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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 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 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 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 ML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel 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 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 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 ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS 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 ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI 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 ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse 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 ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 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 ML20149E7411997-07-16016 July 1997 Notification of 970821 Meeting W/Util in Rockville,Md to Discuss Instrument Drift Study 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 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 ML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel 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 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 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 ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS 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 ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI 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 ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse 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 ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 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 ML20149E7411997-07-16016 July 1997 Notification of 970821 Meeting W/Util in Rockville,Md to Discuss Instrument Drift Study 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 1999-09-29
[Table view] |
Text
- _ _-_______ _
4
. S i THE SAS'C0CK & alLCOX COMPANY ((6[Emli377f0310tN). I f PO'aER GENERATION GROUP g/ 7/p/ ig, g, hgji ,
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From
- 8 R.C. JN. ECCS .GA1.YSIS (2066) d3( ,
File no.
Cu st. f or Ref. ,
P
' Date -
Subj. ,'
4
,' SMMJ. mAK SCENARIOS ?'.AT 2.1979
..-w %
gn. ,
3 Attached are draft writeups on small break scenarios to be used in the l small break cooldown procedure. You are requested to cocument on these writeups and place them in a form suitable for the procedure. The en- N 2
closures are in three parts:
- 1. RCS leaks (non-FZR) with auxiliary feedvater.
- 2. P.CS leaks (non-PZR) without auxiliary feedvar er.
- 3. Smil breaka in pressuriser.
A 1
If you have any questions on these writeups, call either R.C. Jones (X-2066). R.J. Sala (X-2600), or R.m Dunn (X-2138).
.';i 1
RCJ/lc cc E.A. Vomac's 4 i B.M. Dunn R.J. Salm D.F. Hallman N.S. Elliott l
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i i DISCRIFTION OF Sv.U L EZI.U: TRANSIr;T BEHAVIOR
' i 1 ,
y The response of the prisary syste= to a s all breat v1.ll di".~ar great.ly ,
- L I depending on the break size, its location in the systen, operation of the [
$ ?-
? reactor coolant pumps, su=her of ECCS syste=s functioning, and availability of (
t~.1...
secondary side cooling. Figures 1 ar.d 2, plots of RCS pressura and pressurizar y* '
w.-
level histories for various combination of parameters, indicate the vide range "gr r.
of behavior. -
L r h
U CASES VITH AIDCTI.IART TEEDUATER a -
. N i Curves 1 and 2 of Figure 1 show the behsvior.of F.CS pressure to breaks that are large enough in combination with the ECCS to depressurize 3,
the systen to a stable low pressure. ECCS injection easily exceeds core boil-off. Curves 1 and 2 ef Figure 2 show the pressuriser level transier.t. Rapidly
'~
falling pressure causes the het legs to quickly saturate. C 'd les temperature reaches saturation sonevhat later as RC punps coastdown or the RCS depressurizes f.
1 J. '
belov the secondary side saturation pressure. Since these breaks are capable h, t .
of depressurizing t!.e RCS without aid of the stean generators, they are largely insensitive to the availebility of auxiliary feedvster. Operation of the re-
- c. t actor coolant pumps also plays little role in the course of events. Other than T*
verifying that all ESTAS actions have been completed. *he entrator needw to do nothing to bring the systen to a safe stable coadition.
Curve 3 of Figure 1 shows the pressure transient for a break which is
.)
too s=all in combination with the operating HFI to depressurite the RCS. The I
steam generators are being relied upon to remove a portion of core decay heat.
If the reactor coolant pu=ps are not operating, and the pressure has stabilized f.re*-=~'MMq*
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near the seco dary side pressure, RCS pressure cay evesta. ally bes;in falling j again as the decay heat level decreases. If the RC pu=ps are operating, pressure j
4 1
nay, or may not decrease, it could eve =n 21 ty increase to sc=e stable level as h-s the E?I refill and repress =rize the 2CS. The assu=ption for this case is that i
,- r
~j secondary cooling is ~ainemined. Curre 3 of Figure 2 shows pressurizer level t 2 [-
Q W behavior. Curve 6 of Figure 2 shmrs refilling by the EPI. The hot leg tempers- h}.
?1 g' ture quickly falls to the saturated te=perature of the secondary side and controls v j_
] primary systen pressure at s.aturation. The cold leg f:emperature remains slightly 1.
subcooled. If the EPI refill and repressurize the RCS, c' s hot legs can once
= ore become subcooled. The operator needs only to verify ESyAS actions and, if
}0 RC punps have not failed, lexve one ru= sing in each loop.
e i
t 2
Curve 4 of Figure 1 sbcvs the be'.avior of a small break in which the te e r actor coolant purrps have been lost and the break is too s=all in combination ;
.} with the EP1 available to depressuri=e the pri=sry syste z. Although auxiliary feedwater is available, loss of primary sys.te= coolant eventually leads to in-T ..
[
- terruption of circulation around the loop. This is followed by a gradual re-
- pressurization of the primary systen. Although not likely, it is conceivable 2 2 '
that the pri=ary systen could repressurize as high as the pressurizer safety be valvss before the pressure stabi1*ses. This is shown by the dashed line in Figure 4 Once enough inventory has been lost from the primary system to allow >
1- ,
direct stvas condensation 1.s the r6gion of the secas generators adjacent to the secondary side coolant, t':e steam condensation forces a depressurizarfon of E
, the pri=ary systers down to the saturation pressure of the secoc.iary side.
l'l l
Since the cooling capabilities of the secondary side are =eeded to remove n.
! decay heat, pressure vill not fall below that on the secondary side. HPI is sufficient to exceed boil-off in the core, andcondensation in the steam generators -
renoves decay heat energy frc- the systes. The reactor. coolant system is in a ,
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l stable condition and it util re-uf n there until the operator takes further i
q action. The pressurizer level transient is characterized by Curve 3 of Figure l
- 2 during the depressurf r.atiei. sed Curve 4 of Figure 2 dttri
- y, the re~cra.y repre.ssurization phase. The dashed line indicates the icvel behavior if pressure
- is forced up to the pressurizer safety valve setpoint. During this transient, w
- p m
bot leg temperature vill rapidly approach saturation with the initial system W
- 9 depressurization and it vil.1 remain saturated during the vbole transient. Cold
) $
les temperature vill approach saturation as circulation is lost, but may remain slightly subcooled during the repressurization phase of the transient. Once i
direct steam condensation develops in the steam generator, ROS depressurization a
k vill cause the cold les ta=peratures to quickly reach saturation. Cold les f temperatures may once more subcool slightly once the primary systen has stabilized at secondary side pressure. Subsequent filling of the pri=ary system by the EFI may cause temporary icterruption of steam condensation in the stean generator
, as the primary side level rises above the secondary side level. If the de-
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pressurizatiou capability of the break and the 3FI is insufficient to offset decay heat, the prir.ary systen vill once more repressurize until enough RCS i
coolant is lost to allow direct steam condensation in the steam generator. At
, this point the primary system will once again dep tessurize to secondary side 1
preasure. This cyclic behavior will stop once the HF; and break can balance 1
decay heat or the operator takes some a. tion.
]
! Curve 5 of Figure 1 shows the behavior of RCS pressure to a break in which RC ptraps are lost, but v'-ich don not lesd to intarruption of natural circula-tion. The high pressure injection is available and exceeds the leak flow before
/~. the pressurizer has e=ptied. The primary systen es=ains subcooled and natural circulation to the steam generctor removes core decay heat. As Curve 5 of Tigure 2 shows, the pressurizer never er.pties and continues to control primary system pressure.
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3 SAI.L 375.AKS LTmot r ATI.* C r u ATOt 5 There are three basic c. lasses of break respense for small breaks without
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> auxiliary feedvater. These are:
1 l :
- 1. Those breaks capable of relieving all decay heat via the break. ,.
N IN
- 2. Breaks that relieve decay heat .rith bech the EPI injection and via the break. [F x-i h 3. Breaks which do not automatically act= ate t',e HPI and result in f3 system repressurizatica.
+..'
E 3
1 4
The system pressure transients for these breaks are depicted in Tigure 3. L.
- For Class 1. it is seen that the RC system 7tess.
- re decraases rather smoothly o -
,3 "
throughout the transient. For the larger breaks in this class. CFT actuation and 1.PI injection will probably occur. For the s= aller breaks of this class
- I' s only. CFT actuation vill occur. Auxiliary feedwater injection is not necessary for the shert tern stabilization of these breaks.
j Tor Class 2 breaka, the MC pressure vill rapidly reach the ESTAS trip f 1 .
signal 62 to 3 min). With e.he RPIs on, a slev systen depressurization vill f be established coincident with the decrease in cere decay heat. No CFT actua-T tion is expectsd. Auxiliary feedwater is not necessary for the short tera \,
stabilir ation of these breaks.
t Autotatic ESTAS actuation vill not occ*ar fer Class 3 *oreaks. Once the
- . SC second
- .ry side inventory is boiled off, systa=s repressurization vill occur V a
l as the break is not capsble of removing all the f.ecay heat being generated in -
the core. Systes repressurization to the POEr er the pressurizer safety L
valves will occur for snaller breaks in this cla.ss. For the "zero" break t
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d case, repressurization to the POK7 vill occur i= the first 5 sinutes. Operator
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action is required within the first 20 =inutes to ensure core coverage through-out the transient. For the 177-TA lowered-loop plants, this action can be
- either manual actuation of the auxiliary feedwater cystem or the EPI systes.
The establishment of auxiliary feedvater vill rapidly depressurize the a
RCS to the T. STAS actuation pressure, and system pressure vill stabilize at 2 eitber the secondary side SG pressure or at a pressure where the EFI equa.ls W J'
[? the leak rate. ,
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Tor the Davis-Besse plants (raised loop design) operator action is J
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necessary at some time greater than 20 rtinutes (probably 40 ninutes) due to the increased inventory in the loops that is available to drain into the re- ;
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actor vessel. However, due to the low shutoff head on the HPI system, the "
a operator nist establish auxiliary feedwater in order to depressurize the RCS. '
t Pressurizer level response for the first two classes of breaks will be ,
similar to that depicted for Case 1 and 2 breaks discussed in the previous ]
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section. For the Class 3 breaks, pressuriz.er level response vill be as shown '
r I (
in Figure 4 The minious refill time for the pressuriser 1, that for the "zero"
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l break and is shovu on Tigure 4. Af ter initially drawing inventory from the
.c
- pressurizer, the system pressurization vill cause the pressurizer level to 1 '
increase, pessibly to full pressurizer level. Once the operator action to re-i store auxiliary feedwater has been taken, the system depressurizatica vill result in outsurge from the pressurizar, probably resulting in a couplete loss
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, of pressurizer level. For the smaller breaks of Class 3 which results in a system repressurization following the actuation of the !IPI systen, pressuriser (J
level vill increase and then stabilize. -
j t'ithout auxiliary feedvater, both the hot les and cold icg te=peratures vill saturate early in the transient a d, for the Class 1 and 2 breaks, vill remain saturated. For the Class 3 breaks, once auxiliary feedwater is established.
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i che cold leg te=peratures vill rapidly decrease to approxi=ately the saturation .
I g temperature corresponding to the SG secondary side pressure and vill re=aia b
$ there throughout the re=ainder of the transient. Het leg te=peratures will -
I i re=ain saturated throughout the event.
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Sv.AI.I. 3RFJJtS T.T P!JESSGIZIR i
9- The systen pressure transient for a < mil brea in the pressurizer vill be.have in a sinf1=r ranner to that previously discussed. The in.icM d= pres- ~
surization, bovever, vill be core rapid due to scez= relief out the break. ;-
a y) The pressurizer level response for these accidents will initially behave '
4 like a verf small break without auxiliary feedvater. As shout on Yigure 5. an i 2
initial rise in pressurizer level vill occur doe to the pressure reduction in y.
3
' the pressurizer and the subsequent insurge into the pressurizer from the RCS.
i once the reactor tripw. system contraction results in a decreasing level in 1
the pressurizer. Tlashing vill ultimately occur in the hot leg piping causing e an insurge into the pressurizer and vill rapidly fill the pressurizer. For ,
the rer.ainder of the transient, the pressurizer will renzin solid. Towards .
the later stages of the transient.' the pressurizer vill be filled by a two-phase nizture. However, the indicated level vill show that the pressuriser ,
is only partially full.
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