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Category:ANY EXTERNAL MEMORANDUM ROUTED TO NRC & NOTES
MONTHYEARML20087H7221984-03-12012 March 1984 Comments on Need to Resolve Mgt Integrity Issue Prior to NRC Restart Decision ML20023B9371983-04-0404 April 1983 Forwards Eh Gischel Affidavit & Memo Re Allegations on safety-related Mods & Tests.Investigation Underway ML20076J8721982-09-16016 September 1982 Memo Re Leak Feasibility ML20085B1071982-06-17017 June 1982 Discusses Symptoms of Transients ML20085B1061982-06-17017 June 1982 Discusses Symptons of Transients ML20085B0891982-06-17017 June 1982 Submits,For Discussion, X Large Break W/Auxiliary Feedwater & Z Small Break Auxiliary Feedwater W/O Reactor Coolant Pumps ML20085B1091982-05-11011 May 1982 Submits Marginal Comments ML20077K9141982-02-25025 February 1982 Suggests Possible Misreading by Operator ML20085A9131982-02-23023 February 1982 Submits Names of B Karrach & Bm Dunn ML20085A6561982-01-22022 January 1982 Lists Activities,Including Site Program Repts,Weekly Status Repts,Radcas,Emergency Operations,Owners Group Meetings, Operating Experience Seminar,Plant Data Output,Summary Test Rept,Restart Test Rept & Training Contacts ML20024C5711981-07-0101 July 1981 Provides Sequence of Events ML20066F2931980-04-0707 April 1980 Summarizes 800407 Formal Exit Meeting for IE Insp Rept 50-289/80-06 on 800301-31 ML20090G3201980-02-0101 February 1980 Forwards Summaries of Recent Correspondence Re TMI-1 PORV & Excerpts from TMI-1 Restart rept,NUREG-0578 & NUREG-0560 ML20069M8531980-01-14014 January 1980 Discusses IE Insp Rept 50-289/79-24 on 791128-800104 ML20024C5561979-12-14014 December 1979 Emphasizes Need for PRA Capability.Related Info Encl ML20085A6801979-11-27027 November 1979 Requests Evaluation & Action on Submitted Issues Critical to long-term Function of Engineering Dept.Issues Re Mgt of Resources,Product Responsibility & inter-dept Coordination Recommended ML20085A9791979-09-10010 September 1979 Forwards Surveillance Instructions Sent to Customers Re Previous PORV Failures ML20085A8431979-09-0404 September 1979 Requests Concept & Details of Safety Review Group Formation Be Reviewed W/Macmillan.Safety Review Group Should Meet Prior to 790915 to Develop Plan for near-term Actions for Submittal by 791001.Plan Should Include Manpower Assessment ML20024C6061979-09-0404 September 1979 Summarizes Analysis Code Requirements & Verification Project,Action Item 5 on CRAFT2 Simulations of Small Break Transients ML20085A4701979-09-0303 September 1979 Compares B&W & TVA Positions Following 781204 Telcon on Small Break LOCA Analysis.B&W Failed to Evaluate Michelson Rept in Sufficient Detail to Respond to TVA 781204 Telcon Questions ML20085A4101979-08-0303 August 1979 Summarizes 781204 Telcon W/B&W Re Small LOCA ML20024B2921979-07-31031 July 1979 Responds to Embrey Request for 790801 Draft &/Or Status of Presentation for B&W Sys Responsiveness & Suppls 790726 Ltr ML20085A9701979-07-30030 July 1979 Discusses Emergency Operation Guideline Preparation & Maint.Comments on Encl LER Review Proposal Requested by 740807 ML20090G3871979-07-18018 July 1979 Reviews Procedures 2202-1.1 Through 2202-2.5 ML20085A6481979-07-16016 July 1979 Requests Results of & Any Actions Taken Re Davis-Besse-1 Depressurization Incident in Sept 1977 ML20125B4661979-07-13013 July 1979 Discusses 790905 Condensate Polisher Valve Malfunction. While Attempting to Place Polisher 8 in Svc & Remove Polisher 6,water Was Found in Air Supply to Polisher 8 Recorder.Event Duplicated 790328 Trip ML20085A6841979-06-0808 June 1979 Recommends That B&W Site Residents Should Be Requested to Submit Immediately Notification of PORV Operation Situations.Prompt Feedback to Jd Carlson Requested ML20136B5291979-06-0707 June 1979 Discusses Criteria for Processing I-131 Waste Using EPICOR-II Sys.Suggests Using Decanting/Sluicing Pump & Flow Path from Given Resin Bed to Truck Loading Dock.Requests Comments by 790615 ML20136B5341979-06-0707 June 1979 Describes Status of EPICOR-II Facility Operability Program. Facility Presently Capable of Processing Radioactive Water. Schedule of Activities Necessary to Complete Operability Program Encl ML20085A8471979-06-0505 June 1979 Forwards 790604 Memo Re B&W NSSS Responsiveness.Meeting W/N Embrey Recommended to Map Strategy for Demonstrating Manageability of Transient Control ML20024C5111979-05-31031 May 1979 Advises That Preliminary Rept of Safety Concern PSC 16-79 Will Be Provided Upon Completion ML20125D8991979-05-18018 May 1979 Summarizes Encl Testing Results for Scott canister-type Respirators,Per 790518 Telcon W/A Hack of Lasl.Environ Evaluation Encl ML20085B0971979-05-0202 May 1979 Forwards Draft Writeups on Small Break Scenarios to Be Used in Small Break Cooldown Procedure.Comments,In Procedure Form Requested ML20085A4781979-05-0202 May 1979 Forwards Draft Repts on Small Break Scenarios to Be Used in Small Break Cooldown Procedure.Comments Requested. Descriptions of RCS Leaks W/Auxiliary Feedwater & W/O Feedwater & Small Breaks in Pressurizer Encl ML20024B7561979-05-0101 May 1979 Forwards Results Summary of 1978-79 Requal Written Exam,For info.Post-oral Packages Forwarded to Individuals Having Two or More Categories Less than 80% ML20136C6881979-04-15015 April 1979 Responds to Ke Suhrke 790414 Memo,Instruction 461,re Relief Valve Performance.Forwards Tables Providing Electromatic Relief Valve Open/Close Times,State of Fluid Passing Through Valve,Flow Rate & Integrated Flow ML20024B4811979-04-14014 April 1979 Discusses C Michelson,Of Tva,Critique of Small Breaks for B&W RCS in May 1978 ML20136C6631979-04-13013 April 1979 Forwards Drawing 141563E-13 of Reactor Coolant Piping Assembly Elevation ML20136C7121979-04-13013 April 1979 Forwards Drawing 141563E-13,reactor Coolant Piping Assembly Elevation.Re Kosiba 790409 Response to Levinson Forwarding Reactor Vessel Drawings for Core Bypass Calculations Encl ML20085B1041979-04-10010 April 1979 Discusses LOCA-type Accidents ML20126J7171979-04-0909 April 1979 Summarizes Trip to TMI-2 Following 790328 Incident ML20136C7221979-04-0808 April 1979 Discusses Method for Steam Generator B Integrity Checking. WR Stagg 790406 Memo to G Urquhart Re Clarification of Question 1 on once-through Steam Generator B Leak Encl ML20136C6711979-03-30030 March 1979 Discusses Contingency Recommendations for Actions If All Reactor Coolant Pumps Are Lost.Suggests Sys Be Taken Solid W/High Pressure Injection Pumps & Vented Through Pressurizer Via Electromatic Relief Valve Circulation ML20085A4191979-01-0303 January 1979 Submits Monthly Progress Rept for Dec 1978 ML20024C5831979-01-0202 January 1979 Forwards ECCS Analysis Unit Activities Rept,Dec 1978. ML20125D8801978-12-22022 December 1978 Discusses Pressurizer Level Problems Following Reactor Trip on Old Forest Road Simulator.Transient Pressurizer Inventory Strongly Dependent on AFW Feedrate.Runs Showed That Pressurizer Not Far from Empty After Normal Reactor Trip ML20024C5771978-12-11011 December 1978 Recommends Small Break Analyses W/Reactor Coolant Pumps Powered ML20024B4541978-11-16016 November 1978 Requests Withdrawal of 780404 Potential Safety Concern Re Secondary Side Auxiliary Feedwater Control Level.Problem W/ 6-ft Control Not Inadvertent,But Part of Planned Effort ML20024C8161978-11-15015 November 1978 Informs That Toledo Edison Needs to Reduce Auxiliary Feedwater Setpoints for Natural Circulation.Suggestion to Resolve Impasse Provided.Further Analytical Effort Required to Confirm 10 Ft Level Setpoint Adequate ML20024B4551978-11-0303 November 1978 Dismisses Validity of Potential Safety Concern (PSC) Filed Against 205 Plants Re Secondary Side Auxiliary Feedwater Control Level.Potential Obstructions Nonexistent 1984-03-12
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20128G1661996-10-0303 October 1996 Summarizes 960924 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Preliminary Responses to Staff RAI Concerning Request to Change EALs for TMI-1.List of Participants & Copy of Preliminary Response to RAI Encl 1999-09-29
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20203E0321999-02-11011 February 1999 Staff Requirements Memo Re 990211 Affirmation Session in Rockville,Md (Open to Public Attendance) Re Secys 99-044 & 99-045 ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20248H7001998-05-20020 May 1998 Staff Requirements Memo Re SECY-98-071,exemption to 10CFR72.102(f)(1) Seismic Design Requirement for TMI-2 ISFSI ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months 1999-09-29
[Table view] |
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*. B' amp-20345 (6-78)
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j M SITE PROSLE2{ ,- J.
7 REFORT TRANSHIITAL '
t i
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O **** C1.ZARED ****
$' .I 8
To: Change Control For Distribution- File:
13- 0 3 -(*10 1
- S. H. Klein - Quality Assurance ,
Conerset No.: 620-00. OJ SPR /d 7 f,
. central Ens:1.eerina Files 2.C.T3=,vhu - Task Intirteer(s) ^ Titles loss c4 ocey w.#
0."0.2u ct +>J J
- Project Snager Plow [t.# ?O Dates 7['#[7#
Status Code: C _
t ..
I L. C. Rogers - MET. ED. P. E. Perrone
!. 1. R. r.i.e - xctzm J. R. Ilohart - Inti. Support
- e. u. g' I
- 5. A. Karrasch - Plant Integration Attached is one copy of Site. Problem Report Na, 61/. which was processed on Contract 620-00 o3 . Future contracts have been reviewed for the potential
; of a similar problem. This problem is/is not considered applicable to other ec,ntracts I -
i * .
i .
REMARKS: 7fis SM was 4-smiffel m M n mf 4 ~ 4. J %.,meen.
j c!' ' aG a21:J LL*l. 2 Lo seJ" % - L elk . M. u. C ~a "en.1s O
.f tl is Atlt, . s. +L m le mek. el.uJ:
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-D 21e-NUCLEAR SERVICE SU??cRT C;GI::EER
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SITE PRCSLEM REPCR @ BA8 @ !. WILCCX odissaasJa dit ac c.73. caa i > 3. sra ao. a(s.a; cussow(e 4% o 1 Pa%L $lth? l3 - G ro-co o l
" Duke TL e Co. n o. raar ao.1 As4 ao. GAour ao. .w. ad.
,gnoo r.4 o <, z O- o , to /m./ . &
PAodLfM CostACT ac. ovi isILE (Mat i.oss30JCul.2Clili)
The2., #,cd r*lo m CLr- 0 N. //*,,s otsCalPrios of raostta:
. 3 ee- oflacked desev fan of Pro hl" *
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- 5 sTarus-acitan re o4rt. SECLDolAG Pttsos,s ConTACito:
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.D e ca..f W 0.w <.5 LJ.t.sk ea .
f o tiit tt Action itCoMutuoto 57 slit PttsonnEL:
' ') "" * #
- bN*'***"" f*Ef3 Ryl au LP t ske.m a Un~' *" ** *t at n ec4 s sa c.,,L f
t t e Mh s p erw6 r**I"') *
senice.
.i sesatution:
f Tu, su La raw.J ~1;n tus da --.%, .awk.,.J :.i. .J,w
. em:qe,& a ka t,y a j sa ) it t. . p. del M n-c A v Lr. so'-u
*LL G ',*ts k att u & s a n y.
- 5. m, 4.a.reuL h ij %, sett. is t L Q tra:3 deuJ .
i I DATE APPtotta ST OAft i : ', *5 PREPAttD g h j [ A s ,/,,f y
,E .gggggng;.gr
.oATE ,
*=
t cosi Caitcoar sitta caanct 4tg F.C.A..no.
sIGxtf. otFICits ?
Oxoes ornt O Orcs no ( o.- v4 O '(5 "8 O .
slit CCur(Lilam At7aki: OII8AIlo"3:
- g! O sont sre sty so. O i oAlt Courttito: ,.
- n Ip r t) (? t v
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4 M g .iy i '?. 5-d N*
- 5 $ M 94 lnin
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CONFIDENTIAL -
Y
*, - - - . wer - a, l 31Sf0 a 9 8 71- E15 .-Y D. T. ~.- 9i
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Oconee I
~. SPR-676 thescreottom o f 7t=2blen 5 4-N - t':rit shucdova (fd:rr OTSC tube repairs) . 0perators atteerpted to perfat:m an Inninesnring Saffe:;uards Test on the DE System, which involved The DH valve lineup was cycli:ng LP-1 and II.P-Z (DZuisolation valves) . -
chang =d pr'or to Jais' operration so that flow would not be lost during
. che c:est.
- - u ' - - - - -
3045 - Val-se LP-2 was shut- but would not re-open. DE flow'sas lost"as
~=esur.: of i=prope:r valve 111ceup by operator (i.e., LP-95 throttled and T P-13 closed, vics LP-13 cepen and LP-35 closed) . Repeated attecpts to
=e-open the valve were unsuccessful. Atte= pts to re-establish flou in che "isvitcfaover"' ade verce unsuccessful. Pm ".cor core teeperature in-creased tco approx:icately ~.210"P, and at 1730 .peractes finally succeeded
- in neblishi 3 c:ooling CIlov vith LPI pu=p (from ..e BWST). The lower smanumy and. handhaile coverrs had been rs=oved from the B-0TSG as part of
=uba: =epai= wrk..and the water overflowed into the building baaement, (Cappcoxim.a::atly 44,000 gallions) . The Reactor Bu11dir.s filled with steam from :the war ~200 F wateer.
s
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CONFID$NTAL
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M1-
! i SPR Coment Fonn :
-- -9 l' . Co u nt To: b . _. !
SER. No. I; 7 .
l SPR I -l t - -
ut d ~0 /
e 11t1e: T:' A ' E*% WA s s ~ . OS /E-) beO " M2
~~ ~ ~ ' ' -- ----
Date: i .7i -
e o I have reviewed the above SPR/ Resolution and have the following coments:
! l, Co.:.,)o.% A es na+ cle/ew -< Cu~ a. a A $ !. rc_ .
. kS.& /*1 v bg 0, Y fy v! A.4w-Su S~ vL.b ~(Y h ' '~y
; 4
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&c % ' fa. . f ., q . 1p le e o i
! .t *', cz. ,pn d
'
- Y kP[ h, c.g she'sr .M e t.l c, c/ _r -K .e. . m 4 h. / 4;,
,,,i ; f. 6l_ . /.i, ,' ,C../ G n -% r,
^
'%.c <. ~ . .-L ? .
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l .
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;. O Please consider these cements in you resolution; no reply to me is required.
l l 6 Please incorporate or #resolve these cc =ents. I would appreciate a
;. reply by */
. indicating how these ccer:ents have l . :.
been resolved.
1-I! / e P. E'.' Peri'one E'xt. 210
' /.[7 - f f
v CONFIDENTIAL m m'= .----.---s.
s- - - - - - - - , -- - __
c- x _ ,
318;p r O98 r 91 -
t E15'9 _x . .9. ..1'II .
l 2
h Y.' SITE PRCELEM RENr.L v
!!/ '! ,,'d'
- --St.CrK A WILCOX m "h%.W.-
1 OtsGenaiG4 .Att
- 0. Cons.ac. pra no. 4 t e . a c.
CusTO .e t e- - . a Tcledo Edisen Cocpeny F.R.Faist 3/27/78 lcc=. 13 620-0014 A c1
>> a- "'
'O vf20-tmatorque/Velan >-[1 TIS 022 28/0 t'1/001 PA03LEM CONTACT / ) g,) d)
MAX 20 Cs4AACT123)
Tf TLC (Sorc/ Viv C ernter I?otor
?:r. F. R. Psist # 4 <:~
Otscattilon of ra05LE:!: steing the courst of investigating the valve ste= nut
~~ ~
' failure (SPR Ikola , Rev. 0), as apparen discrepancy in li=itorque =otor herse-a power ratizig vs.s noted. Discussions uth 35 ' T.rtgineering (S. L,-ma.na) indi-
! cated that a 1 hp coter should have been su, plied with the operator. The
. original motor rece'ived cn site vas i1.6 hp cotor. It vc.s changed out -by O TECo (S?R #222). Motor na=eplate data is attachel. The code of failure of the 5 ste:2 nut vs.s probably due to excessive torque. A larger operator =otor vill
. result in core torque.
t.'.
.~
'i 3 ,
3 STATUS-Action To DATE. Inct00lds PLA30x3 ComiACTED:
S. Ls= anna, J. Lauer, B&*J, svare of proble=. B. Beyer (."'Eco) was. infor=ed of E
discrepesey.
I i futTHER ACTION REC 0HMENDED BY $4TE PER30ANEL:
I 1. Ccnfins size =otor that should be on operator.
l ., )
2 If changed to 1.6 hp rotor, provide details. .
. ~
~
.I L RE30LUTI0s:
$2E LfirE< Mbm 2. 4. J.gsergas.so) yo dj. Metr $j po rto .,.ig. g (3,,,y s ,4 y, E DATE I
1 PPtr t[0 sf DATE APPROVED sf S W_-_-_"-
\ . o a % b lf..$r f.A A . ro 94 . W Y~EU ~~ISt
,; %.J I Cosi CATEGOAT FIELO ChanGL 219 V
lF.C.A. NO.
a SICMlf. CCFICllhCT On0*a,.,.0txta O Orts no E l 0.. 4 O't3 "o 's.
SITE Courttilan atroti: DEYlATICn5:
- l. G 80"E
-(i SOM Letter 1375, copy atta:hed, vritten to the f DATC CCntLETID: 6/2/73
% = custc=cr en 6/2/78. This clears the SFR.
1-
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T. R. Taist h)#hd/2/TS
- r a rus ML, hems CONFIDENTIAL surrt / Or 3
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. A'~!ACi m N @ ch, P.ev. 01 > F=5*fsra/322 620-001h .
5/2c/77
.O ,
Descrietien of P :blem:
i . . .
t
- 1. Se valve =s.or operatcr vas cha:;;ed out c: 2C-r/2 during the week of .
? May 15, 1977. Sis was d:== hy TI:s !* sir.te:2=ce without censulting .
f BW. TTCo Milstena:ce said the =cter was fou:d bu :: c t while ecs-
"~ *
' ducting a survey of lir. iter-ua s 6;erators, ne repiscenent =o or-h=_s -- i the followi=g na=eplate data:
- l.
Replacene:s Ms er Dats Orieinal ?.~eter Data Telve PC-2 RC-2 ID T107kkCI 107' -CZ-Sta.4 .25 ft. Ibs. 25 ft. Ibs. .
. Run 5 ft. Ibs. . 5 ft. Ibs.
...- E.P. 1.6 1.6 Type P - P '.
Frame ' 256 B56 Amps 7.6/3.8 ,
Not ca nameplate. -
- Yolts 220/kl0 220/kho In$ulation Class E Class I 2Azty 15 min. , ,
15 min.
!, Radiation Insulation I Radiation Amp. Te=p. kO'c kO*C
. ?.
as
- 2. Aithough the r.:=eplate data is the sa=e as the criCinal:.otor, a reviev of the suitability of the LO'c ambiest re=;erature should be perfor=ed for this i velve =otor applicatics.
1 l ;.
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"u=e Telecopy to Trcsh ' - ell, 5/26/77. CONFIDENTML 5/26/h
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A s.n m_ o. A bn e7.,
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' SPR Cocr3ent fore 7o. l. 2 km c - c - ne SER.No._g l'..
sea , nt 3cc c . . .
T1tle: Qs e< LMa 7/C ?e ti,7 llAs. vi hf bings'?&&
jj
- e- .
I have reviewed the above SPR/acsolution and have the following cocinent.s:
Y N $6 S -
h
- a. Q..< /d c kg )
,- 4 K e W m .<.
~
L gg/ ka nA &.~ ,.M .
eg v,dd 4 pe A * .
&&. lgw o ---
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' h Please censider these corrrnents in ycur resolution; no reply to me is required.
lease iTicorpor e. solve these cocr.ents. A would appreciate a f reply by I l/ indicating how these com.ents have
! teen resolved. '
l, -
gik !*!"
P. E. Perrone. Ext. 2105
. CONFIDENTIAL l
s- .- .- ., r .,,wg ~. , - , . _ , _ , , .
318 0 9n 9.r3,!
. ris eYN;E.
~ -
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- -..n
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, . ...- ' l- ... / BABrG , l. !!ILCOX spa .e.p?% ~ ,. ,
}
n.,.o'i3. =7:"~ we ,-- mc::rus e .n,.-. ,
SITEeePECB'.D4
,,.,,. .. -r REPCM.. -
> o.n.sntion
- m. -
dait cy,=
; y. . . . ci, f. a ). 57a no. ..at,,,,.
l ci,5 g on(p. 11/2/77 13 - 620-001(a "( _, o Toledo Idison Ccupany F.R.Falst ,PAal no.fia;t m3. f. sour .y. i. Q. . ..
r.A. no.
. ,g, gag 023 090 IS 28/0al/005 1 . / lt ,1 Crosby g p y* 1,j, ,*
re;tt (iens 30 chaaacitR5)
PA08ttM COntaci
-.I 6 ,%,
J. E. A de:-so
Electrcratic.F.elief Valve 16difiestion DE5c21PT10m 07 PecaLEM:
I *
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=
2 .
5 k 2
! s . .
'1"IACIE3 I,.
I status.acTiOu TO DATE. Inctuot*G PE*' y nb. Engineering is :uare of
. .- e * * - - - ,
.,f uo. , and J. A. Lauer, Pro.f. Mgs. know of this prc':-
len. ~T. D. Hurray and 3. R. Beyer, TIco, are also avare of the proble: A.
f utTutt Action RECOMMENDED SY SITE pet 3GENEL: 1. Ii/nb. Engineering should reviev h 2.
Crosby installation; operating and maintenance instructions No. I - 1115, Sect.
with the Crosby vendor to dete:. ine if these instructions vill give,,the prcper Insincering to proyide additiene.1 pilot valve sten adjustnent when actuated. 2.
. recos:sendation and concurrence with action taken.
nE s otui L. .; ,.E,a.L.
7E<b..:: iJ w a.. *'"~% .u l. {~*^'?
" #* * ' "~' ' '.' ' '~
J n. . s on:, . [Mc.
b'"->""S J .L .u h al 1m.c'wJ.3.. rs.x m _
&W f*- =_ _. .
DATE DATE APPROVED ST 5 , 3,g, gy 2 - . - f_ # d l~ //~Jf~?7 .'
. L - M"f l~E~7
, y l / /
cost cAlt:02T ritt0 canci dQ f.c. A. ho* sicair. ett Cli': .
O son. OtutS Ofts ao 5 05- /V//l 0 755 '* h hfl&Inc21
. sitt c:sitErica atri,ar: sc:-t Let .er 4352, ec;/ attached' g ac3g 57: arv n'J.
gI was written to TICo. Instruction :: .ual ! cor- a.;t cc,a,'.1:10,. 3/21./75
= rect and will not' be revised. Additienal adjec .
~,
" ment check provided. Lig. cencurred with Crosby / c3 ,gg.!2 3r g h 2 ATE
~
TEco acticas. F. Rr FalstypM 3/2'/73
! CONFIDENTIAL ,, ,, ,,,, J g ,, ,._.
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, spa 1326 -
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620-0014
. ,7 -
sabcockt.Wilcox 11/2/77 l .
d l
Descriotion of P-oblem:
On 10/13/77, the electro =atic relief valve was tested after the cocpletion
* - ' ! of repairs e.s outlined in S?R E369. Le valve was cycled six times success-fully. On the seventh test cycle the pilot valve did not close.- De ERV- .
was isolated and per sitted to cool down while vaiting for Crosby represents-tives. [
Crosby rep. , k' alt Conroy, arri ed and the pilot valve asse=bly vas re=oved from the main valve. Disasse=bly of the 111ot vsive revealed thnt the pilct valve sten had stuck open due to the cler< tole-ance causing a binding con- '
l dition between the O.D. of the stem and the I. J.
of the pilot valve nozzle.
' Also, a small metal particle was found in the pilot ste=/noz:1? area. Sd-sequent cleasing of the inlet piping to the ERY revealed this same type of metal particles. .
_.s-m he Crosby representative furnishil a detailed drawin_. of the pilot valve r.
stem requiring a diaceter of .37h_ nis was chacged to read .30 diaseter
~.373 * .372 by the Crosby rep., and the stem was modified accordingly by TECo l'.aintenssee under the directics of the Crosby rep. Bis =odification resulted in opening the clears =ce between the stes and the no::le thus eliminating the binding.
De nozzle was also ree=ed out vitb. a reamer the sac: size, no material was removed.
All parts vere cleaned and assembled. De solenoid linkage vas adjusted to drop the adjustment bolt r. ore squarely on the disc aciiuator. In addition, the adjustnent belt was positio'ned to =ove the pilot valve stem off the seat a m W of .125". It had been moving off the seat sc=e .375".
De pilot va.lve was tested without pressure by actuating the solenoid three times. Le valve was tested again twice with 5 or 6 seconds between tests.
Dis was fo31oved by testinC the valve five more times assuring actuatica each time by a one sinute delay between tests. Se valve was tested with a j
pressure of 1100 psig on the seccad and third occasion.
l JEA:sif I ,
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