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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:OUTGOING CORRESPONDENCE
MONTHYEARML20217A5911999-09-30030 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 IR 05000266/19990041999-04-28028 April 1999 Discusses Insp Rept 50-266/99-04 on 990105-0222 & Forwards NOV Re Failure to Ack Validity of Temp Alarm & Appreciate Significance of Low Temp Readings for Unit 1 SI Pumps Min Flow Line ML20206B8121999-04-23023 April 1999 Forwards FEMA Evaluation Rept for 981103 Emergency Preparedness Exercise at Point Beach Nuclear Power Plant. Deficiency Identified for Manitowoc County as Result of Exercise.County Corrected Deficiency Immediately ML20205S7041999-04-20020 April 1999 Forwards Insp Repts 50-266/99-05 & 50-301/99-05 on 990222-0312.One Violation Noted & Being Treated as Non-Cited Violation.Expresses Concern Re Timeliness of C/As ML20205R4651999-04-19019 April 1999 Forwards Insp Repts 50-266/99-10 & 50-301/99-10 on 990329- 0401.No Violations Noted.During Insp NRC Observation of Licensee Activities Showed Emergency Preparedness Program to Be Adequately Implemented ML20205R6081999-04-19019 April 1999 Confirms of NRC Routine Mgt 990504 Meeting in Lisle,Il to Discuss Progress in Implementation of Improvement Initiatives in Engineering Area,As Well as to Discuss Challenges Faced by Operators ML20205P0311999-04-13013 April 1999 Refers to Various Changes Received by Region III in Jan 1999 to Portions of Point Beach NPP Emergency Plan.Informs That NRC Approval Not Required Based on Determinations That Changes Do Not Decrease Effectiveness of Emergency Plan ML20205N4221999-04-12012 April 1999 Discusses 990326 Predecisional Enforcement Conference with Util Re Apparent Violation Concerning Operator Response to Low Temp Alarm for Minimum Flow Recirculation Line for Unit 1 Safety Injection Sys.Handouts Provided by Util Encl ML20205C4701999-03-26026 March 1999 Discusses Review of Various Changes to Portions of Plant Emergency Plan.Informs That Revision Was Submitted Under Provisions of 10CFR50.54(q) ML20196K8731999-03-26026 March 1999 Advises of Licensee Planned Insp Effort Resulting from Plant Ppr.Plant Issues Matrix & Insp Plan for Next 6 Months Encl ML20204E5561999-03-16016 March 1999 Forwards Insp Repts 50-266/99-07 & 50-301/99-07 on 990216-19.No Violations Noted.Three Weaknesses Re Chemistry Program Were Identified ML20204D8161999-03-12012 March 1999 Forwards Insp Rept 50-266/99-04 on 990105-0222.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20207L9191999-03-11011 March 1999 Discusses from Util Informing NRC That Bases References for TS 15.4.4 Revised to Correct References to Point Beach Nuclear Plant FSAR Related to Reactor Containment Design.Revised Bases Page 15.4.4-7 Encl ML20207L1161999-03-10010 March 1999 Forwards Insp Repts 50-266/99-02 & 50-301/99-02 on 990105- 0222 & Nov.One Violation Associated with Program for Implementing Abnormal & Eops.Other Two Violations non-cited Violations ML20207H8661999-03-0808 March 1999 Ack Receipt of ,Which Transmitted Changes to Pbnp Security Sections 1.2,1.3,2.1,2.4,6.1,B-2.0,B-3.0 & Figure T,Per 10CFR50.54(p).No NRC Approval Is Required,Since Util Determined That Changes Do Not Decrease Effectiveness ML20207D6661999-02-22022 February 1999 Forwards Assessment of Design of Restraints on Main Steam Piping & Primary Loop Auxiliary Piping Systems at Point Beach Nuclear Plant.Staff Concludes That WE Unable to Retrieve Original Analyses That May Have Been Performed ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20202H6601999-02-0101 February 1999 Discusses Evaluation of Wisconsin Electric Power Co Response to NRC GL 97-05, Steam Generator Tube Insp Techniques ML20206U2981999-02-0101 February 1999 Informs That by 980811 & 1223 Ltrs,Nrc Responded to WOG Positions Re Corrective Actions to Address Generic Aspects of part-length Control Rod Drive Mechanism Housing Issue Resulting from Leak at Prairie Island,Unit 2 on 980123 ML20202G5321999-02-0101 February 1999 Forwards Insp Repts 50-266/99-03 & 50-301/99-03 on 990111-15.No Violations Noted.Cooperation,Communication & Effectiveness of Security & Maint Staff to Ensure Equipment Effectiveness Has Been Successful ML20199H5491999-01-15015 January 1999 Forwards Insp Repts 50-266/98-21 & 50-301/98-21 on 981121- 990104 & Notice of Violation.Violation Being Cited Because of Repetitive Nature & That Violation Could Reasonably Have Been Prevented by C/A for Previous Finding ML20206R8891999-01-13013 January 1999 Forwards SER Accepting Util 981116 & 30 Proposed Revs to Nuclear Quality Assurance Program Implemented at Point Beach Nuclear Plant Units 1 & 2 ML20199D7751999-01-0808 January 1999 Documents 990105 Telcon Issuing Notice of Enforcement Discrection for Wisconsin Electric Re Point Beach,Unit 1 ML20198K6911998-12-24024 December 1998 Forwards Insp Repts 50-266/98-22 & 50-301/98-22 on 981208-10.No Violations Noted.Concludes That Licensee Carried Out Properly Addressed Findings of Maint Rule Baseline Insp ML20198J6061998-12-22022 December 1998 Discusses Plant,Units 1 & 2 Licensed Operator Staffing Requirements 1999-09-08
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.8 3 UNITED STATES S
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j WASHINGTON, D.C. 20555-0001 Scientech, Inc. SEP 2 31993 1 ATTN: James Meyer, Project Manager l 11821 Parklawn Drive l Rockville, MD 20852 Dear Mr. Meyer- i
Subject:
Contract No. NRC-04-91-068 Task Order No. 23 Entitled, ,
" Individual Plant Examination (IPE) Reviews, Internal Events, !
Back End Only" (Point Beach Units 1 & 2)
In accordance with Section G.5, Task Order Procedures, of the subject !
contract, this letter definitizes Task Order No. 23. This effort shall be performed in accordance with the enclosed Statement of Work.
Task Order No. 23 shall be in effect from September 30, 1993 through September 29, 1994 with a total cost ceiling of $18,334.77. The amount of
$16,753.00 represents the total estimated reimbursable costs and the amount of l
$1,581.77 represents the fixed fee. l The obligated amount of this task order is $18,334.77.
Accounting Data for Task Order No. 23 is as follows:
APPN No.: 31X0200.360 B&R No.: 36019202300 JOB CODE: L1933 BOC No.: 2542 Obligated Amount: $18,334.77 RES Identifier: RES-C93-215 The following individuals are considered to be essential to the successful performance for work hereunder: James Meyer and Henry Amarasooriya.
The Contractor agrees that such personnel shall not be removed from the effort under the task order without compliance with Contract Clause H.1, Eey Personnel. !
The issuance of this task order does not amend any terms or conditions of the I subject contract. I Your contacts during the course of this task order are:
Technical Matters: John Flack, Project Officer (301) 492-3979 l Contractual Matters: Paulette Smith, Contract Administrator (301) 492-7670 h10 930923-I NRC-04-91-OSg pyg .w.
Uf I
i
+
NRC-04-91-068 '
Please indicate your acceptance of this Task Order No. 23 by having an official, authorized to bind your organization, execute three copies of this document in the space provided and return two copies to the above Contract Administrator. You should retain the third copy for your records.
As we rapidly approaching September 30, our fiscal year ending date, you should expedite the execution of and return of this document. Unless the signed documents are returned to me prior to that date, I cannot assure you of the continued availability of these funds. You also also requested to FAX a copy of the signed document as soon as possible to ensure that the NRC has adequate time to record this obligation of funds. The facsimile number is (301) 492-4994.
If you have any questions regarding the modification, please contact Paulette Smith, Contract Administrator, on (301) 492-7670.
Sincerely, J. .
Jdfc A. Fields, Contracting Officer Contract Administration Branch No. 3 Division of Contracts and Property Management Office of Administration
Enclosure:
Statement of Work 1 ACCEPTED: > .
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Marsiia11 T J.Cd av V N
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TITLE l
l September 27, 1993 DATE l
Contract NRC-04-91-068 Scientech STATEMENT OF WORK Task Order - 23 TITLE: Individual Plant Examination (IPE) Reviews.
Internal Events Back-End Only (Point Beach Units 1 & 2)
DOCKET NUMBER: 50-266 NRC PROJECT MANAGER: John H. Flack, RES (301-492-3979)
NRC TEAM LEADER FOR POINT BEACH UNITS 1 & 2: John H. Flack, RES (301-492-3979)
TECHNICAL HONITOR: John H. Flack, RES (301-492-3979)
PERIOD OF PERFORMANCE: September 30, 1993 through September 29, 1994 BACKGROUND:
On November 23, 1988, the NRC issued Generic Letter 88-20, " Individual Plant Examination," which stated that licensees of existing plants should perform a systematic examination .(IPE) to identify any plant-specific vulnerabilities to severe accidents, and to report the results to the Commission. The purpose of the IPE is to have each utility (1) develop an overall appreciation of severe accident behavior; (2) understand the most likely severe accident sequences at its plant; (3) gain a quantitative understanding of the overall probability of core damage and radioactive material releases; and (4) reduce the overall probability of core damage and radioactive releases by modifying 3rocedures '
and hardware to prevent or mitigate severe accidents. All IPE su)mittals will be reviewed by the NRC staff to determine if licensees met the intent of Generic Letter 88-20.
OBJECTIVE: ,
. The purpose of this.coatract is to solicit c~ontractor support in order to enhance the NRC review of licensees' IPE submittals. This contract includes the examination and evaluation of the Point Beach Units 1 & 2 IPE submittal, specifically with regard to the "back-end" analysis. The contractor review will be of limited scope and consist of a " submittal only" review and the licensee's resaonse to questions raised by the staff. The " submittal only" review and gatiering of associated insights will help the NRC staff determine-whether the licensee's IPE process met the intent of Generic Letter 88-20, or whether a more detailed review is warranted.
By identifying the IPE's strengths and weaknesses, extracting important insights and findings, and providing a comparison to staff reviewed and 1
accepted PSAs (e.g. NUREG-1150, PSAs identified in NUREG-1335 Appendix B), it is expected that the NRC will be in a better position to expeditiously evaluate the licensee's IPE process. To provide support under this contract, ,
l the contractor will search for obvious errors, omissions and inconsistencies in the IPE submittal and the licensee's response to a " Request for Additional !
1 Information," (RAI) as described in the work requirements listed below.-
WORK RE0VIREMENTS AND SCHEDULE:
The contractor will perform a " submittal only" review of the Point Beach Units ,
1 & 2 "back-end" IPE analysis. [The review is to include only the Level II !
analysis. Review of Level III (consequence analysis) is beyond the scope of this contract.) The contractor shall provide the qualified specialists and the necessary facilities, materials, and services to carry out such a review.
The contractor will utilize NRC review guidance documents for detail and reference, as well as other interim guidance provided by the FRC Technical Monitor. The contractor is not expected to make a plant / site visit in order to perform this review.
Subtask 1. Review and Identification of IPE Insichts Perform a back-end " submittal only" review of each IPE submittal and identify important IPE insights by completing the NRC IPE Data Sumary Sheets. During the review, focus on the areas described below under " Work Requirement." The contractor will note any: (1) inconsistencies between methodology employed in the IPE submittals and other P5A studies, and (2) inconsistencies between the submittal's IPE findings and findings stemming from other PSAs (See NUREG-1335, Appendix B). Respond explicitly to each work requirement by noting important review findings including any IPE strengths and weaknesses.
Appropriately characterize any shortcomings with respect to the impact on IPE conclusions. Identify and provide a justification for a Request for Additional Information (RAI). , ,
Word Recuirement 1.1. Perform a General Review of the licensee's IEE Back-End Analytic Process Check the following:
1.'1.1 The IPE submittal is essentially complete with respect to the /
level of' detail requested in NUREG-1335.
1.1.2 IPE employed methodology is clearly described and justified for selection. Approach is consistent with Generic Letter 88-20 <
Appendix 1.
1.1.3 The IPE employed a viable process to confirm that the containment-and containment systems represent the as-built, as-operated plant.
1.1.4 IPE back-end had been appropriately peer-reviewed to help assure ;
the analytic techniques were correctly applied. i 2 ;
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P Work Reauirement 1.2. Review of the Containment Analvsis/Charatterization .
Check the following:
1.2.1 The IPE analysis appropriately treated front-end and back-end dependencies, i.e., plant damage states considered reactor ,
system / containment system availability, system mission times, inventory depletion, dual usage (spray vs. injection).
1.2.2 Classes of sequences with significant probability (those that meet the G.L. 88-20/NUREG-1335 screening criteria) were evaluated further using simplistic, but realistic, containment event trees.
1.2.3 The focus of the IPE's containment analysis was on failure modes and timing. Containment failure modes are consistent with those identified in Table 2.2 of NUREG-1335.
1.2.4 The IPE process assessed and identified contributors to containment isolation failure.
1.2.5 System / human response were integrated with the phenomenological aspects of accident progression into the containment event trees.
Allowances for recovery actions were made to allow for accident management actions.
1.2.6 The IPE submittal approp'riately documented radionuclide release characterization for accident sequences exceeding the Generic letter 88-20 (or NUREG-1335) screening criteria.
Work Reauirement 1.3. Review the Ouantitative Nature of the Accident Procression and Containment Performance Analysis Check the following:
1.3.1 The licensee employed a reasonable process to understand and quantify severe accident progression. The process lead to a determination of important conditional containment failure probabilities, and considered phenomenological uncertainties, either qualitative or quantitative. - <
1.3.2 Dominant contributors to containment failure are consistent with insights from other PSAs of similar design.
1.3.3 The IPE a)propriately characterized containment performance for each of t1e CET end-states by assessing containment loading -
(either calculated or referenced).
1.3.4 The containment analysis considered the impact of severe accident environments on equipment behavior.
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Work Recuirement 1.4. Review the IPE Acoroach to Reducino the Probability of Core Damace or Fission Product Release Check the following:
1' 1.4.1 The IPE analysis appears to support the licensee's. definition of vulnerability, and that the definition provides a means by which the identification of potential vulnerabilities (as so defined) and plant modifications (or safety enhancements) is made possible.
1.4.2 The identification of plant improvements and proposed modifications are reasonably expected to enhance plant safety.
Work Reouirement 1.5, Review Licensee's Response to Containment Performance Imorovement Recommendations Check that the licensee appropriately responded to ret.ommendations stemming from the Containment Performance Improvement (CPI) Program, i.e., that the ,
licensee's assessment, findings, conclusions and actions (as appropriate) considered the following as a function of containment type:
BHRs (MARK I,II,III) o Harden vent :
o Alternative water . supply for drywell spray / vessel injection :
o Enhanced reactor pressure vessel depressurization system reliability '
o Implementation of Revision 4 of the BWR Owners Group EPGs o Improved hydrogen igniter power supply (Mark III) j Additional for BWR (MARK III) l 1
Evaluation of vulnerability to interrupted power supply to' o !
hydrogen igniters and need for improvement l PWR Ice Condenser Containments o Evaluation of vulnerability to interrupted power supply to j hydrogen igniters and need for improvement j
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i PWR Dry Containments o Evaluation of containment and equipment vulnerabilities to hydrogen combustion (local and global) and need for improvement. This would include consideration of gaseous pathways between the cavity and the upper containment volume l
to confirm adequate communication to promote natural circulation and recombination of combustible gases in the reactor cavity.
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Work Reautrement 2.0. Complete Data Sheets A. Summarize data on the Consolidated Data Summary Sheet as described below.
GONSOLIDATED DATA
SUMMARY
SHEET (INTERNAL EVENTS) o Conditional containment failure probability given core damage:
o Significant PRA findings:
o Enhanced plant hardware (implemented after 1988 PRA) containment modifications:
o Potential containment improvements under consideration and not modeled:
B. Complete the NRC data summary sheets and note any lack of information, as appropriate. However, exclude those data entries marked "BNL Data Entry." These data will be collected by Brookhaven National Laboratory under a separate contract.
Subtask 2. PreDare Preliminary Technical Evaluation Report Prepare a preliminary Technical Evaluation Report with the outline prescribed below. ,
I. Executive Summary Provide a brief overview of the IPE review, the scope and depth as appropriate. Place emphasis on review areas identified as being important and rationale for importance, i.e., found to be important in other PSAs of similar design. Discuss any important or unique plant characteristics. Note plants with similar features and any important ' -
insights stemming from other relevant PSA studies.
II. Contractor Review Findings Ex211citly address each work requirement element listed above under Su) task 1, " Review and Identification of IPE Insights." Discuss any .
strength or weakness so identified and significance with respect to the overall IPE effort. Identify any additional information (in the form of questions back to the licensee) which would be important to the review effort. List these questions separately in an appendix.
Indicate why the information is important for closure.
III. Overall Evaluation and Conclusion Summarize the " submittal only" review conclusions based on the information submitted and significance of IPE strengths and weaknesses.
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IV. IPE Insights, Improvements, and Comitments Characterize important IPE findings and insights, including any significant containment characteristics or analytic assumptions that impact insights. Describe and characterize any significant enhancements implemented by the licensee, specifically in response to important insights which stem from the IPE process. Identify any licensee commitments and characterize the need to track comitments based on the impact on IPE conclusions. Also identify and characterize any potential improvements not forthcoming but perceived to be significant.
V. IPE Evaluation and Data Sumary Sheets i Attach: (a) Consolidated Data Sumary Sheets using the above outline, and (b) the NRC IPE data sheets.
Appendix: Questions and Comments Provide all questions and coments which are to be discussed with the licensee. Provide rationale for coments, especially when seeking additional information.
Subtask 3. Prepare Final Technical Evaluation Report Review the licensee's response to staff questions and comments. Update the preliminary TER developed under Subtask 2, as appropriate, based on the additional information received from the licensee. Emphasis should be placed on review areas identified under Subtask 2. Provide rationale as appropriate !
to support the need for any additional follow-on studies or recommendations. ;
Note: The contractor should be prepared to participate in telephone !
comunications with the licensee and/or discussions with NRC review team l members regarding the licensee's responses to questions and issues ,
- i stemming from the preliminary TER.
l REPORT RE0VIREMENTS:
Technical Reports
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The contractor will. submit to the NRC Technical Monitor four copies of the Preliminary Technical Evaluation Report (TER) on January 3?,1994. Copies will include three hard copies and one 3.5" computer diskette version (Wordperfect 5.1 or other IBM PC com>atible software acceptable to the NRC IPE Team Leader). The Preliminary TER s1all sumarize all findings, results, and ,
conclusions in the areas examined in the format described under Subtask 2. If the contractor finds that the licensee's IPE is obviously deficient in' any of' the areas examined, the Technical Monitor should be notified in advance.
Deficient or weak areas should be clearly documented in the Technical Evaluation Report. In addition, if the contractor finds that there are specific areas that need additional in-depth review, the Team Leader 6
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The contractor will submit to the NRC Technical Monitor three copies of the Final Technical Evaluation Report (TER) two weeks after the receipt of the licensee's response to staff questions and comments. Copies will include two hard copies and one 3.5" computer diskette version (Wordperfect 5.1 or other IBM PC compatible software acceptable to the NRC IPE Team Leader). The Final TER shall update all findings, results, and conclusions in the areas examined in the format described under Subtask 2 as appropriate.
BUSINESS LETTER REPORT:
The contractor shall provide monthly progress reports in accordance with the requirements of the basic contract.
MEETINGS AND TRAVEL:
One, one person trip to NRC Headquarters to present and discuss review findings and conclusions.
ESTIKATED LEVEL OF EFFORT:
For each IPE reviewed:
Subtask 1 80 contractor hours Subtask 2 80 contractor hours Subtask 3 16 contractor hours It shall be the responsibility of the contractor to assign technical staff, employees, and subcontractors who have the required educational background, '
experience, or combination thereof, to meet both the technical and regulatory objectives of the work specified in this S0W. The NRC will rely on representation made by the contractor concerning the qualifications of the personnel proposed for assignment to this task order including assurance that all information contained in the technical and cost proposals, including resumes and conflict of interest disclosures, is accurate and truthful.
NRC FURNISHED MATERIAL:
- 1. Licensee's IPE submittal.
- 2. Licensee's response to staff generated questions and associated information.
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TECHNICAL DIRECTION:
The NRC Project Manager is:
John H. Flack Severe Accident Issues Branch Division of Safety Issue Resolution U.S. NRC, Mail Stop NL/S 324 Washington, D.C. 20555 Telephone No. (301) FTS-492-3979 L
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