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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
[Table view] |
Text
..
O Wisconsin Electnc ecua courasr 23I W MICH! GAM. P.O. BOX 2046, MILWAUKEE. WI 53231 March 2, 1981 0 %
Mr. Harold R. Denton, Director 7g 4 Office of Nuclear Reactor Rerfulation v gr U. S. NUCLEAR REGULATORY COMMISSION 74
.u
- Washington, D. C. 20555 W ,, [ " L1 Attention: Mr. R. L. Clark, Chief 5 ..
Operating Reactors Branch 3 '[
f 6$'
Sp
'M- C ,'
Gentlemen:
DOCKET NOS. 50-266 AND 50-301 FIRE PROTECTION SAFETY EVALUATION REPORT SUPPLEMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 The following comments an . formation are provided in c
response to the Fire Protection 4 Evaluation Report (SER) supplement for Point Beach Nucle.. Plant, Units 1 and 2, which was transmitted with your letter dated October 21, 1980, and Enclosures 1, 2, and 3 which were transmitted with your letter dated January 22, 1981. These documents identify ten open items for which additional information has been requested (SER Section 3.1) and four unresolved items (SER Section 3.2).
The supplement states that modifications for some items should be made in accordance with particular sections of Appendix R to 10 CFR Part 50. We consider it inappropriate to require simple compliance with a particular rule statement without consideration of plant specific conditions or fire protective provisions. This requirement negates considerable design effort by the licensee and review effort by the NRC Staff without demonstrating that increased plant safety will be achieved.
Nevertheless, we re-evaluated the subject modifications in light of the requirements of Appendix R.
The following is our evaluation of each of the open and unresolved items. Available design information is enclosed for your review.
05 3.1.5 Water Damage Protection g Floor drains will be provided in the cable spreading room. The licensee's proposal to install floor drains in the cable spreading room was based upon our assumption that /[
8103 090 gq g 7
Mr. Harold R. Denton March 2, 1981 installation of a fixed water suppression system would provide acceptable fire protection for the room.
The cable spreading room sprinkler system design was submitted with our June 23, 1980 letter. Evaluations of Section 3.1.4, Fixed Water Suppression Systems, and Section 3.2.1, Safe Shutdown Capability, in the supplement do not mention water protection in the cable spreading room. ,
t The size of a floor drain system in the cable spreading room is dependent upon the need for, size, and type of fire suppression system to be provided. The suitability of a fire ,
suppression system plus other protective features of the cable spreading room to provide acceptable fire protection should be resolved before the floor drain design is finalized. With the !
expectation that floor drains will be required to accommodate manual fire fighting activities, and in order to expedite imple-mentation of fire protection modifications, we will continue our engineering effort for this item. Preliminary floor drain design information is contained in the enclosed Attachment A.
3.1.9 Fire Barriers Licensee will perform the modifications specified in the supplement. The modification actions listed in the supplement t are in accordance with the licensee's proposed action as listed in the SER. Penetration seal design information which was furnished with our October 13, 1980 letter has been accepted by your January 22 letter. Additional design information for Itea 3 of this modification is contained in the enclosed Attachment B.
3.1.14 Cable Separation SER Item 3.1.14 dealt only with " cable or co'nduit that interconnects redundant safety-related cable trays". However, in the supplement, this item has been expanded to be synonymous with Item 3.2.1, which deals more generally with safe shutdown capability. With respect to the original SER Item 3.1.14, the
! cable or conduit interconnects have been identified. Fire stops and conduit seals to remove the combustible pathway are being installed as part of the ongoing penetration seal modification.
Seal design information which was furnished with our October 13 letter has been accepted by your January 22 letter. Cables routed in common conduits or junction boxes will be relocated to
- eliminate the interconnect.
3.1.15 Ventilation System Control Cables This item was not identified as an open item in either the SER or the supplement. However, the Staff stated in l
l l
, - _ , _ _ - ~ _ _ _ _ _
i , t 1
- i i !
[ Mr. Harold R. Denton March 2, 1981 Enclosure 2 to the January 22 letter that licensee should either l l show compliance with Section III.G of Appendix R or verify that I
! there is no effect on safe shutdown capability, j
$ t We have reviewed the location, routing, and operation ;
- function of the subject. cables. Each air supply opening to the (
! diesel room ventilation fans is provided with a manually actuated ;
fire damper for the purpose of containing a potential diesel 7 1 generator room fire within the affected room. The subject cables ;
i begin at the fire damper closure switches and energize relays l which open normally closed contacts in each ventilating fan circuit to prevent fan operation when the dampers are closed. j A complete loss of cable function in a fire event would leave the ;
relay de-energized and ventilation fan operability unimpaired. l Therefore, the loss of these cables due to a fire would have no ,
effect on safe shutdown capability following the fire, and ;
protective action in accordance with Section III.G of Appendix R [
is not required. j 3.1.17 Hydrogen Hazard Fire Protection ,
i*
This item will be considered as part of Item 3.2.1 below.
t 3.1.24 Diesel Generator Air Intake Structure [
l Rather than provide an alternate intake structure as [
! originally proposed, licensee will permanently reverse the ;
i ventilation flow through the diesel rooms. Since the existing :
intake structures will then become the exhaust structures, the fire rated enclosures discussed in the supplement will not be
- necessary. Design information for this modification is contained i in the enclosed Attachment C. l s 1 I Auxiliary Building Cable Tray Penetration Seals 3.1.26 3.1.27 Containment Building Fire Stops 3.1.28 Service Building Penetration Seals The seals and fire stops required in these items will
be installed. Seal design information was furnished with licensee's :
October 13 letter and accepted in Enclosure 1 of your January 22 ;
l letter. !
3.1.32 Fire Hydrant Inspections _
r The licensce submitted an administrative procedure for annual fire hydrant inspections based upon equipment history.
On this basis we continue to consider annual fire hydrant inspections to be adequate. In addition, the monthly fire protection equipment surveillance procedure has been expanded to
- I P
_ _ _ __ ____. - __ _ . _ _ . . _ _ _ _ . _. . . _ _ - ~ _ , _ . - - _ . _ _. .-. , . _ ,
- . - . . - - ._ ~ _ _ - -. -- .- . ___
i
~
i I
t Mr. Harold R. Denton March ., 1981 ;
f 4 include fire hydrant inspections for accessibility and condition. !
We consider the degree of performed inspections to meet all NFPA !
requirements. The monthly surveillance procedure is contained !
in the enclosed Attachment D.
3.1.33 Control Room Light Fixtures t
This item seems to have been erroneously listed as a l requirement in Enclosure 3 to your January 22 letter. The ;
- proposed modification was stated to be acceptable in the SER i
~
supplement. The modification has been completed. ;
t 3.2.1 Safe Shutdown Capability The licensee's December 29, 1978 letter referenced in .
the supplement provided an evaluation of the plant specific l capability to achieve and maintain shutdown for postulated fires l in various plant areas. This. evaluation was based on quantified i postulated fires and proposed modifications which were considered :
adequate to satisfy the conditions of Branch Technical Position ,
9.5-1. We have not been apprised of any specific deficiencies of fire protection features determined during your evaluation or y the technical basis for your conclusions in the supplement. j i
The supplement states that, to meet Section III.G of the proposed Appendix R to 10 CFR Part 50, the licensee should provide an alternate shutdown capability for the following areas of the plant:
- 1. Cable spreading room -
- 2. Switchgear room
- 3. Control room
- 4. Auxiliary feedwater pump area ,
- 5. Auxiliary building El. 8 ft., 26 ft., and 46 ft.
and above ;
- 6. Containment
- 7. Containment facades However, Section 50.48(b) of the rule in its effective form requires the licensee to reassess those areas of the facility to determine whether the requirements of Section III.G.2 of Appendix R are satisfied. If they are not, the licensee may either provide the alternative shutdown capability in accordance with Section III.G.3 or request an exemption. Licensee is currently undertaking this evaluation. -
3.2.2 Circulating Water Pumphouse Fire Protection The supplement statements indicate that some misunder-l standing exists regarding configuration of the circulating water '
pumphouse. The resolutions and blanket imposition of the l t 1
I I
Mr. Harold R. Denton March 2, 1981 j requirements of Section III.G of Appendix R to 10 CFR Part 50 i do not accurately address the pumphouse configuration or the [
specific concerns stated in the SER.
l i A more complete description of the circulating water pumphouse configuration is contained in the enclosed Attachment [
l E. We believe that this infor,ation satisfactorily addresses I
) the concerns stated in the SER.
i 3.2.4 Fire Brigade Training Frequency i Licensee's fire protection training program will be f modified to include annual practice sessions for each fire l brigade member. However, we feel strongly that overall fire protection will be more effective if the shift supervisor may be a member of the fire brigade.
(
i i
- 3.2.6 Reactor Coolant Pump Lube Oil Collection
, Existing and proposed coolant pump oil collection
] systems are undergoing evaluation to determine compliance with :
Section III.O of Appendix R. ;
1 j Very truly yours, [
f I,
C. W. Fay, Director ,
Nuclear Power Department i
Attachments l Copy to NRC Resident Inspector , I i
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I i i I
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- ,-- _-- -, .- _ , ,e - - - , , , ,, _ , -
?, ., ATTACHMENT A
. . CABLE SPREADING ROOM FLOOR DRAINS DATE February 17, 1981 ,
PAGE 1 l LJ LJ
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8' Room Soze L = 78.Sf T W s 'l7 3 FT A = 3715 FT
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- I'i I N 2*?? IN' e 9 G O L, //J.
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%TTACHMENT A ;
. CABLE SPREADING ROOM FLOOR DRAINS DATE February 17, 1981 PAGE 2 i
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d ra o n c os t r y .
r-
ATTACHMENT A CABLE SPREADING ROOM '
FLOOR DRAINS DATE February 17. 1981 '
PAGE 3 ;
I 4 " Dra on s to o'Ch 4 " dra in loeader is aclef vate with 4 a de r .2..s* H :
s e low dra in en t r y . I A Ca ta l & s n . de'a . dea r:. S ys Tem is pe c ora,,reahd.
. Hose Ds's c h a rg e i
I se. hose (fow Vute = :O qf m l'/2 in. host flow rate : 100 p m -
Drass s sjt Te m .1 s n'g e d for t s or9por< cred is E/ere(ore erk uaTe.
e e
- ATTACHMENT A .
a .
CABLE SPREADING ROOM FLOOR DRAINS DATE February 17, 1981 4 l PAGE
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0 February 17, 1981 ATTACHitENT B AUXILIARY BUILDItiG VENTILATION EXHAUST FILTER ROOM ROLLING FIRE DOOR AND CONTROL ROOM VIEWIrlG WIrlDOW GUILLOTINE FIRE DAMPER 6
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-[ 10 GA STEEL IVI6"DIA. HOLE SPECFICATIONS
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FACE VIEW
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REQ'Q A B FAras CUSTOMER REVISION 1 DATE[BY E! \ \ HI 23V.2 f, yy 3l3/j " 1 rJ w. w , w m
- CUSTOMER ORDER NQ /]t. . . . I md vmb!ct.nq ine
AGENTS ORDER NO.
JOB GULLOTINE FIRE DAMPER DAF-P-2216 1 ~ onL MTE * *TWL *~* * **1 m .ce DAF-D-2216 E 1
~~' ~ ~ _
February 26,~1981 ~ ~ ~ ~ ' ]
Page 1 of 3 i I
ATTACHMENT C l t DIESEL GENERATOR ROOM !
! AIR SUPPLY j
. i i
Section 5.1.5 of the Safety Evaluation Report expressed concern that smoke t r
- from a turbine lube oil reservoir fire could be drawn into the diesel l
generator combustion air intakes and prevent diesel generator startup.
i
! Item 3.1.24 of the Safety Evaluation Report is a licensee proposed modifi- ;
! cation consisting of a two-hour fire rated enclosure around the existing :
air intake structures with smoke dampers and ducting so that an outdoor !
i fresh air supply could be provided to the diesel generator rooms in the l l event of a lube oil fire. -
2 i A structure and associated ductwork was designed. It was found that an !
! adequate structure could not be located in a manner suitable for unimpeded [
plant operations and maintenance activities. The location of the proposed ;
outdoor air supply would be within 30 feet of the existing diesel generator !
room exhaust. This suggested investigation of permanently reversing venti-lation flow through the diesel generator rooms. Such a modification would !
always provide a fresh air supply to the diesel generators without instal- .
lation of space consuming ductwork. ;
Consultation with the diesel generator manufacturer verified that ventila- i tion air flow direction should not affect diesel operation. The diesel is !
designed to operate with room static pressure within + 3 in, of H O2 of _
a atmospheric pressure. Diesels are normally installed with the generator :
j facing the room air inlet. Because the Point Beach installation would be '
l opposite of normal, the adequacy of generator cooling required verification.
4 Consultation with the ventilation fan cunufacturer verified that reversed i flow could be accomplished with a potential for decreased air flow and fan ;
vibration. j Based on the above consultation, a field verification test was conducted.
. Gravity operated room inlet and discharge louvers were reversed. Ventila-tion fan blades and motor leads were reversed. The diesel generator was >
operated at rated continuous operating load and the following items were evaluated.
- 1. Room Static Pressure The diesel room static pressure was measured with just the diesel i
running and with both the diesel and ventilation fan running. No deviation from atmospheric oressure was detected. Room access doors were readily operated. All louvers operated satisfactorily. .
- 2. Generator Discharge Temperature '
Flow rates were measured and heat loads calculated for the test f condition. This data was used with the Su.mer ambient design temper-ature to calculate and worst case generator discharge temperature.
, _ . . _ ~ _ -
t i
Page 2 of 3 i i The worst case generator discharge temperature was found to be below i the design specification temocrature and generator cooling is veri-fied to be adequate. ;
- 3. Ventilation Fan Flow _ f:
Irdtial test measurements indicated a fan flow rate of about 70,100 cfm L
. which is higher than the initial design flow rate of 50,000 cfm. Some !
reduction in flow rate was desired because~approximately 10,000 cfm i combustion air would not flow through the fan. The pitch of the fan !
blades was adjusted and a flow rate of approximately 42,000 cfm was l l measured. This is considered to be an appropriate flow rate for re- F versed flow operation. -
- 4. Fan Vibration
'l No significant fan vibration was noted. However, some vibration of I
! the fan discharge louvers was noted which appeared to be a result of f
- pressure pulsations generated by the fan. The vibration was not of ;
- sufficient amplitude to warrant corrective action. !
l 5. Personnel Hazard at Discharge Enclosure ,
! i i Air velocity measurements were taken at several locations around the !
discharge enclosure. The discharge louvers provide suitable deflec-l tion towards the floor. Waist height air velocity was very low at a !
distance of three feet from the enclosure. Installation of deflectors i is not considered necessary. ,
4
- 6. Potential Freezing .
Service water and fire protection piping should be protected from l freezing during diesel operation and while the diesel is idle. -
- Continuous service water system flow exists during diesel operation. (
- Service water temperature was monitored during the test with the ;
ventilation fan in continuous operation and no deviation was noted. l Fire protection piping is installed near the ceiling which will be 1 warmed by heat rising from the diesel. Ventilation fan operation is j
- thermostatically controlled. The lowest fan actuation setting is 900F !
i and the lowest fan cutoff setting is 700F. Should ventilation fan !
operation be initiated, it will be terminated before room temperature I approaches freezing. There is no apparent potential for freezing j during diesel operation, j l During the Winter season, room air heaters maintain diesel room temper- t i ature at 650 F while the diesel is idle. Turbine hall roof exhausters !
I could induce air leakage through the gravity operated dampers of the 1 diesel room. If such leakage were to exceed room air heater capacity,
! room temperature could decrease to the point of freezing. Counter- ;
j weights on the gravity inlet louvers were adjusted to hold the louvers 2
closed with the diesel and ventilation fan idle prior to the field i verification test. An air flow rate approximately equal to the room air heater capacity was measured at the redundant ventilation fan during l
l l
l w
Page 3 of 3 the test. The room air heating fan was shut off following the test and flow through the ventilation fan was not of measurable quantity.
Therefore, air inleakage is negligible and no apparent freezing problem exists. Tr.e diesel room ambient conditions are being carefully watched during the current Winter season.
We have concluded, following our design efforts, that installation of an air inlet enclosure and ducting is not a practical method of enhancing fire protection safety at Point Beach ike. lear Plant. We hereby propose an alternate modification which consists of permanently reversing the ventila-tion flow through the diesel generator rooms. Tnis modification, which has been verification tested in accordance with the above description, will provide a fresh air supply to the diesel generators.
t We
ATTACHMENT D February 26, 1981 2 ,
DATE ~ ~ ~ ,75-14 DSS !!AJOR FPS -
Revision 0 11-20-80 POIfff BEAC!! NUCLE &It PLAllT TEC1'HICAL SPECIFICATI0!! SURVEIT LANCE TESTIllG
!!O!!TiiLY FIRE EQUIP::EIIT SURVEILLA!!CE OUTSIDF ,;l:EAS, MAI!JTEtJ?d:CE A!!D POI; TABLE WELDItlG CARTS
. CAUTIOli
, OPERADILITY 01: Tile DOUELE STARTTED ITEl:S OF Ti!IS PROCEDURE Al'E A TECl!!!! CAL SPECIFICATIO!! REQUILEl:EliT. IF Tl:ERE ARE AIT/ PROCLEMS TELT0H::ll:G T!!EEE STEl'S, !ICTIFY TiiE DUIY SHIFT SUPERVISOR I!':EDIATELT.
J 17 - 204 Cartridges fl'.eded CONDITIC!!S Hord:AL 9 - 5tt Cartridg..: ::eeded II:ITIALS
- 1. Fi!-22, south. rest hose station inventory
- a. 6 lengthe of ?!;" hose
- b. 3 lengths of l'," hce.e
- c. 2 gate valves en hydrant sht.t
- d. 1 2\" r.or:le
- e. 2 Ib" no le:. _
- f. I gated vye
- g. 1 fire a::e _
- h. I wrecking bcr
- i. 4 cpanner wrcnches
- j. I hydrant wrcr ch
- k. lionen 15-301 and 15-302
- 1. Foan pinypipe uit h pickup tube .
- m. liydrant barrel appears dry
- n. liyarant accescibic
- 2. Ansul 9-26-123 (200), fuel oil pu~phouse WT* Accescible Location Scaled Damaged or Defective Tag Updated .
- 3. Ansu'. 9-26-124 (208), sewage treatraent area
Accessible Location Scaled Damaged cr Defective Tag Updated -
- Weight reciuired in June and December.
~ - . _ - __. - - _.
I
- TS-14 Page 2 CONDITIONS NORMAL INITIALS
- 4. Extension !!uilding
- a. Ansul 9-26-121 (20#), extensions building garage WT* Accessible Location ,
Scaled Damaged or Defective Tag Updated
- b. Pressurized water 9-26-216 (2b gal.), lower hallway west Pressur e - Sat. Accessible l Location Sealed Damaged or Defectiv2 [
Tag Updated
- c. CO2 9-26-222 (5#), lower hallway cabinet
- WT* Accessible Location Sealed Damaged or Defective Tag Updated CO 9-26-200 (55), CAS d.
2 WT* Accessible Location Scaled Damged or Defcctive Tag Updatcd
- e. Pressurized water 9-26-217 (2\ gal.), lower hallway cast Pressure - Sat. Accessible Location Scaled Damaged or Defective Tag Updated J
- f. Pressurized water 9-36-219 (24 gal.), upper hallway east Pressure - Sat. Accessible .
Location Scaled Damaged or Defective Tag Updated ,
- g. CO2 9-36-221 (5#), upper hallway cabinet WT* Accessible Location Scaled Damaged or Defective Tag Updated- -
- h. Pressurized water 9-36-220 (2h gal.), conference room 4 Pressure - Sat. Accer.sible Location
{ Scaled _ Daiaaged or Defective Tag Upd7ted
- Weight required in June and Deceraber.
. .c l
TS-14 i Page 3 L f
L CONDITIONS
~
NOR!!AL [
- INITIALS
{
- 1. CO 9-36-218 (108), electrical /hcating and. ventilating WT* Accessible Location Scaled Dar. aged or Defective' ,
Tag Updated j
- j. CO 9-36-212 (5#), computer Room 2
UT* Accessible _ Location f Scaled Damaged or Defective -
Tag Updated >-
- 5. FH-21, south fire hydrant (near parking lot)
- a. I hydrant wrench !
- b. Hydrant' barrel appears dry i
- c. Hydrant accessible
- 6. Gatehouse !
I
- a. CO 2 9-26-210 (5#)
l UT* Accessible Location t
! Sealed Dataaged or Defective [
Tag Updated 3
- b. Pressurized water 9-26-214 (2\ gal.) ,
Pressure - Sat. Accessible- ,
Location Sealed Dalaaged or Defective ,.
i Tag Updated ,
- 7. SAS .
L
- a. CO 2 9-26-215 (5#), SAS l P
WT* Accessible Location
- Scaled Damaged or Defective i Tag Updated I f
E f
- Weight required in June and December. .
t i
E i
9 ,
+ . - - - y ,, .- - , - - - - - ,m - . , - - , . . . - ~ , . - - . - - -
d TS-14 Page 4 1
" CONDITIONS MonMAL :
INITIALS
- 8. F11-27, southeast hose station inventory
- a. 6 lengths of 24" hose
- b. 3 lengths of Ih" hose
- c. 2 gate valves on hydrant shut
- d. 1 2b noa:lc 214 noz::les e.
- f. 1 gated wye ,
- g. I fire are s h. 1 urecking bar
- i. 4 spanner vrenches
- j. I hydrent wrench
- k. !!ydrant barrel appears dry
- 1. Hydrant accessible
- 9. Circulating..ater pu;phouse a.**HR-30 FP-35 shut Hose in place __
Cover installed Mozzle shut Condition 1
- b. Ansul, 9-26-120 (205) i t
WT* Accessible Location l
Scaled Dalanged or Defective t Tag Updated ,
- c. Ansul, 9-26-119 (200) [
. t r
WT* Accessible Location Damaged or Defective [
Scaled ;
Tag Updated .
d.**HR-29 t W
FP-34 Hose in place Cover Condition installed Nozzle shut FH-26. northeast hose station inventory j 10.
t
- a. 6 lengths of 2h" hose ;
- b. 3 lengths of 14" hose ;
- c. 2 gate valves on hydrant shut ,
r j
l
- Weight required in June and December. ,
l - ,
, , . . . - - _ , _ _ . . . - . . . . , , , _ , - , , - , , - . _ - , . . . -l
. . r. * - .
e, TS-34 Page 5 4
' CONDITIONS NORMAL INITIALS
- 10. (Cont'd)
- d. I 2h" nozzle
- e. 2 14" nozzles
- f. I gated wye
- g. I fire axe
- h. I wrecking bar ,
- i. 4 spanner wrenches
- j. I hydrant urench
- k. Ilydrant barrel appears dry 9
- l. llydrant accessible
- 11. Fil-25, north fir e hydrant (near 2X01)
- a. I hydrant wrench
. b. liydrant barrel appears dry I c. liydrent accessible
- 12. Warehouse #2 1
I
- a. Ansul, 9-26-136 (20#)
WT* Accessible Location Sealed Damaged or Defective Tag Updated
- b. Ansul, 9-26-135 (204)
WTA Accessible Location Scaled Damged or. Defective Tag Updated
- c. Ansul, 9-26-131 (20#) ,
- UT* Accessible Location Sealed Damged or Defective -
Tag Updated 4
- d. Ansul,.AU Spare 1 (350# Cart) -
Nitrogan Pressure Accessible Location Sealed Damged or Defective Tag Updated ,
- c. Dry pipe valve Air Side Pressure Water Side Pressure
}
Check Compress.or Oil Level Chcck Water Prime on Valve 1-
- Weight required in June and December.
y wq, --
p -e e.-&-.~---+7--;amy- 9 -,---,ym7.---,. y ,w.y ..g-p9-=er. ,-- w- - -
w . _ + - . .--.r-%-y, ,- y--*my y1 5---t-r 3 e
r s .
's
. TS-14 Page 6 CONDITIONS NORliAL
~
INITIALS
- 13. Fit-24, northwest hose station inventory
- a. 6 ler.gtt' of 2h" hose
- b. 3 lengt B of Ib" hose
- c. 2 gate valves on hydrant shut
- d. 1 25" nozcle 2 1\" nozr.le c.
- f. I gated wye
- g. 1 fire axe
- h. I vrecking bar
- i. 4 spar.ner wrenches
- j. I hydrant wrench
- h. liydrant barrcl appears dry
- 1. 11ydrant acces sible
- 14. SG CO system and Ansuls 2
- a. llanual iscaltion on cardox tank Open and sealed Seal in place on start suitch
- b. Quick throu valve at east daor open Itose station condition ,
NOTE: DO fl0T RENOVE ll0ZE OR NO22LE.
- c. Tank level %, (min. C5)
- d. Ansul 9-26-129 (20E) ,
WT* Accessible Location Scaled Damaged or Defective Tag Updated _
- e. Ansul 9-26-128 (20#)
WT* Accessible Location Scaled Damaged or Defective Tag Updated
- f. Ansul 9-26-127 (Fixed 150#) ,
Nitrogen pressure Gas quick throw valve scaled open __ Relea.se mechanism cover scaled closed Damaged or Defective Tag Updated
- Weight required in June and December
O
. e
.TS-14 Page 7 CONDITIONS HORMAL INITIALS
- 15. FH-23, west fire hydrant (near SG)
- a. I hydrant wrench
- b. Hydrant barrel appears dry
- c. Hydrant accessible
- 16. Warehouse #1 dry pipe valve and . sprinkler system Compressor pressure Water pressure Air side pressure Check compressor oil level Check water prime on valve
- 17. Ansul 9-26-126 (20!!), Warhouse #1 WT* Accessible Location Sealed Damaged or Defective Tag Updated
- 18. Ansul 9-26-125 (208), garage WT* Accessible Location Sealed Damaged or Defective Tag Updated
- 19. Ansul 9-2C-133 (200), gas pump WT* Accessible Location Sealed Damaged or Defective Tag Updated _,
- 20. Switchyard control house
- a. Ansul 9-26-133 (208)
WT* Accessible Location Sealed Damaged or Defective - .
Tag Updated .
- b. Ansul 9-26-132 (150# Cart)
Nitrogen pressure Accessible Location .
Scaled Damged or Defective Tag Upwated
- c. CO 2 9-26-131 (1004 Cart)
WT* Accessible _ Location Scaled Damaged or Defective Tag Updated
- Weight required in June and December.
MMW
,TS-14 o Page 8 CONDITIO!!S MOR11AL
- INITIALS
- d. Ansul 9-26-130 (204)
WT* Accessible Location Scaled Damaged or Defective Tag Updated 0FFICE ARCA
- 21. Pressurized water, 6-26-104 (2h gal.)
Pr est.ure - Sat. Accescible Location Scaled Damaged or Defective Tag Updated
- 22. C0 , 6-26-103 (2\#)
2 WT* Accessible Location Scaled Damged or Defective ,, Tag Updated
- 23. !!C-2, Cabinet FP-61 Shut liose in place
, llozzle Shut Condition OTl!Cf1
- 24. Ansul 9-26-144 (54), Pickup 2811J WT* Accessible Location Secled Damaged or Defective Tag Updated
- 25. Ansul 9-26-145 (5#), Truck 3004A WTA Accessible Location Scaled Damaged or Defective Tag Updated
- 26. Ansul 9-26-146 (54), Truck 1004B WT* Accessible Location Sealed -
Damaged or Defective Tag Updated
- 27. Ansul 9-26-147 (5#), Truck 1003B WTA Accessible Location Sealed Damaged or Defective Tag Updated
- Weight required in June and December.
, . t k
, TS-14 Page 9 CONDITIONS NORMAL
, - INITIALS
- 28. Ancul, 9-26-194 (5#) Truck 1833D WT* Accessible Location Scaled !
Damaged or Defective Tag Updated
. I i
- 29. Ancul 9-26-163 (58), Galion, Cherry Picker
, UT* Accessible Locotion Sealed
! Damaged or Defective Tag Updated l
- 30. Ansul 9-26-164 (5#), Tractor i i
UI* Accessibic Location Sealed I Data.ged or Defective Tag Updated [
- 31. Annul 9-26-195 (208), site Boundary Control Center !
I
] UT* Acceccible Locaticn Scaled
, Dant.ged or Dcrective Tag Updated ,
- 32. An'sul 9-26-196 (5#), Guard Vehicle 251d3 WTA Accessible Location Sealed '
j Dam 09;d or Dcfective Tag Updated
~
- 33. Ansul 9-26-197 (5#), Gasoline Fork Lift WTI' Accessible Location Sealed .
Damaged or Defective Tag Updated ,
- 34. Annul 9-26-162 (200), Guard Trailer '
a i
+
UTA Accessible Location Sealed Damaged or Defective Tag Updated t i
r
- Weight required in June and December. .
t t
E r
s ,
I
. . e * - pr*
_ ..,-._m - , , . _ . _ , . , , _ , _ . . , . _ , . . - , ..mv...,,,.r,,, , _ ..m.4.- .~.y _
4,_m_,,,wi-
o
,TS-14 Page 10
- 35. Conduct surveillance on the following Maintenance welding carts.
14 - 208 Cartridges needed.
Ansul units installed on carts.
Tag Conditions Ext. # Nano . WT.* Location Se aled Updated 7 f f,,1g 10-M-148 Welding Rig #1 10-M-149 Wolding Rig G2 10-M-150 Welding Rig #3 10-M-151 Welding Rig #4 10-M-152 Nelding Rig #5 10-M-153 Wclding Rig f 6
~10-M-154 Wolding Rig #7 10-M-155 Welding Rig ES 10-n-156 Wclding Rig #9 10-M-157 Oxyacctylono Rig A 10-M-158 Oxyacetylene Rig B 10-M-159 Oxyacetylene nig C 10-M-160 Oxyacetylene Rig D 10-M-182 Oxyacetylenc Rig C ,
s
- Weight required in June and December O
S f
~
. February 26, 1981 Page 1 of 2 ATTACHMENT E 4
CIRCULATING WATER PUMPHOUSE_
FIRE PROTECTION We are concerned that the evaluation statements contained in the October 21, 1980 supplement to the Fire Protection Safety Evaluation Report do not indicate sufficient understanding of the Circulating Water Pumphouse i configuration. The total pumphouse arrangement is shown on Figure 1. t Figure 2 is an expanded view of one-half of the safety related pump area. 1 It should be noted that the diesel fire pump day tank is located 1 within a curbed area in a corner of the non-safety related portion of the pumphouse. Oil piping to and from the diesel engine is embedded in the floor. Each circulating water pump is surrounded by a section of floor grating. Pump lubricating oil or spilled transient flammable liquids would i drain through the grating to elevation -11'-9". Each circulating water pump is in a separate compartment at this lower elevation. ' The safety related pump area is completely separated at the -11'-9" elevation by 2 foot thick concrete walls and is partially bounded on two sides by 12 inch thick concrete missile barriers at the operating floor level. Non-safety related motor control centers are set on 7 inch high concrete pads. Safety related pump cables are embedded in the concrete floor.
The concern expressed in the Safety Evaluation Report was that a fire at the diesel driven fire pump could damage the service water pumps.
The supplement states that installation of curbs, deflectors and a floor drain in this area is acceptable. Therefore, the concern expressed in the Safety Evaluation Report appears to be resolved. The metal security wall arocnd the safety related pump area was installed for security purposes, provides no fire protection benefit other than restricting access to the area, will not be removed, and does not qualify as a basis for rejecting the proposed fire protection modifications.
The barrier and equipment location recommendations listed in the supplement do not relate accurately to the configuration of the circulating L water pumphouse shown on Figure 1. , l The licensee's fire protection efforts have resulted in improve-
, ment of the originally proposed circulating water pumphouse fire protection ;
i modifications: i
- 1. The number of fire dete. tors will be increased 6 1;o 15.
- 2. The wet pipe automatic sprinkler system will cover the entire safety related area inside the security wall.
- 3. The curbs, deflectors and floor drain around the diesel engine ,
will remove spilled oil from the safety related area and not merely contain it.
- 4. Curbing will be installed around the perimeter of the security wall and c threshold installed in the doorway to prevent spilled i flammable liquids from entering the safety related area.
?
i
Page 2 of 2 l J
- 5. Steel plate will be installed over the floor grating in the
- 1. safety related area to prevent flame from a potential fire in a circulating water pump pit from entering the safety 4
related area.
The proposed modifications include barrier modifications designed ,
. to protect the entire safety related pump area from flammable liquid spills !'
instead of each service water pump. This provides greater distance separa-j tion from potential fires without impairing access to the service water l pumps than would be provided by many individual barriers. The numerous !
'- openings in the circulating water pumphouse floor will prevent the accumu- ;
lation of a large quantity of flammable liquid. Therefore, the potential ;
i for a long duration fire does not exist and the specification for rated !
fire barriers is of reduced practical significance. We consider the pro-posed modifications to be suitable to the requirements of Appendix R Section III G.
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