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MONTHYEARML20126L9251980-12-15015 December 1980 Technical Evaluation Rept, Environ Qualification of Safety- Related Electrical Equipment to Harsh Environs Project stage: Other ML20207L3521981-01-29029 January 1981 Informs That 810116 Extension for Time to Request Hearing Re 801024 Order for Mod of Lisense Acceptable & Consistent W/ 810108 Request Project stage: Other ML20126L9191981-05-29029 May 1981 Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.No Outstanding Items Requiring Immediate Corrective Action.Completion of Corrective Actions by 820630 Will Ensure Compliance W/Nrc 800523 Memorandum Project stage: Approval ML20041D7681982-03-0303 March 1982 Submits Correction to Util 820225 Ltr Re NUREG-0737,Item II.K.2.13, Thermal-Mechanical Rept - Effect of HPI on Vessel Integrity for Small Break LOCA W/No Auxiliary Feedwater. Project stage: Request ML20207N4381982-04-0606 April 1982 Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl Info Project stage: Request ML20054L0231982-06-30030 June 1982 Advises That Completion of Installation of Two Isolation Valves ASV-195 & ASV-196 for Automatic Isolation of Steam Source Line in Auxiliary Bldg Delayed Until 821231,in Response to IE Bulletin 79-01B Project stage: Other ML20054L8491982-07-0101 July 1982 Forwards Current Schedule for Installation of Qualified Electrical Equipment.Evaluation Worksheets & Test Repts Have Not Been Sent for Item II.D.3, Valve Position Indication, Since Five of Six Units Tested Failed Project stage: Other ML0310801341983-01-11011 January 1983 Withdrawn NRC Generic Letter 1983-001: Operator Licensing Examination Site Visit Project stage: Request ML20072A9681983-01-21021 January 1983 Advises That Proprietary Info in Franklin Research Ctr Technical Evaluation Rept Re Environ Qualification Must Remain Proprietary Until Released by Author.Remaining Documentation Will Be Submitted by 830131 Project stage: Other ML20064N5281983-02-0707 February 1983 Advises That Proprietary Data Reviewed in Plant Technical Evaluation Rept on Environ Qualification of safety-related Electrical Equipment.Westinghouse Equipment Items 62 & 63 No Longer Proprietary Project stage: Other ML20065A8411983-02-11011 February 1983 Informs That Licensee Will Submit Info Identifying Electrical Equipment Important to Safety & Schedule for Either Qualification or Replacement by 830520,per NRC Project stage: Other ML20071E4691983-03-10010 March 1983 Responds to NRC Re safety-related Electrical Equipment.Justification for Continued Operation Encl Project stage: Other NRC Generic Letter 1983-151983-03-23023 March 1983 NRC Generic Letter 1983-015: Implementation of Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds During Preservice & Inservice Examinations, Revision 1. Project stage: Request ML20073K9011983-03-25025 March 1983 Public Version of Rev 27 to Emergency Plan Supporting Procedure Administrative Memo 41, Emergency Duty Officer (EDO) & Other Emergency Duties Project stage: Request ML20073B3551983-04-0808 April 1983 Advises That Investigation of Category Ii.B in 830111 SER Re Environ Qualification of Electrical Equipment Identified No Equipment in Subj Category Per Project stage: Other ML20069L9601983-04-29029 April 1983 Advises That Justification for Continued Operation Will Be Included in 830520 Submittal Per Re Environ Qualification of Electrical Equipment,In Response to .Facility Presently Shut Down for Refueling Project stage: Other ML20073R5471983-04-29029 April 1983 Responds to NRC Re safety-related Electrical Equipment.Justification for Continued Operation Exists for All Equipment Which May Not Be Qualified.Response Submitted 830310 Contains No Changes or Proprietary Info Project stage: Other ML20071J6551983-05-20020 May 1983 Forwards Crystal River Unit 3 Environ Qualification Status, Per 10CFR50.49 Project stage: Other ML20071G8771983-05-20020 May 1983 Forwards Info Re Environ Qualification of Electrical Equipment Important to Safety,Per 10CFR50.49.List of Activities to Resolve Technical Evaluation Rept Open Items Encl.Namco Limit Switches Scheduled for Replacement Listed Project stage: Other ML20085J3351983-10-10010 October 1983 Discusses 831013 Meeting to Resolve Deficiencies Noted in Franklin Research Ctr Technical Evaluation Rept Re Environ Qualification of safety-related Electrical Equipment.Agenda & Supporting Documentation Encl Project stage: Meeting ML20082G3431983-11-23023 November 1983 Forwards Agenda for 831213 Meeting W/Nrc in Bethesda,Md to Discuss & Resolve Outstanding Issues Re Environ Qualification of Electrical Equipment Project stage: Meeting ML20083A2061983-11-29029 November 1983 Forwards Equipment Qualifications Manual,Rev 2 Project stage: Other 3F0184-29, Forwards Minutes of 831215 Meeting Re Equipment Qualification Issue Resolution.Minutes Reflect Results of 840124 Telcon.Response to IE Info Notice 79-22 Considered in Encl 3 Methodology1984-01-31031 January 1984 Forwards Minutes of 831215 Meeting Re Equipment Qualification Issue Resolution.Minutes Reflect Results of 840124 Telcon.Response to IE Info Notice 79-22 Considered in Encl 3 Methodology Project stage: Meeting ML20088A9051984-04-0303 April 1984 Forwards Generic Issues,Resolution of Open Items & Justifications for Continued Operations Per 831213 Meeting Re Environ Qualifications for safety-related Electrical Equipment Deficiencies Project stage: Meeting 3F0584-18, Forwards Response to NRC 840502 Questions Re Environ Qualification of Installed Electrical Equipment1984-05-31031 May 1984 Forwards Response to NRC 840502 Questions Re Environ Qualification of Installed Electrical Equipment Project stage: Other ML20090A0571984-06-26026 June 1984 Forwards Sys Component Evaluation Worksheets & Justifications for Continued Operation Re Environ Qualification of Electrical Equipment,In Response to NRC .Methodology Used to Create Master List Described Project stage: Other ML20094B8331984-08-0202 August 1984 Requests Extension of Qualification Program Completion Schedule to End of June 1985 Refueling Outage for Crosby Lift Indicating Switch Assemblies & Veam Thermocouple Connectors Project stage: Other ML20099C4911984-11-0909 November 1984 Application for Amends to License DPR-24 & DPR-27, Authorizing Additions to Tech Specs Re Overtemp delta-T & Overpower delta-T to Specify Time Constants Used in Measured delta-T & Avg Temp Lag Compensations.Fee Paid Project stage: Request ML20099C2991984-11-14014 November 1984 Forwards Corrected Tech Spec Page 15.2.3-3,per 841113 Discussion,Re Lag Compensation Term for Second Average Temp Term Project stage: Request ML20099D9351984-11-15015 November 1984 Submits Addl Info Re 841109 Tech Spec Change Request 102 Concerning Overpower & Overtemp Delta Temp Compensation Project stage: Request ML20101A2221984-12-13013 December 1984 Forwards Manufacturer Response Time Test Results to Suppl Info Provided in Re Overtemp & Overtemp delta-T Lag Compensation Project stage: Request ML20101Q5901984-12-28028 December 1984 Forwards Fee for Extension of Deadline for 840802 Environ Qualifications Per .Fee Paid Project stage: Other 3F0185-19, Submits Certifications for Environ Qualification of Electrical Equipment,Per Generic Ltr 84-24 Request.Insp of Target Rock Valves Scheduled During Refuel V1985-01-25025 January 1985 Submits Certifications for Environ Qualification of Electrical Equipment,Per Generic Ltr 84-24 Request.Insp of Target Rock Valves Scheduled During Refuel V Project stage: Other ML20101T7451985-02-0101 February 1985 Responds to Generic Ltr 84-24 Re Certification of Compliance w/10CFR50.49, Environ Qualification of Electric Equipment Important to Safety for Nuclear Power Plants. Appropriate Actions Taken to Correct Potential Deficiencies Project stage: Other ML20108D8621985-03-0101 March 1985 Requests Further Extension of 850331 outage-based Equipment Qualification Deadline for Hydrogen/Oxygen Analyzers.Revised Schedule for Completion of Qualification Testing on Hydrogen/Oxygen Analyzers Encl Project stage: Other ML20112H3081985-03-27027 March 1985 Requests Expedited Relief from Current 850331 Equipment Qualification Deadline for Facility Drywell & Oxygen Analyzers Until 851130 Due to Recent Change in Schedule for Upcoming Refueling Outage Project stage: Other ML20112H1641985-03-28028 March 1985 Forwards Rev 2 to Inservice Testing Program,Point Beach Nuclear Plant Units 1 & 2, as Part of Pump Relief Request 9.Requests That NRC Grant Interim Approval for Pump Relief Request Project stage: Request ML20100L0171985-04-0909 April 1985 Forwards Application Fee,Per NRC ,To Cover 850301 Request for Extension of 10CFR50.49 Equipment Qualification Deadline for Drywell Hydrogen & Oxygen Analyzers Currently Installed at Facility Project stage: Request ML20125E1931985-06-0505 June 1985 Advises of Fees Due for 841111 & 850502 Applications for Amends to Licenses DPR-24 & DPR-27 Re Environ Qualification of Water Regulating Valves & Lift Indicating Assemblies.Fees Due Irrespective of NRC Disposition of Application Project stage: Other ML20126J2931985-06-11011 June 1985 Authorizes Implementation of Proposed ASME Code Pump & Valve Inservice Testing Programs to Be Completed No Later than 850801,per 850328 Request for Relief from Requirements Project stage: Other ML20128A0391985-06-28028 June 1985 Submits Supplemental Info Re Questions Raised During Equipment Qualification (EQ) Insp During Wk of 850520. T-drains on Limitorque Motor Operators Replaced W/Plugs.All EQ Procedures Approved & Ready for Use Project stage: Supplement ML20137E9981985-08-16016 August 1985 Notifies of Problems That May Necessitate Extension of Equipment Qualification Deadline for Primary Containment Hydrogen & Oxygen Gas Analyzers,Per 10CFR50.49(h).Revised Testing Schedule for Analyzers Encl Project stage: Other ML20137T6811985-11-27027 November 1985 Provides Status of Environ Qualification Effort for Drywell Hydrogen & Oxygen analyzers.Architect-engineer Determined Equipment Located in Mild Environ Will Remain Operable During & for at Least 180 Days Following LOCA Project stage: Other ML20141M9031986-02-24024 February 1986 Requests Commitment of Necessary Resources to Address Policy Issues Delaying Resolution of Inservice Testing Program Matters.Interim Relief for Several Inservice Testing Requirements Due to Delay Also Requested Project stage: Other 1984-01-31
[Table View] |
Discusses 831013 Meeting to Resolve Deficiencies Noted in Franklin Research Ctr Technical Evaluation Rept Re Environ Qualification of safety-related Electrical Equipment.Agenda & Supporting Documentation EnclML20085J335 |
Person / Time |
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Site: |
Point Beach ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
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Issue date: |
10/10/1983 |
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From: |
Burstein S WISCONSIN ELECTRIC POWER CO. |
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To: |
Harold Denton, John Miller Office of Nuclear Reactor Regulation |
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References |
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IEB-79-01B, IEB-79-1B, TAC-42507, TAC-42508, TAC-42512, TAC-55557, TAC-55558, TAC-60640, TAC-60641, NUDOCS 8310130004 |
Download: ML20085J335 (41) |
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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] Category:UTILITY TO NRC
MONTHYEARML20059H9391990-09-13013 September 1990 Forwards Amended Response to Notice of Violations Noted in Insp Repts 50-266/89-27 & 50-301/89-26.Corrective Action: Revised Procedures Will Not Be Issued Until After Unit 2 Refueling Outage.Other Changes Anticipated by 901231 ML20059G7211990-09-0505 September 1990 Responds to Generic Ltr 90-03, Vender Interface for Safety- Related Components. Implementing Formal Vendor Interface Program for Every safety-related Component Impractical ML20028G9071990-08-31031 August 1990 Advises That long-term erosion/corrosion-induced Program for Pipe Wall Thinning in Place,Per Generic Ltr 89-08.Program Assures Erosion/Corrosion Will Not Lead to Degradation of Single & two-phase High Energy Carbon Steel Sys ML20059G8741990-08-31031 August 1990 Forwards Revised Security Plan,Per NRC .Summary of Revs Listed.Rev Withheld (Ref 10CFR3,50,70 & 73) ML20064A4711990-08-29029 August 1990 Forwards Semiannual Monitoring Rept,Jan-June 1990, Rev 1 to Process Control Program, Rev 7 to Environ Manual & Rev 5 to Odcm ML20058N6771990-08-0303 August 1990 Forwards Public Version of Revised Procedures to Emergency Plan manual.W/900813 Release Memo ML20058L1471990-08-0303 August 1990 Responds to NRC Re Weaknesses Noted in Insp Repts 50-266/90-201 & 50-301/90-201 Re Electrical Distribution. Corrective Actions:Design Basis Documentation Will Be Developed to Alleviate Weaknessess in Diesel Generators ML20058L5041990-07-30030 July 1990 Discusses & Forwards Results of fitness-for-duty Program Performance Data for 6-month Period Ending 900630 ML20055J2031990-07-25025 July 1990 Responds to NRC Bulletin 89-002 Re Insp of safety-related Anchor/Darling Model S350W Check Valves Supplied w/A193 Grade B6 Type 410 SS Retaining Block Studs.Studs Visually Inspected & No Cracks Found ML20055H7781990-07-24024 July 1990 Forwards Corrected Monthly Operating Rept for June 1990 for Point Beach Unit 2.Correction on Line 18 Regards Net Electrical Energy Generated ML20055H6621990-07-23023 July 1990 Forwards Central Files & Public Versions of Revised Epips, Including Rev 2 to EPIP 1.1.1,Rev 16 to EPIP 4.1,Rev 6 to EPIP 6.5,Rev 20 to EPIP 1.2,Rev 8 to EPIP 6.3,Rev 0 to EPIP 7.3.2,Rev 10 EPIP 10.2 & Rev 11 to EPIP 11.3 ML20058K8941990-07-23023 July 1990 Forwards June 1990 Updated FSAR for Point Beach Nuclear Plant Units 1 & 2.Steam Generator Upper Ph Guideline in Table 10.2-1 Changed from 9.3 to 9.4 ML20044A9091990-07-0606 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil in Transmitters Mfg by Rosemount.None of Listed Transmitters Installed at Plant in Aug 1988 Identified as Having High Failure Fraction Due to Loss of Fill Oil ML20055D4421990-07-0303 July 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Point Beach Nuclear Plant Unit 1,1990, Summary Rept ML20055D3471990-06-29029 June 1990 Provides Addl Response to Bulletin 88-008, Thermal Stresses in Piping Connected to Rcss. Engineering Evaluations Performed to Assure Code Compliance Due to Unanalyzed Condition of Thermal Stratification Addressed ML20055D6221990-06-29029 June 1990 Provides Suppl to Re Loss of All Ac Power.Test Demonstrated That Ventilation Mod & Recalibration of High Temp Trip for Auxiliary Power Diesel Improved Performance of Gas Turbine Generator as Alternate Ac Source ML20055D2291990-06-22022 June 1990 Informs NRC That Gj Maxfield Promoted to Plant Manager effective,900701 ML20055D6231990-06-22022 June 1990 Advises of Decision to Proceed W/Leak Testing of Sys During Plant Refueling Outage Due to Delay in Delivery of Gamma-Metrics Hardware Fix Kits.Test Revealed That Both in-containment Cable & Detector Assembly Cable Had Leaks ML20044A0011990-06-18018 June 1990 Provides Current Implementation Status of Generic Safety Issues at Plant,In Response to Generic Ltr 90-04 ML20043D6511990-05-25025 May 1990 Discusses Cycle 18 Reload on 900519,following 7-wk Refueling & Maint Outage.Reload SER for Cycle 18 Demonstrates That No Unreviewed Safety Questions,As Defined in 10CFR50.59, Involved in Operation of Unit During Cycle ML20043B1481990-05-18018 May 1990 Advises That Necessary Info Received from Westinghouse Re Revised Administrative Controls for NRC Bulletin 88-002, Rapidly Propagating Fatique Cracks in Steam Generator Tubes. ML20043B1101990-05-17017 May 1990 Documents Status of Evaluations Committed to Be Performed Re IE Bulletin 79-14 Program.Support CH-151-4-H50 Modified During Unit 1 Refueling Outage & Now in Code Compliance. Meeting Proposed During Wks of 900618 or 900716 ML20043A9921990-05-16016 May 1990 Advises of Typo in Item 2.C Re Emergency Diesel Generator Meter Accuracy in Submittal Re Corrective Actions in Response to Concerns Identified During Electrical Insp.Meter Calibr Reading Should Be 3,050 Kw Not 350 Kw ML20043B0481990-05-16016 May 1990 Updates 890330 Response to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Util Will Replace Unit 1 Inverter & Battery Charger Circuit Breakers within 30 Days After Receipt & QA Verification ML20043A7631990-05-15015 May 1990 Responds to Notice of Violation & Forwards Civil Penalty in Amount of $87,000 for Violations Noted in Insp Repts 50-266/89-32,50-266/89-33,50-301/89-32 & 50-301/89-33. Addl Employees Added in QA & Corporate Nuclear Engineering ML20042H0201990-05-10010 May 1990 Forwards List of Concerns Identified at 900417 Electrical Insp Exit Meeting to Discuss Preliminary Findings of Special Electrical Insp Conducted on 900319-0412 Re Adequacy of Electrical Distribution Sys ML20043A2181990-05-10010 May 1990 Forwards Nonproprietary & Proprietary Version of Point Beach Nuclear Plant,Emergency Plan Exercise,900314. ML20042G7441990-05-0909 May 1990 Forwards LER 90-003-00 ML20042G7361990-05-0808 May 1990 Forwards LER 90-004-00 ML20042E4571990-04-10010 April 1990 Documents Basis for Request for Temporary Waiver of Compliance of Tech Spec 15.3.7.A.1.e Re Diesel Generator Fuel Oil Supply ML20012F2961990-03-29029 March 1990 Withdraws Tech Spec Change Request 120 Re Staff Organization Changes & Deletion of Organizational Charts,Based on Further Corporate Restructuring within Util ML20012D8301990-03-20020 March 1990 Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Power Plants. No Limiting Condition for Operation Required for Overfill Protection Sys at Plant ML20012D4241990-03-0808 March 1990 Forwards Public Version of Revised Epips,Including Rev 17 to EPIP 1.3,Rev 8 to EPIP 3.1,Rev 15 to EPIP 4.1,Rev 1 to EPIP 6.7,Rev 1 to EPIP 7.1,Rev 11 to EPIP 7.2.1 & Rev 11 to EPIP 7.2.2 ML20011F7531990-02-26026 February 1990 Informs NRC of Apparent Inconsistency Between Min Level of Boric Acid Solution to Be Maintained in Boric Acid Storage Tanks Per Tech Specs & Amount of Deliverable Boric Acid Assumed in Safety Analyses ML20006B7091990-01-25025 January 1990 Responds to NRC Bulletin 89-002 Re Check Valve Bolting Insp. All Anchor-Darling Model S35OW Check Valves Inspected for Cracked Internal Bolting During Refueling Outage of Unit.No Indications of Cracks Found ML20006A3381990-01-18018 January 1990 Forwards PDR & Central Files Versions of Rev 16 to EPIP 9.2 & Forms, Radiological Dose Evaluation. ML20006A3411990-01-16016 January 1990 Forwards Rev 16 to EPIP 9.2, Radiological Dose Evaluation to Be Inserted in EPIP Manual ML20005G0901990-01-12012 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Outside of Intake Structure Will Be Inspected for Excessive Corrosion on Semiannual Basis & Forebay & Pumphouse Inspected ML20005G1751990-01-12012 January 1990 Responds to NRC 891213 Ltr Re Violations Noted in Insp Repts 50-266/89-30 & 50-301/89-30.Corrective Action:Procedure RP-6A, Steam Generator Crevice Flush (Vacuum Mode), Initiated ML20005H0551990-01-11011 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Util Will Provide Specific Training to All Members Responsible for Refueling Operation to Emphasize Importance of Procedures ML20005G9031990-01-0909 January 1990 Forwards Monthly Operating Repts for Dec 1989 for Point Beach Nuclear Plant Units 1 & 2 & Revised Monthly Operating Rept for Nov for Point Beach Unit 2 ML20005G5641990-01-0808 January 1990 Updates Progress Made on Issues Discussed in Insp Repts 50-266/89-12 & 50-301/89-11 Re Emergency Diesel Generator Vertical Slice SSFI Conducted by Util.By Jul 1990,revised Calculation Re as-built Configuration Will Be Performed ML20005E5441989-12-29029 December 1989 Describes Actions & Insps Completed During Recent U2R15 Refueling Cycle & Proposed Schedule for Completion of NRC Bulletin 88-008 Requirements,Per Util 881221 & 890616 Ltrs. Extension Requested Until 900631 to Submit Data Evaluation ML20005E5451989-12-28028 December 1989 Advises That Addl Info Required from Westinghouse to Meet Util 890621 Commitment to Adopt Administrative Control Re Rapidly Propagating Fatigue Cracks in Steam Generator Tubes Per NRC Bulletin 88-002.Info Anticipated by End of Mar 1990 ML20005E5381989-12-27027 December 1989 Provides Update of Status of Implementation of Resolution of Human Engineering Discrepancies Documented During Dcrdr. Lighting Intended to Document Deficiencies Per NUREG-0700, Eleven Human Engineering Discrepancy Computers Resolved ML19354D5781989-12-21021 December 1989 Certifies Implementation of Fitness for Duty Program Which Meets Requirements of 10CFR26 for All Personnel Having Unescorted Access to Plant Protected Areas.Periodic Mandatory Random Chemical Testing Will Commence on 900103 ML20005D8071989-12-21021 December 1989 Forwards Response to Violations Noted in Insp Repts 50-266/89-29 & 50-301/89-29.Response Withheld (Ref 10CFR73.21) ML20005E2301989-12-21021 December 1989 Forwards Reactor Containment Bldg Integrated Leak Rate Test Point Beach Nuclear Plant Unit 2, Summary Rept,Per 10CFR50,App J.Type A,B & C Leak Test Results Provided ML20042D2391989-12-21021 December 1989 Responds to Violations Noted in Insp Repts 50-266/89-27 & 50-301/89-26.Corrective Actions:Superintendent of Health Physics Discussed Log Book Entry Requirements W/Health Physics Contractor Site Coordinator ML19354D6231989-12-15015 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor- Operated Valve Testing & Surveillance.Util Intends to Meet All Recommendations Discussed in Ltr Except for Item C Re Changing motor-operated Valve Switch Settings 1990-09-05
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lHsconsin Electnc romcome 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, Wl 53201 l
October 10, 1983 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D.C. 20555 Attention: Mr. J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 RESOLUTION OF SAFETY EVALUATION REPORTS FOR ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 On December 27, 1982, Wisconsin Electric received the Safety Evaluation Reports (SERs) regarding the Environmental Qualifi-cation of Safety-Related Electrical Equipment at Point Beach Nuclear Plant, Units 1 cnd 2 (PBNP). The SERs each contained a Technical Evaluation Report (TER) , written by Franklin Research Center under contract to the NRC, which noted a number of environmental qualifi-cation documentation deficiencies for safety-related electrical equipment at PBNP. In our letter to you dated February 18, 1983, we provided justification for continued operation until the documenta-tion deficiencies could be officially resolved and stated our inten-tion to request a meeting with your Staff to discuss additional documentation assembled to resolve the deficiencies. We have recent-ly been informed by our NRC Project Manager that such a meeting has been scheduled for October 13, 1983. Enclosure 1 to this letter is an agenda for this meeting which includes a discussion of all of the deficiencies noted in the TERs. It is our understanding that l Wisconsin Electric would subsequently confirm in writing the resolu-tions reached at the meeting for each of the deficiencies and your Staff would then issue a supplemental SER to officially resolve the deficiencies on the PBNP dockets.
In a related matter, Enclosure 2 to this letter is a revised " List of Electric Equipment Important to Safety to be Envi-ronmentally Qualified" for PBNP. This list has been revised from the list submitted as Enclosure 1 to our May 20, 1983 letter to Mr. H. R. Denton regarding " Environmental Qualification of Electric Equipment Impcrtant to Safety Within the Scope of 10 CFR 50.49." The l revision corrects a few minor typographical errors and adds the Crosby lift indicating switch casemblies planned for installation on the pressurizer code safety valves for both PBNP units. The lift
@ I 0310130004 031010 DR ADOCK 050002gg
Mr. H. R._Denton October 10, 1983 indicating switch assemblies were inadvertently excluded from the original list.
The Crosby lift indicating switch assemblies have not yet been environmentally qualified due to test difficulties in the
~ initial qualification program. Crosby is now beginning a second qualification test program. Wisconsin Electric does not intend to install the Crosby switch assemblies on the PBNP pressurizer code safety valves until the qualification is successfully completed. The Crosby switch assemblies are now planned for installation on PBNP during the outages currently planned to end on November 2, 1984 (Unit 2)'and May 24, 1985 (Unit 1). Paragraph (g) of NRC rule 10 CFR 50.49 imposed an environmental qualification deadline for this equipment of "by the end of the second refueling outage after March 31, 1982" (i.e., June 30, 1983 for PBNP Unit 2 and March 30, 1984 for PBNP Unit 1). The rule also states, however, that "the Director of the Office of Nuclear Reactor Regulatory [ sic] may grant requests for extensions of this deadline to a date no later than November 30,
. 1985,-for specific pieces of equipment if these requests ... demon-strate good cause for the extension, such as procurement lead time, test complications, and installation problems." Therefore, an extension of the environmental qualification deadline imposed by 10 CFR 50.49 is requested until May 24, 1985 for the Crosby lift indicating switch assemblies and associated cables, splices, connec-tors, etc. to be installed on the pressurizer code safety valves at PBNP. This date is the scheduled end of the next refueling outage for PBNP, Unit 1, subsequent to the expected completion date of the second Crosby test program.
We would be pleased to answer any questions you may have regarding this information or the request for extension of the environmental qualification deadline.
Very truly yours, C
~
, . {
Sol Burstein Exe utive Vice President Enclosures Copy to NRC Resident Inspector
_ . _ . . . . . , _ _ . _ _ . _ _ _ _ __ _ -_~
ENCLOSURE 1 AGENDA FOR WISCONSIN ELECTRIC MEETING WITH NRC STAFF TO RESOLVE ENVIRONMENTAL QUALIFICATION SER DEFICIENCIES
- 1. Generic EQ Deficiencies
- 2. Specific Equipment EQ Deficiencies Pressure, D/P, and Level Transmitters Solenoid Valves for Air-0perated Valves Motors (including splices and bearing / lubricant)
Temperature Measurement Devices Electro-Pneumatic (I/P). Transducers Electrical Distribution Devices Limit Switches for Air-0perated Valves / Acoustical Monitors Motor Operated Valves (including lubricants)
- 3. May 20, 1983 Response to 10 CFR 50.49 and Extension Requests
- 4. September 1,1983 Response to Regulatory Guide 1.97 l
ENCLOSURE 2 LIST OF ELECTRIC EOUIPMENT IMPORTANT TO SAFETY TO BE ENVIF.ONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNIT 1 AND 2 (October 10,1983)
Notes: 1. A request for an extension of the environmental qualification deadline imposed by 10 CFR 50.49(g) (i.e., "the end of the second refueling outage after March 31,1982") was requested for the final environmental qualification documentation only (not installation or operation) of this equipment in our letter to Mr. H. R. Denton dated May 4, 1983. The end of the second refueling outage after March 31, 1982 was June 30, 1983 for PBNP, Unit 2, and is expected to be March 30, 1984 for PBNP, Unit 1. The requested deadline extension was granted until March 30, 1984 by Mr. H. R. Denton's letter to Mr. C. W. Fay dated July 22, 1983.
- 2. Some equipment items were listed in NRC Qualification Category II. A
(" Equipment Qualification Not Established") or II.C (" Equipment Satisfies All Requirements Exr.ept Qualified Life or Replacement Schedule Justified") in the Technical Evaluation Report (TER) attached to the PBNP Safety Evaluation Report dated December 22, 1982 regarding " Environmental Qualification of Safety Related Electrical Equipment." A meeting has been scheduled with the NRC Staff on October 13, 1983 to resolve the documentation questions raised in the TER. Wisconsin Electric considers this equipment to be environmentally qualified in accordance with 10 CFR 50.49 (i.e.,
D0RGuidelines).
- 3. This equipment is within the scope of 10 CFR 50.49(b)(3) (i.e.,
"Certain post-accident monitoring equipment"). An extension of the environmental qualification deadline imposed by 10 CFR 50.49(g)
(i.e., "the end of the second refueling outage after March 31, 1982") was requested until November 1,1984 in our letter to Mr. H. R. Denton dated May 4,1983. The requested deadline exten-sion was granted until November 1, 1984 by Mr. H. R. Denton's letter to Mr. C. W. Fay dated July 22, 1983.
- 4. A request for extension of the environmental qualification deadline was requested for this equipment in accordance with 10 CFR 50.49(g) by our letter to Mr. H. R. Denton dated May 20, 1983. The requested deadline extension was granted until November 1, 1984 by Mr. H. R. Denton's letter to Mr. C. W. Fay dated July 22, 1983.
- 5. A request for extension of the enviror. mental qualification deadline has been requested for this equipment until May 24, 1985 by this letter in accordance with 10 CFR 50.49(g).
- 6. The " installation operation" date is the date by which the equipment was turned over the operations group for operation. The final official turnover may not be. completed by the specified date due to the lack of certain formal quality assurance documentation required.
The final operation configuration may also not be complete due to various power supply, instrumentation loop, and control board modifications being implemented at PBNP.
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLFAR PLANT, UNITS 1 AND 2 System: 1. Safety Injection Page: I-1 Date: October 10, 1983
' Expected Expected or Actual Environmental It a PBNP NRC No. Tag No.
Installation / Qualification TER No. Description Operation Date Documentatiop,Qate
- 1. 1-P15A&B 24 a. Westinghouse Motors - High-Head Safety Original Equipment 6/30/83
2-P15A&B Injection Pumps None b. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall or Equivalent 41 c. Power Cables - Okonite Okonex-Insulated and Okoprene-Jacketed 5000 Volt Power 50 d. Motor & Pump Bearing Lubricant - American Oil Co. No. 68 Oil or Equivalent
, 2. 1&2-SI878 63 a. Limitorque Valve Motor Operators - High- Original Equipment 6/30/83(2)
B&D Head Cold Leg Injection Line Isolation Valves 43 b. Power Cable - Kerite 600 Volt Power Cable 43 c. Control Cable - Kerite 600 Volt Control Cable None d. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall or Equivalent
- e. Electrical Penetration Splices - Bechtel 36 Dwg. No. SK-E-165/Raychem Type SFR 35 f. Electrical Penetration Assembly - Westinghouse /
Crouse Hinds Welded Canister Penetration 54 g. Main Gear Case Lubricant - American Oil Co.
Amolith #1 EP or AMDEX #2 EP Greases
- 56 h. Geared Limit Switch Assembly Lubricant -
f Mobil Oil Co. No. 28 Grease
- 3. 1&2-SI878 62 a. Limitorque Valve Motor Operators - High-Head Original Equipment 6/30/83(2)
A&C Reactor Vessel Injection Line Isolation Valves 43 b. Power Cable (see Item 2.b)
- 43 c. Control Cable (see Item 2.c)
None d. Motor-to-Lead Splices (see Item 2.d) 36 e. Electrical Penetration Splices (see Item 2.e) 35 f. Electrical Penetration Assembly (see Item 2.f) 54 g. Main Gear Case Lubricant (see Item 2.g) 56 h. Geared Limit Switch Assembly Lubricant (see Item 2.h)
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BFACH NUCLEAR PLANT, UNITS 1 AND 2 System: I. Safety Injection Page: I-2 Date: October 10, 1983 Expected Expected or Actual Environmental Itco PBNP NRC Installation / Qualification No. Tag No. TER No. Description Operation Date Documentation Date
- 4. 1&2-SI852 63 a. Limitorque Valve Motor Operators - Low-Head Original Equipment 6/30/83(2)
A&B Reactor Vessel Injection Line Isolation Valves 43 b. Power Cable (see Item 2.b) 43 c. Control Cable (see Item 2.c)
None d. Motor-to-Lead Splices (see Item 2.d) 36 e. Electrical Penetration Sp7 ices (see Item 2.e) 35 f. Electrical Penetration Assembly (see Item 2.f) 54 g. Main Gear Case Lubricant (see Item 2.g) 56 h. Geared Limit Switch Assembly Lubricant (see Item 2.h)
- 5. 1&2-SI851 66 (Unit 1) a. Limitorque Valve Motor Operators - Low-Head Original Equipment 6/30/83(2)
A&B 70 (Unit 2) Safety Injection Suction from Containment Sump B Isolation Valves
, 43 b. Power Cable (see Item 2.b) 39 c. Control Cable - Rome 600 Volt Control Cable i
None d. Motor-to-Lead Splices (see Item 2.d) 54 e. Main Gear Case Lubricant (see Item 2.g) 56 f. Geared Limit Switch Assembly Lubricant (see Item 2.h)
- 6. 1&2-PT922 1 a. Foxboro Pressure Transmitters - Safety Injection 12/10/82 (Unit 1) 3/30/84(1)
& 923 Pump Discharge Pressure 6/30/83 (Unit 2)
None b. Cable Splices - Raychem Type WCSF-N 40 c. Instrumentation Cable - Boston Insulated Wire &
i Cable Co. Bostrad 7 Twisted Shielded Pair 1
- 7. 1&2-FT924 4 a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 2) 3/30/84(1)
& 925 High-Head Safety Injection Line Flow 3/30/84 (Unit 1)
None b. Instrumentation Cable - Anaconda, Rockbestos, or Brand Rex Twisted, Shielded Pair
- 3. 1&2-FT928 3 a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 1) 3/30/84(1)
Low-Head Safety Injection Line (Train B) Flow 3/30/84 None b. Instrumentation Cable - Anaconda, Rockbestos, or Brand Rex Twisted, Shielded Pair
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
~
System: I. Safety Injection Page: I-3 Date: October 10, 1983 Expected Expected or Actual Environmental Item PBNP NRC Installation / Qualification Nr. Taq'No. TER No. Description Operation Date Documentation Date
- 9. 1&2-PT936, None a. Foxboro Pressure Transmitters - Safety Injec- 12/10/82 (Unit 1) 3/30/84(3) 937, 940, tion Accumulator Pressure 6/30/83 (Unit 2)
& 941 42 b. Instrumentation Cable - Okonite Okotherm-Insul-ated and Okoseal-Jacketed Twisted, Shielded Pair or Okonite PVC-Insulated and Jacketed Twisted, Shielded Pair (1-PT937 only) 36 c. Electrical Penetration Splices - Bechtel Dwg.
No. SK-E-165/Raychem Type SFR 35 d. Electrical Penetration Assembly - Westinghouse /
Crouse Hinds Welded Canister Penetration
- 10. 1&2-LT960 5 a. Gems Delaval Level Transmitter - Containment 12/10/82 (Unit 1) 3/30/84(1)
& 961 Sump B Water Level 6/30/83 (Unit 2)
None b. Conax Electrical Conductor Seal Assembly (ECSA)
None c. ECSA-to-Cable Splice - Raychem Type WCSF-N None d. Instrumentation Cable - Anaconda, Rockbestos, or Brand Rex Twisted, Shielded Triple None e. Cable-to-Penetration Splices - Raychem Type WCSF-N None f. Electrical Penetration Assembly - Westinghouse Modular Penetrations
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENlALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: II. Containment Spray Page: 11-1 Date: October 10, 1983 Expected Expected or Actual Environmental Item PBNP NRC Installation / Qualification No. Tag No. TER No. Description Operation Date Documentation Date
- 1. 1-P14A&B 25 a. Westinghouse Motors - Containment Spray Pumps Original Equipment 6/30/83(2) 2-P14A&B None b. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall or Equivalent 43 c. Power Cables - Kerite 600 Volt Power 55 d. Motor Bearing Lubricant - American Oil Co. Amolith
- 2 Grease or Equivalent 52 e. Pump Bearing Lubricant - American Oil Co. Rykon Industrial No. 32 Oil
- 2. 1&2SI860 64 a. Limitorque Valve Motor Operators - Containment Original Equipment 6/30/83(2)
A,B,C,& D Spray Pump Discharge Line Isolation Valves 43 b. Power Cables - Kerite 600 Volt Power 39 c. Control Cables - Rome 600 Volt Control None d. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall or Equivalent 54 e. Main Gear Case Lubricant - American Oil Co.
Amolith #1 EP or Amdex #2 EP Greases
. 56 f. Geared Limit Switch Assembly Lubricant - Mobil Oil Co. No. 28 Grease
- 3. 1&2SI871 64 a. Limitorque Valve Motor Operators - Containment Original Equipment 6/30/83(2)
A&B Spray Pump Suction from RHR Heat Exchange Outlet Isolation Valves 43 b. Power Cables (see Item 2.b) 39 c. Control Cables (see Item 2.c)
None d. Motor-to-Lead Splices (see Item 2.d) 54 e. Main Gear Case Lubricant (see Item 2.f) 56 f. Geared Limit Switch Assembly Lubricant (see Item 2.f)
- . . = --. - -_ .- -.
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEPCH NUCLEAR PLANT, UNITS 1 AND 2 System: II. Containment Spray Page: II-2 Date: October. 10, 1983 Expected
, Expected or Actual Environmental Item PBNP NRC -Installation / . Qualification No. Tag No. TER No. Description Operation Date Documentation Date
- 4. 1&2-SI836 33 a. Fisher Electro-Pneumatic (I/P) Transducers - 6/30/83 (Unit 2) 6/30/83 (Unit 2)
A&B Containment Spray Additive Tank Outlet Isolation 3/30/84 (Unit 1) 3/30/84 (Unit 1)
Valve Air Operators 57 b. NAMCO Limit Switches - Valve Position Indication None c. Conax Electrical Conductor Seal Assemblies (ECSAs) for NAMCO Limit Switches None d. ECSA-to-Cable Splices - Raychem Type WCSF-N 39 e. Control Cable - Rome 600 Volt Control None f. I/P Instrumentation Cable - Okonite PVC-Insulated and Jacketed Twisted, Shielded Pair
- 5. 1&2-LT931 2 a. Foxboro Differential Pressure Transmitter - 6/30/83 (Unit 2) 3/30/84(1)
Containment Spray Additive Tank Water Level 3/30/84 (Unit 1)
None b. Instrumentation Cable - Anaconda, Rockbestos, or Brand Rex Twisted, Shielded Pair i
j '6. 1&2-FT962 None a. Foxboro Differential Pressure Transmitter -
' 3/30/84 (Unit 1)- 11/1/84(3)
& 953 Containment Spray Pump Discharge Line Flow 11/1/84 (Unit 2)
None b. Instrumentation Cable - Anaconda, Rockbestos, j or Brand Rex Twisted Shielded Pair i
i 1
e 2
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: III. Auxiliary Coolant Page: III-1 Date: October 10, 1983 Expected Expected or Actual Environmental Item PBNP NRC Installation / Qualification No. Tag No. TER No. Description Operation Date Documentation Date
- 1. 1-P10A&B 27 a. Westinghouse Motors - Residual Heat Removal Original Equipment 6/30/83(2) 2-P10A&B (Low-Head Safety Injection) Pumps None b. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall or Equivalent 43 c. Power Cables - Kerite 600 Volt Power i 55 d. Motor Bearing Lubricant - American Oil Co.
Amolith # 2 Grease or Equivalent 52 e. Pump Bearing Lubricant - American Oil Co.
Rykon Industrial No. 32 Oil
- 2. 1-P11A&B 26 a. Westinghouse Motors - Component Cooling Water Original Equipment 6/30/83(2) 2-P11A&B Pumps None b. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall or Equivalent 43 c. Power Cables - Kerite 600 Volt Power 55 d. Motor Bearing Lubricant - American Oil Co.
Amolith #2 Grease or Equivalent 51 e. Pump Bearing Lubricant - American Oil Co.
Industrial No. 46 Oil
- 3. 1&2-AC738 66 a. Limitorque Valve Motor Operators - Component Original Equipment 6/30/83(2)
- A&B Cooling Water to RHR Heat Exchanger Isolation Valves 43 b. Power Cable - Kerite 600 Volt Power 39 c. Control Cable - Rome 600 Volt Control None d. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall or Equivalent 54 e. Main Gear Case Lubricant - American Oil Co.
Amolith #1 EP or AMDEX #2 EP Greases 56 f. Geared Limit Switch Assembly Lubricant - Mobil Oil Co. No. 28 Grease
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT -
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: III. Auxiliary Coolant Page: III-2 Date: October 10, 1983 Expected Expected or Actual Environmental Item PBNP NRC Installation / Qualification No. Tag No. TER No. Description Operation Date Documentation Date
- 4. 1&2-AC624, 33 a. Fisher Electro-Pneumatic (I/P) Transducers - 6/30/83(Unit 2) 625, & 626 6/30/83 (Unit 2)
Residual Heat Removal Heat Exchanger Discharge 3/30/84 (Unit 1) 3/30/84 (Unit 1)
(624 & 625) and Bypass (626) Line Throttle Valves 57 b. NAMCO Limit Switches - Valve Position Indication None c. Conax Electrical Conductor Seal Assemblies (ECSAs) for NAMCO Limit Switches None d. ECSA-to-Cable Splices - Raychem Type WCSF-N 39 e. Control Cable - Rome 600 Volt Control None f. I/P Instrumentation Cable - Okonite PVC-Insulated and Jacketed Twisted, Shielded Pair
- 5. 1&2-FT626 7 a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 2) 3/30/84(1)
Residual Heat Removal (Low-Head Safety - 3/30/84 (Unit 1)
Injection-Train A) Discharge Line Flow None g. Cable Splices - Raychem Type WCSF-N 40 c. Instrumentation Cable - Boston Insulated Wire
& Cable Co. Bostrad 7 Twisted, Shielded Pair
- 6. 1&2-PT628 8 a. Foxboro Pressure Transmitters - Residual Heat 6/30/83 (Unit 2) 3/30/84(1)
& 629 Removal (Low-Head Safety Injection) Pump 3/30/84 (Unit 1)
Discharge Pressure None b. Cable Splices - Raychem Type WCSF-N 40 c. Instrumentation Cable - Boston Insulated Wire
& Cable Co. Bostrad 7 Twisted, Shielded Pair (Unit 1) or Okonite PVC-Insulated and Jacketed Twisted, Shielded Pair (Unit 2)
- 7. 1&2-FT619 6 a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 2) 3/30/84(1)
Component Cooling Water Discharge Line Flow 3/30/84 (Unit 1)
None b. Cable Splices - Raychem Type WCSF-N
- c. Instrumentation Cable - Boston Insulated Wire
& Cable Co. Bostrad 7 Twisted, Shielded Pair
. - - - _ -. . -- - . - . . . . . - . - _ - -- . . - . - . - .- . . =.
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT- .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
~
System: III. Auxiliary Coolant Page: III-3 Date: October 10, 1983 Expected Expected or Actual Environmental i Item PBNP NRC Installation /
i NB. Tag No. TER No. Description Qualification Operation Date Documentation Date
- 8. 1&2-TE621 30 a. Conax Resistance Temperature Detectors - 6/30/83 (Unit 2) 3/30/84(1) j Component Cooling Heat Exchange' Outlet Line 3/30/84 (Unit 1)
Temperature
- l None b. Cable Splices - Raychem Type WCSF-N 40 c. Instrumentation Cable - Boston-Insulated Wire &
Cable Co. Bostrad 7 Double Twisted, Shielded Pair l
- 9. 1&2-TE622 30 a. Conax Resistance Temperature Detectors - 6/30/83 (Unit 2) 3/30/84(1)
& 623 Residual Heat Removal Heat Exchanger Outlet 3/30/84 (Unit 1)
Line Temperature
- None b. Cable. Splices - Raychem Type WCSF-N i
- None c. Instrumentation Cable - Anaconda, Rockbestos, t
or Brand Rex Twisted, Shielded Triple
}
i i
1 I
I 1
\ :
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: IV. Auxiliary Feedwater Page: IV-1 Date: October 10, 1983 Expected Expected or Actual Environmental Item PBNP NRC Installation / Qualification N). Tag No. TER No. Description Operation Date Documentation Date
- 1. 1&2-FT4036 None a. Foxboro Differential Pressure Transmitters - 7/5/81 3/30/84(3)
& 4037 Auxiliary Feedwater to Steam Generator Line Flow
- b. Instrumentation Cable - Boston Insulated Wire &
Cable Co. Bostrad 7 Twisted, Shielded Pair
- 2. LT4038, 17 a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 2) 3/30/84(1)(3) 4039, 4040, Condensate Sterage Tank Water Level 3/30/84 (Unit 1)
& 4041 b. Instrumentation Cable - Anaconda, Rockbestos, or Brand Rex Twisted, Shielded Pair I
i N
1 1
I i
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 ANO 2 System: V. Reactor Coolant Page: V-1 Date: October 10, 1983 Expected Expected or Actual Environmental Itco PBNP NRC Installation / Qualification No. Tag No. TER No. Description Operation Date Documentation Date 1.* 1&2-RC515 61 a. Limitorque Valve Motor Operators - Pressurizer Original Equipment 6/30/83(2)
& 516 Power Operated Relief Valve Blocking Valves 43 b. Power Cables - Kerite 600 Volt Power 39 (43) c. Control Cables - Rome 600 Volt Control (Kerite for 1-RC515)
None d. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall
, or Equivalent 36 e. Electrical Penetration Splices - Bechtel Dwg.
No. SK-E-165/Raychem Type SFR 35 f. Electrical Penetration Assembly - Westinghouse /
Crouse Hinds Welded Canister Penetrations 54 g. Main Gear Case Lubricant - American Oil Co.
Amolith #1 EP or AMDEX #2 EP Greases 56 h. Geared Limit Switch Assembly Lubricant- Mobil Oil Co. No. 28 Grease 2.* 1&2-RC430 19 a. ASCO Solenoid Valves - Pressurizer Power 12/10/82 (Unit 1) 6/30/83
& 431C Operated Relief Valve Air Operator 6/30/83 (Unit 2)
- b. NAMCO Limit Switches- Valve Position Indication 58 c. Conax Electrical Conductor Seal Assemblies (ECSAs) for NAMCO Limit Switches None d. ECSA-to-Cable Splices - Raychem Type WCSF-N 43 e. Control Cable - Kerite 600 Volt Control ,
- 36 f. Electrical Penetration Splices (see Item 1.e) 35 g. Electrical Penetration Assembly (see Item 1.f) 3.* 1&2-RC None a. Target Rock Solenoid Valves - Reactor Coolant 6/30/83 (Unit 2) 3/30/84 570A&B System Gas Vent Line Isolation Valves 3/30/84 (Unit 1) 575A&B, & None b. Conax Electrical Conductor Seal Assemblies (ECSAs)
- This equipment is not safety-related. Its failure or spurious operation can not prevent the achievement or maintenance of safe shutdown or mitigation of design-basis accidents. This equipment is not within the scope of 10 CFR 50.49(b) but is listed here for completeness.
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT -
TO SAFETY TO BE ENVIR0fetENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: - V. Reactor. Coolant Page: V-2
- j. Date: October 10, 1983 I:
Expected Expected or Actual Environmental
. Item PBNP NRC Installation / Qualification
- N o. Tag No. TER No. Description Operation Date Documentation Date i
.580A&B None c. ECSA-to-Cable Splices - Raychem Type WCSF-N i None d. Control Cable - Anaconda, Rockbestos, or Brand '
, Rex 600 Volt Control None e. Electrical Penetration Splices - Raychem Type WCSF-N l None f. Electrical Penetration Assembly-Westinghouse
- .. Modular Penetrations
- 4. 1&2-PT420, 13 a. Foxboro Pressure Transmitters - Reactor Coolant 6/30/83 (Unit 2) 3/30/84(1)(3)
{ '420A, & System Wide-Range Pressure 3/30/84 (Unit 1)
! 420B None b. Instrumentation Cable Anaconda, Rockbestos, or Brand Rex Twisted Shielded Pair None c. Electrical Penetratiion Splices - Raychem Type i WCSF-N None d. Electrical Penetration Assembly - Westinghouse Modular Penetration
, 5. 1&2-LT 11 a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 2) 3/30/84(1) 426, 427, Pressurizer Water Level 3/30/84 (Unit 1)
- 428, & 433 42 b. Instrumentation Cable.- Okonite Okotherm -
1 Insulated and Okoseal-Jacketed Twisted, Shielded Pair t 36 c. Electrical Penetration Splices (see Item 1.e) .
- 35 d. Electrical Penetration Assembly (see Item 1.f) l 6. 1&2-PT 10 a. Foxboro Pressure Transmitters - Pressurizer 12/10/82 (Unit 1) 3/30/S4(1) !
429, 430, Narrow-Range Pressure 6/30/83 (Unit 2) !
} 431, & 449 42 b. Instrumentation Cable (see Item 5.b) i
, 36 c. Electrical Penetration Splices (see Item 1.e) *
! 35 d. Electrical Penetration Assembly (see Item 1.f) 1 l 7. 1&2-LT None a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 2) 3/30/84(3) i 494 & 495 Reactor Vessel Wide-Range Water Level 3/30/84 (Unit 1)
- None b. Instrumentation Cable (see Item 4.b) i None c. Electrical Penetration Splices (see Item 4.c) t j None d. Electrical Penetration Assembly (see Item 4.d) l 1 '
a
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
4 TO SAFETY TO BE ENVIR00 MENTALLY QUALIFIED '
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
- System
- V. Reactor Coolant Page: V-3 Date: October 10, 1983 Expected '
Expected or Actual Environmental
- Item PBNP NRC Installation / '
1 Ns. Tag No. TER No. Description Qualification-Operation Date Documentatiop 0 ate
- 8. 1&2-LT None a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 2) 3/30/84 "'
496 & 497 Reactor Vessel Narrow-Range Water Level 3/30/84 (Unit 1) t None b. Instrumentation Cable (see Item 4.b) i None c. Electrical Penetration Splices (see Item 4.c) !
None d. Electrical Penetration Assembly (see Item 4.d) !
)- 9. 1&2-PT498 None a. Foxboro Pressure Transmitters - Reactor 6/30/83 (Unit 2) 3/30/84(3)
Coolant System. Gas Vent Discharge Line Pressure 3/30/84 (Unit 1)
! None b. Instrumentation Cable (see Item 4.b)
.c. Electrical Penetration Splices (see Item 4.c)
None 3 None d. Electrical Penetration Assembly (see (item 4.d)
- 10. 1&2-TE None a. Conax Thermocouples (T/C) - Reactor Vessel Level 3/30/84 (Unit 1) 11/1/84(3) 499 thru Indicating System Reference Leg Temperature 11/1/84 (Unit 2) 502, 506 None b. T/C-to-Cable Splices (see Item 4.c) i i- thru 509 None c. T/C Extension Cable - Anaconda Type K T/C Exten-
- and 1-TE sion Twisted, Shielded Pair
! 503 & 510 None d. Electrical Penetration Splices (see Item 4.c) ,
j None e. Electrical Penetration Assembly (see Item 4.d) j 11. 1&2-TE1 31 a. Control Products Corp. Thermocouples (T/Cs) !
11/1/84 (Unit 2) 11/1/84(3)
! thru 39 Incore (Core Exit) Thermocouples 3/30/84 (Unit 1) ,
t 47 b. Veam Division of Litton T/C Connectors t
! 37 c. Instrumentation Cable (see Item 10.c)
} None d. Electrical Penetration Splices (see . Item 4.c) I l None e. Electrical Penetration Assembly (see Item 4.d) l l 12. 1&2-TE 32 (Unit 1) a. Conax Resistance Temperature Detectors (RTDs)- 3/30/84 (Unit 1)* 11/1/84(1)(3)
- 450A-D & 32 and 69 Reactor Coolant System Hot & Cold Leg Loop Temp. 11/1/84 (Unit 2)* t
! 451A-D (Unit 2) b. RTD-to-Cable Splices (see Item 4.c) l c. Instrumentation Cable - Anaconda, Rockbestos, i or Brand Rex Twisted, Shielded Triple
- c. Electrical Penetration Splices (see Item 4.c)
~
I O
- e. Electrical Penetration Assembly (see Item 4.d) . !
One element of each dual element RTD will be operational through existing cables and instrumentation racks by 12/10/82 l
(Unit 1) and 6/30/83 (Unit 2). i
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT -
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: V. Reactor Coolant Page: V-4 Date: October 10, 1983 Expected Expected or Actual Environmental Item PBNP NRC Installation /
Ns. Tag No. TER No. Description Qualification Operation Date Documentation Date
- 13. 1&2-PCV434 None a. Crosby Lift Indicating Switch Assemblies -
& 435 11/1/84 (Unit 2) 5/24/85(5)
Reactor Coolant System Pressurizer Code Safety 5/24/85 (Unit 1)
Valves
- b. Switch Assembly Pigtail-to-Cable Splices (see Item 4.c)
- c. Control Cable - Anaconda, Rockbestos, or Brand Rex 600 Volt Control
- d. Electrical Penetration Splices (see Item 4.c)
- e. Electrical Penetration Assembly (see Item 4.d) n a
i J
MASTERLISTOFELECTRICALEQUIPMENTIMPORTANy O -
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED
~
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 '
. J t' System: VI. Chemical-& Volume Control d 'o 'Page: -VI-1 .
,L Date: October 10, 1983, s . Expected v Expected or~ Actual Environmental
-Item' 'PBNP NRC b Installation / Qdalification N s. Tag No. TER No. Description '
Operation Date- Documentation Date
- 1. 1&2-CV1296 22 a.-ASCO Solenoid Valves - Auxiliary Charging 12/10/82 (Unit 1) 6/30/83 ~
Line Isolation Valve Air Operators 6/30/83 (Unit 2) x 60- b: NAMCO Limit Switches - Valve Position Indication- '
None c. Consx Electrical Conductor Seal Assemblies (ECSA's) s for NAMCO Limit Switches None d. ECSA-to-Cable Splices - Raychem Type WCSF-N 43 e. Control- Cable - Kerite 600 Volt ~ Control i 36 f. Electrical Penetration Splices - Bechtel Dwg. -
- x, 1 No. SK-E-165/Raychem Type SFR -,
- g. Electrical Penetration Assembly - Westinghouse /
j 35 -
Crouse Hinds Welded Canister Penetration
- 2. 1&2CV313A None a. ASCO Solenoid Valves - Reactor Coolant Pump 6/30/83 (Unit 2) '-
6/30/83 (Unit 2) j 1
Seal Water (Return Line Isolation Valve Air Operators 3/30/84 (Unit 1) '. 3/30/84 (Unit 1) 2 None b. NAMCO Limit Switches (see Item 1.b)
None. c. Conax ECSA (see Item-1.c)
None d. ECSA-to-Cable Splices (see Item 1.d) ~
None e. Control Cables - Anaconda,.Rockbestos, or Brand '
Rex 600 Volt Control None f. Electrical Penetration Sp1 ices-(see Item 1.d)
None g. Electrical Penetration Assembly - Westinghouse a Modular Penetration
- 3. 1&2-CV371A None a. ASCO Solenoid Valves - Reactor Coolant Letdown 6/30/83 (Unit 2) 6/30/83 (Unit 2)
Line Isolation. Valve Air Operators 3/30/84 (Unit 1) 3/30/84 (Unit 1)
None b. NAMC0 Limit Switches (see. Item 1.b) l None c. Conax ECSA (see Item 1.c)
! None d. ECSA-to-Cable Splices (see Item 1.d)
None e. Control Cables - (see Item 2.e)
None f. Electrical Penetration Splices (see Item 1.d)
- None g. Electrical Penetration Assembly - Westinghouse j Modular Penetration i
I i
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: VI. Chemical & Volume Control Page: VI-2 Date: October 10, 1983 Expected Expected or Actual Environmental Itta PBNP NRC Installation / Qualification N 3. Tag No. TER No. Description Operation Date Documentation Date
- 4. 1&2-LT106, 12 a. Foxboro Differential Pressure Transmitters - 6/30/83 (Unit 2) 3/30/84(1) 172, & 190 Boric Acid Storage Tank Water Level 3/30/84 (Unit 1)
LT102, 171, None b. Cable Splices - Raychem Type WCSF-N
& 189 40 c. Instrumentation Cable - Boston Insulated Wire
& Cable Co. Bostrad 7 Twisted, Shielded Pair or Okonite PVC-Insulated and Jacketed Twisted, Sheilded Pair (2-LT106 & 190) i
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: VII. Heating & Ventilation Page: VII-1 Date: October 10, 1983 Expected Expected or Actual Environmental ItGm PBNP NRC Installation / Qualification No. . Tag No. .TER No. Description Operation Date Documentation Date i
- 1. 1&2-W1A1 28 a. Westinghouse Motors - Containment Air Recircu- Original Equipment 6/30/83(2)
B1, C1, & lation Emergency Cooling Fans
.D1 29 b. Motor-to-Lead Splices - Westinghouse Drawing l No. 206C391 l 43 c. Power. Cable - Kerite 600 Volt Power i 53 d. Motor and Fan Bearing Lubricant - Chevron Style 1 SRI Grease None e. Fan Bearing Housing Labyrinth Seal Lubricant -
- Westinghouse Style No. M-53701TT (E. I. Dupont de Nemours & Co., Inc. Krytox 240 AC Florinated)
Grease 36 f. Electrical Penetration Splices - Raychem Type WCSF-N 35 g. Electrical Penetration Assembly - Westinghouse /
1 Crouse Hinds Welded Canister or Westinghouse Modular Penetration 1
j 2. 1&2-HV 20 a. ASCO Solenoid Valves - Containment Purge Supply 12/10/82 (Unit 1) 6/30/83 3213 & .and Exhaust Line Isolation Valve Air Operators 6/30/83 (Unit 2)
! 3245 60 b. NAMCO Limit Switches - Valve Position Indication
- c. Conax Electrical Conductor Seal Assembly (ECSA)
None for NAMCO Limit Switches None d. ECSA-to-Cable Splices - Raychem Type WCSF-N 43 e. Control Cables - Kerite 600 Volt Control 36 f. Electrical Penetration Splices - Bechtel Dwg.
i No.SK-E-165/Raychem Type SFR 35 g. Electrical' Penetration Assembly - Westinghouse /
Crouse Hinds Welded Canister Penetration
,' 3. 1&2-HV 21 a. ASCO Solenoid Valves - Containment Atmosphere 12/10/82 (Unit 1) 6/30/83 j 3200C Sampling Line Isolation Valve Operators 6/30/83 (Unit 2) 60 b. NAMCO Limit Switches - Valve Position Indication None c. Conax Electrical Conductor Seal Assembly (ECSA) for NAMCO Limit Switches l
s l
_ ~
I
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MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT -
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: VII. Heating & Ventilation Page: VII-2
, Date: October 10, 1983 Expected Expected or Actual Environmental It:0 PBNP Tag No.
NRC Installation / Qualification
- No. TER No. Description Operation Date Documentation Date None d. ECSA-to-Cable Splices (see Item 2.d) 39 e Control Cables - Kerite 600 Volt Control 36 f. Electrical Penetration Splices (see Item 2.f)
. 35 g. Electrical Penetration Assembly (see Item 2.g) 4 T
l
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT -
TO SAFETY T0.BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: VIII. Main & Reheat Steam Page: VIII-1 Date: October 10, 1983 Expected
' Expected or Actual Environmental Ittm PBNP NRC Installation / Qualification N o. Tag No. TER No. Description Operation Date Docunentation Date
- 1. 1&2-MS 65 a. Limitorque Valve Motor Operator - Steam Supply Original Equipment 6/30/83(2) 2019 & to Turbine - Driven Auxiliary Feedwater Pump 2020 Isolation Valves 43 b. Power Cables - Kerite 600 Volt Power 39 c. Control Cables - Rome 600 Volt Control i None c. Motor-to-Lead Splices - Scotch #70 Silicon Rubber Tape Insulation with Vinyl Tape Overall or Equivalent q 54 e. Main Gear Case Lubricant - American Oil Co.
Amolith #1 EP or AMDEX #2 EP Greases 56 f. Geared Limit Switch Assembly Lubricant-Mobil
- Oil Co. No. 28 Grease 4
- 2. 1&2-FT 15 a. Foxboro Differential Pressure Transmitters - 12/10/82 (Unit 1) 3/30/84(1) 464, 465, Main Steam Line Flow 6/30/83 (Unit 2) 474, & 475 42 b. Instrumentation Cable - Okonite, Okotherm-Insulated, Okoseal-Jacketed Twisted, Shielded Pair 36 c. Electrical Penetration Splices - Bechtel Dwg.
No. SK-E-165/Raychem Type SFR 35 d. Electrical Penetration Assembly - Westinghouse /
Crouse Hinds Welded Canister Penetration j 3. 1&2PT 16 a. Foxboro Pressure Transmitter - Main Steam Line 12/10/82 (Unit 1) 3/30/84(1) 468, 469, (Steam Generator) Pressure 6/30/83 (Unit 2) 482, 478, 42 b. Instrumentation Cable - Same as Item 2.b or Okonite PVC-Insulated and Jacketed Twisted, Shielded Pair (2-PT478, 479, & 483) 479, & 483 None c. Additional Instrumentation Cable - Anaconda, l Rockbestos, or Brand Rex Twisted, Shielded Pair None d. Cable-to-Cable Splices - Raychem Type WCSF-N i
1
-~, _ _ _ _ _ _ _ _ _ _ . _ . _ _ _
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT -
T0 SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: IX. Main Feedwater Page: IX-1 Date: October 10, 1983 Expected Expected or Actual Environmental It m PBNP NRC Installation /
N 3. Tag No. TER No. Description Qualification Operation Date Documentation Date
- 1. 1&2-CV None a. ASCO Solenoid Valves - Main Feedwater Regu- 3/30/84 (Unit 1) 11/1/84(4) 466 & 476 lating Valve Air Operator Trip on Safety 11/1/84 (Unit 2)
Injection None b. NAMCO Limit Switches - Valve Position Indication None c. Conax Electrical Conductor Seal Assemblies (ECSAS) for NAMCO Limit Switches None d. ECSA-to-Cable Splices - Raychem Type WCSF-N 39 e. Control Cable -Rome 600 Volt Control
- 2. 1&2-CV 480 None a. ASCO Solenoid Valves - Main Feedwater Regu- 3/30/84 (Unit 1) 11/1/84(4)
& 481 lating Bypass Valve Air Operator Trip on Safety 11/1/84 (Unit 2)
Injection None b. NAMC0 Limit Switches (see Item 1.b)
None c. Conax ECSA (see Item 1.c)
None d. ECSA-to-Cable Splices (see. Item 1.d) 39 e. Control Cable (see Item 1.e)
- 3. 1&2-LT461, 14 a. Foxboro Differential Pressure Transmitters - 12/10/82 (Unit 1) 3/30/84(1) 462, 463, Steam Generator Narrow-Range Water Level 6/30/83 (Unit 2) 471, 472, & 42 b. Instrumentation Cable - Okonite Okotherm-473 Insulated, Okoseal-Jacketed Twisted, Shielded Pair 36 c. Electrical Penetration Splices - Bechtel Dwg.
No. SK-E-165/Raychem Type SFR 35 d. Electrical Penetration Assembly - Westinghouse /
Crouse Hinds Welded Canister Penetration
- 4. 1&2- LT 14 a. Foxboro Differential Pressure Transmitter - 12/10/82 (Unit 1 - 3/30/84(1)(3) 460A&B, Steam Generator Wide-Range Water Level one temporary channel) 470A&B None b. Instrumentation Cable - Anaconda, Rockbestos, 3/30/84 (Unit 1 -
or Brand Rex Twisted, Shielded Pair final configuration)
None c. Electrical Penetration Splices - Raychem Type 6/30/83 (Unit 2 -
WCSF-N one temporary channel)
None d. Electrical Penetration Assembly - Westinghouse 11/1/84 (Unit 2 -
Modular Penetration final configuration)
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT -
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: X. Electrical Page: X-1 Date: October 10, 1983 i
Expected Expected or Actual Environmental Item PBNP NRC Installation /
l No. Tag No. TER No. Description Qualification Operation Date Documentation Date
- 1. 1&2-B32 43 a. Power Cables to Safeguards Motor Control Original Equipment 6/30/83
& 42 Center - Kerite 600 Volt Power 39 b. Control Cables to Safeguards Motor Control Centers - Rome 600 Volt Control
'i i
a 3
1 l
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT TO SAFEIY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
, System: XI. Containment Page: XI-1 Date: October 10, 1983 Expected Expected or Actual Environmental Item PBNP NRC Installation / Qualification No. Tag No. TER No. Description Operation Date Documentation Date
- 1. 1&2-PT 9 a. Foxboro Pressure Transmitters - Containment 12/10/82 (Unit 1) 3/30/84(1) 945 thru Narrow-Range and Intermediate-Range Pressure 6/30/83 (Unit 2) 950 40 b. Instrumentation Cable - Boston Insulated Wire
& Cable Co. Bostrad 7 Twisted, Shielded Pair
- 2. 1&2-PT968 None a. Foxboro Pressure Transmitters - Containment 6/30/83 (Unit 2) 3/30/84(3)
& 969 Wide- Range Pressure 3/30/84 (Unit 1)
None b. Instrumentation Cable - Anaconda, Rockbestos, or Brand Rex Twisted, Shielded Pair
- 3. 1&2-HA969 None a. Exo-Sensor Hydrogen Analyzers - Containment 6/30/83 (Unit 2) 11/1/84(3) thru 967 Hydrogen Concentration 3/30/84 (Unit 1)
None b. Instrumentation Cable (see Item 2.b or Equivalent)
None c. Electrical Penetration Splices - Raychem Type WCSF-N None d. Electrical Penetration Assembly - Westinghouse Modular Penetrations
- 4. 1&2-TE3292 None a. Conax Resistance Temperature Detectors (RTDs) - 3/30/84 (Unit 1) 11/1/84(3)
& 3293 Containment Atmosphere Temperature 11/1/84 (Unit 2)
None b. RTD-to-Cable Splices - Raychem Type WCSF-N None c. Instrumentation Cable - Anaconda, Rockbestos, or Brand Rex Twisted, Shielded Triple None d. Electrical Penetration Splices - Raychem Type WCSF-N None e. Electrical Penetration Assembly - Westinghouse Modular Penetrations
- 5. 1&2-TE3294 None a. Conax Resistance Temperature Detectors (RTDs) - 3/30/84 (Unit 1) 11/1/84(3)
& 3295 Containment Sump B Water Temperature 11/1/84 (Unit 2)
None b. RTD-to-Cable Splices (see item 4.b)
None c. Instrumentation Cable (see Item 4.c)
None d. Electrical Penetration Splices (see Item 4.d)
None e. Electrical Penetration Assembly (see Item 4.e)
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: XI. Containment Page: XI-2 Date: October 10, 1983 Expected Expected or Actual Environmental Itga PBNP NRC Installation /
No. Tag No.
Qualification TER No. Description Operation Date Documentation Date
- 6. 1&2-RE126, None a. General Atomic Radiation Monitor - Containment 3/30/84 (Unit 1) 11/1/64(3) 127, & 128 High-Range Gamma Radiation 11/1/84 (Unit 2)
None b. Monitor-to-Cable Splices - Amphenol Coaxial Connectors /Raychem Type WCSF-N None c. Instrumentation Cable - Rockbestos Coaxial None d. Electrical Penetration Splices - Amphenol Coaxial Connectors /Raychem Type WCSF-N None e. Electrical Penetration Assembly - Westinghouse Modular Penetration
- 7. 1&2-LT958 None a. Gems Delaval Level Transmitters - Containment 6/30/83 (Unit 2) 3/30/84(3)
& 959 Sump A Water Level 3/30/84 (Unit 1)
None b. Conax Electrical Conductor Seal Assemblies (ECSAs) for Transmitter None c. ECSA-to-Cable Splices - Raychem Type WCSF-N None d. Instrumentation Cable (see Item 4.c)
None e. Electrical Penetration Splices - Raychem Type WCSF-N None f. Electrical Penetration Assembly - Westinghouse Modular Penetrations
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT ;
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED s
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
, System: XII. Sampling Page: XII-1 1
Date: October 10, 1983 Expected Expected or Actual Environmental Ittm PBNP NRC Installation / Qualification i No. Tag No. .TER No. Description Operation Date Documentation Date
, - 1. 1&2-SV951, 23 a. ASCO Solenoid Valves - Pressurizer Steam Space, 12/10/82 (Unit 1) 6/30/33
- 953, & 955 Pressurizer Liquid Space, and Reactor Coolant 6/30/83 (Unit 2)
Hot Leg Sample Line Isolation Valve Air Operators 59 b. NAMCO Limit Switches - Valve Position Indication
- None c. Conax Electrical. Conductor Seal Assemblies (ECSAs) for NAMCO Limit Switches -
None d..ECSA-to-Cable Splices - Raychem Type WCSF-N 43 e. Control Cable - Kerite 600 Volt Control j 36 f. Electrical Penetration Splices - Bechtel Dwg.
, No. SK-E-165/Raychem Type SFR-
! 35 g. Electrical Penetration Assembly - Westinghouse /
Crouse Hinds Welded Canister Penetration
- 2. .1&2-SV966C 18 a. ASCO Solenoid Valves - Reactor Coolant Hot Leg 12/10/82 (Unit 1) 6/30/83(3) i Sample Line Isolation Valve Air Operators 6/30/83 (Unit 2) 57 b. NAMCO Limit Switches - Valve Position Indication
! None c. Conax Electrical Conductor Seal Assemblies (ECSAs)
I for NAMCO Limit Switches None d. ECSA-to-Cable Splices - Raychem Typw WCSF-N
. 39 e. Control Cable - Rome 600 Volt Control
- 3. 1&2-SV959 None a. ASCO Solenoid Valves - Residual Heat Removal 3/30/84 (Unit 1) 11/1/84(3)
, Heat Exchanger Outlet Sample Line Isolation 11/1/84 (Unit 2) ;
i Valve Air Operators None b. NAMCO Limit Switches - Valve Position Indication None c. Conax ECSAs (see Item 2.b)
None d. ECSA-to-Cable Splices - Raychem Type WCSF-N ,
39 e. Control Cable - Rome 600 Volt Control i
4 t
1
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: XIII. Instrument Air Page: XIII-1 Date: October 10,.1983 i
Expected Expected or Actual Environmental Itca PBNP NRC Installation / Qualification Na. Tag No. TER No. Description Operation Date Documentation Date
- 1. 1&2-IA3647 lbne a. ASCO Solenoid Valves - Instrument Air to 3/30/84 (Unit 1)' 11/1/84(3)
& 3048 Containment Line Isolation Valve Air Operators 11/1/84 (Unit 2)
None b. NAMCO Limit Switches - Valve Position Indication None c. Conax Electrical Conductor Seal Assemblies (ECSAs) for NAMCO Limit Switches
, None d. ECSA-to-Cable Splices - Raychem Type WCSF-N j 39 e. Control Cable'- Rome 600 Volt Control 1
4 i
4 4
1 1
MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT .
TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 System: XIV. Steam Generator Blowdown Page: XIV-1 Date: October 10, 1983 Expected Expected or Actual Environmental Item PBNP NRC Installation /
No. Tag No. TER No. Description Qualification Operation Date Documentation Date
- 1. 1&2-CV5958 None a. ASCO Solenoid Valves - Steam Generator 12/10/82 (Unit) 6/30/83
& 5959 Blowdown Line Isolation Valve Air Operators 6/30/83 (Unit 2)
None b. NAMCO Limit Switches - Valve Position Indication None c. Conax Electrical Conductor Seal Assemblies (ECSAs) for NAMCO Limit Switches
! None d. ECSA-to-Cable Splices - Raychem Type WCSF-N None e. Control Cable - Anaconda, Rockbestos, or Brand Rex 600 Volt Control
, None f. Electrical Penetration Splices - Raychem Type WCSF-N None g. Electrical Penetration Assembly - Westinghouse Modular Penetration
)
i i
4