced five H/C <
cycles on tait 1 and two on Unit 2 sinco submitting the JCO. This -
leaves a sufficient number of cycles to maintain an adequate safety margin, and therefore, we conclude that there are no short-term safety concerns associated with thermal stratification offects on the surge lines at PBNP.
This.JCO will allow WE sufficient timo to evaluate whether to apply refined anslytical techniques to the Unit 1 IWA pipe whip rostraint doJigny for Codo fatigue compliance, or to modify the whip restraint designs to eliminate the lug problem altogether.
Additionally, this will allow WE to complete the additional reviews of past operating records, and to revise the PBNP operating procedures to assure compliance with the 210'F system Delta-T limit for water solid heatup and cooldown procedures.
s -m ,y- ,-em p- w-ww ,-sem-,m--w~ma
Document Control Desh June 7, 1991 Page 4 Picano contact us if you have any questions concerning our proposed actions in this manner, very truly yours, L.!
//
g is bl C. W., ray Vice president 11uclear Power Department Copios to: 11RC Regional Administrator - llegion III IJRC Resident Inspector
WIHCONHIN ELECTRIC POWER CONPANY POINT DKACH NUCLEAR PLANT UNITS 1 AND 2 PREDDURIZER DURGE LINE THERMAL STRATIFICATION ANALYDID REDULTD AND PLANT SPECIPIC RESPONDE FOR NRC IE DULLETIN 00-11 Wisconsin Electric Power Company (WE) elected to perform individual plant specific analyses for the offects of thermal stratification on the Point Beach Nuclear Plant (PDNP) Units 1 and 2 pressurizer surge lines to setisfy the requirements delineated in NRC 1E Dulletin 88-11. This decision occurred after being informed by Westinghouse Electric Corporation in May 199n that PDNP wou3d not be completely bounded by the Westinghouse Owncra Group (WOG) generic detailed analysis for the thermal stratification of the pressurizer uurgo line because of the iony radius elbows utilized at PDNP.
A summary of the results of the plant specific analyses performed by Sargent and Lundy are au follows:
- 1) h PPLIC A D I LI T_Y_O F_DI; p I O N_I H r_QRH ATIO N WE has reviewed the piping layout drawings, support drawings, pipe whip restraint drawings, and all other information provided to the Westinghouse Owners Group (WOG) Ior the generic detailed analysis contained in WCAP-12639 entitled
" Westinghouse owners Group Pressurizer Surge Line Thermal Stratification Generic Detailed Analysis Program MUHP-1091 Summary Report", dated June 1990 and has concluded that the generic c'etailed analysis and design basis information is applicabls for PbHP units 1 and 2,
- 2) YE RI rlRATION_OF_Q PE RATIO N A L_M l;T110 D0 2.1 WE has determined irom a review by the PUNP operations department, and prior surveys by the WOG that PDNP follows a water solid heatup/cooldown method for both units and have determined that the maximum system AT of 210*P is within the limits set by Westinghouse in its generic detailed analysis, and utilized by Sargent and Lundy in their plant specific analyses for heatup, cooldown, and RCS venting.
2.2 Additional review of the operating procedures has determined that the maximum RCS temperature during the venting operation is limited to 200*r, at which temperature the RCS is utill water solid and the system AT is less than 150*F.
4 1 .
- 3) RU P P.0RT_ LOAD R_AND_PI PI NQ_D10 P L AC E M ENT O 3.1 The nurgo line piping in nupported by throo variablo opring hangers per unit at PUNP. Thero are no rigid rentraints on the surgo lino piping for either unit.
Individual spring can settings woro used in the analyoun 30 required for each respectivo opring can.
3.2 The plant specific analysis piping displacomonts for all normal design conditionn, atratification effects, and thermal anchor displacements of the RCL and pZR at each apring support and whip rostraint location were compared to the available travel distances and gap dimensions respectively. The analyzed piping displacements for the spring hangers were all within their respective travel distances. There were soveral insulation hits on Unit 2 that required ovaluations for gap closuron. The results of thoso ovaluations show that the insulation gap clonures woro of a small magnitude t.nd an a result have a negligible offect on the global piping responso and stresses.
Thoro was one metal-to-metal gap clocuro on pipe whip restraint R4 on U1. This interforence was caused by normal thermal growth of the piping and was previously evaluated and found to be acceptable for stroscos, loads, and fatigue. This analysis (reference 1) had already boon completed prior to the plant specific analyala, and the offects of this interforence were accounted for in the thermal stratification analynia.
- 4) RElBMLC_AND_DKhDMRIORT_KQMENTD 4.1 WE has compared the OBE pipe bending moments used in the WOG fatiguo analysis (WCAP-12639) with the maximum of those which have boon analyzed for both PDNP units. The i results are tabulated below MOMENT _(fl-LD1 EITIING ANALYSID Mb Mt Isng radius elbown WOG 34000 34000
" S&L 7300 (U1) 10100 (U1;
" S&L 6100 (U2) 10600 (U2)
All other components WOG 60166 60166
" S&L 12300 (U1) 3000 (U1) l
" S&L 12100 (U2) 3000 (U2) l 4.2 WE hwa compared the equation 13 allowable doadweight and ODE' mismic resultant moments for the RCS hot leg nozzlo calt.ulakod in WCAP-12639 with those generated in tho analysen for each Unit. The results of this comparison cro es follows:
l
o l
EITTING ANhhYDID REQMLTANT_MQMENT_(ET-LDL RCS hot leg nozzle WOG 36700
" S&L 12900 (U1)
" S&L 16000 (U2)
- 5) MX IMUM_.QOM EETID_DERG E _kI NE_EI EI NQ._STRE R R E E The maximum computed stresses for both the primary stress intensity and primary plus secondary stress intensity are summarized below:
MAXIMUM ALLOWABLE STRESS STRESS ,
EQUATlDll DU111 1)Uill LOCATLQ11 t IM11 (U?) >
9B 8.9 9.1 24.75 Red. Le Safo End l 9D 9.8 10.1 36.6 LRE near RCL 10 60.9 u9.1 49.5 LRE near RCL 12 44.5 52.6 54.9* LRE near RCL 13 34.3 22.7 49.5 LRE near RCL
- Allowable based on average value of Sm, (Smi + Smj)/2, where
- i and j are the load sets producing the maximum thermal stress range.
- 6) MAX 1MUR qQMEUIED CUMULATIVE U8h0EJACIQRS The maximum computed cumulative usage factors (CUF) developed by the plant specific analyses for each unit are as follows:
LOCATION UNIT CMI Reducer to PZR Safe End 1 .755 (1)
Reducer to PZR Safe End 2 .875 (1) Maximum value at locations other than those with integral welded attachments. See Section 7.0 for results at these locations.
- 7) KYAhUAT_LON OF INTI_QRAL WELDED _ATIACEMENTR PBNP Unit 1 has three integral welded attachments (IWAs) at pipe whip restraints R2, R4, and RS. The lug / collar design is
! the same for each restraint. Because the lugs are only wolded to the top of the pipe, thermal striping effects on the lug CUF were ignored.
EQ. 10 STRESS CUT (1) (3) TOTAL H/C ltEST. Not Dutil H/9_ LUG Fil&G IN1: RILL 21 R2 25.6 .489 1.385 144 R4 30.1 .503 1.901 84 R5 27.9 .470 1.454 137 (1) Basad on 40-year H/C design cycles (2) Number of H/C event sequences for which CUT s 1.0 in the present configuration (3) The maximum usage factor at locations removed im the lug locations is; cur =0.755 The IWAs exist only on the U1 surge line as part of u.ie existing pipe whip restraint lug / collar design for R2, R4, and RS. R4 was previously evaluated for metal-to-metal gap closure (reference 1) due to normal thermal operating conditions and found to be acceptable. This condition was accounted for in the fatigue analysis performed for the lugs.
Code case H-122 was conservatively used to evaluate the IWAs.
The results indicate acceptable fatigue usage for the 40-year design life of the unit assuming the average current rate of 2 H/C cycles per year, but do not demonstrate CUFs less than 1.0 f' 'ho full 200 H/C design cycles. WE is currently eva.uating whether to use further refined analytical techniques to satisfy Code fatigue requirements or to modify the whip restraint design to climinate the IWA design. We expect to have this evaluation completed before the end of 1991. If we determine that a modification will be necessary to resolve the issue, we will advise the NRC of the schedule for installation of the modification.
8.O EYAkMATLQH_QLEREDDRRHEJLEQMkB The pressurizer surge nozzle loadings due to normal operating, seismic, and thermal stratification effects have been compared to the previously qualified PZR surge nozzle umbrella loads in the PZR stress report. The qualified umbrella loads are based on a safe end material with lower allowables than the PBNP PZR safe end material, and are transmitted by a 10 inch diameter pipe instead of 14 inches as used in the report. The worst case forces are less than 15% of the umbrella force allowab)es, and worst case moments are less than 65% of the umbrella bending moment allowables. Therefore it is deemed that the loads generated by the plant specific analysis (including thermal stratification effects) on the PZR surge nozzle are acceptable.
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