Summarizes Function of NRC Research Review Group & 780110 Meeting.Review Group Will Develop Plan for Projects for Development of New or Improved Nuclear Power Plant Sys.Draft Rept to Congress Encl.Rept Will Be Reviewed on 780210ML20085A876 |
Person / Time |
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Site: |
Three Mile Island |
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Issue date: |
01/20/1978 |
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From: |
Roy D BABCOCK & WILCOX CO. |
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To: |
Taylor J BABCOCK & WILCOX CO. |
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References |
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TASK-*, TASK-GB GPU-0457, GPU-457, NUDOCS 8307070357 |
Download: ML20085A876 (13) |
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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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THE' 8ABC0CX & WILCOX COMPANY -
POWER GENERATION GROUP To l J. H. Taylor, Manager, Licensing Free D. H. Roy, Manager, Planc. Design (2315) m .. u
.Cust. File No.
or Ret.
Subj. Date
"*' '- cerch R=ic Croup Meeting January'20, 1973 ln , .. . . - .
A research review group has been established by the NRC to implement the requirements of an amendment to the Energy Reorganization Act of 1974 which-directs the Commission to:
. . . develop a long-term plan for proj ects for the .
development of new or improved systems' for nuclear power plants."
This amendment resulted from criticism raised in the Ford Foundacien-sponsored report, " Nuclear Power Issues and Choices", that the current safety research program was deficient in research leading to new and
, improved safety components and systems. The review group is headed by Saul Levine, Director of Nuclear Regulatory Research, and is com-prised of the members shown in Attachment 1. Members of industry, including utilities, various national laboratories, EPRI, consulting firms, intervenor organizacions, other NRC and DOE organizations, etc.,
have been asked to serve as consultants to the review group.
The first meeting of the research review group was held on January 10, 1978, with Saul Levine prea.iding. Attendees are shown in Attachment 2.
Saul Levine opened the meeting with an explanation of the purpose of the review group and a brief description of what he hoped to acco=plish at this first meeting. The first report to Congress is due to be submitted on April 1,1978, with subsequent reports to be filed anntr.Ily
, thereafter in February. The purpose of the review group is to prepare the plan called for by the Congressional amendment to the Energy
..t-. . . . - . . ..~. . Reorganization Act of 1974 and to report progress against the plan in subsequent annual reports. Saul stated that at the first meeting he hoped to generate a list of projects for consideration for inclusion in the report by way of informal dialogue acong the review group =e bers and its consultanta. He stated it 'as not the intention of the Nuclear Regulatory Research office to perform de alled design of ayste=s which might improve reactor safecy, but to perform confirmatory research in advance of design submittals and to perform research which could lead to generacien of conceptual designs for improved safety systems.
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the Nuclear Regulatory Research office would submit th.a t If necesscry, concepts for improved safety systems to DOE with the request detailed designs be developed by that agency and be recuened to theObviously, this NRC for further review NRCand research.
the charter of the research organiz'acion could contribute to ,
even greater instability in the regulatoryThe arena and decrease evenfurt NRC has never and .ather competing power generation systems.
really viewed themselves as simply an agency which promulgatescrit against these er teria; this amendment of systems submitted to itthe wider view that th. NRC would like to se(ms to me to formalize take with respect to its regulatory responsibilities.
l As would be expected, the need for improved ECCS systems was discussed by several NRC personnel and by Dr. Spencer Bush acting consultant. such as a PNLJ of check valves in the' cold legs. Improved containment systems, as vented systems, were mentioned. Identification of innovative means to make
- nuclear power plants less susceptible to sabotage and to mitigate damage which may result frors an act of sabotage were Research into means for understanding systems mentioned by Dr. Bush. interactions and for identifying particularly sensitive or vulnerable
' interfaces was also suggested for inclusion in the report.
There was much discussion, led principally by Steve Hanauer, of work needed to help eliminate Control operatorroom errordesign, prior, during, pattern and after an recognition, i
upset or accident event.
alarm display simplification, automation of actions required toetc., were dis mitigate the event, Engineering Research Program. Dr. Hanauer stated that the most significant finding of the WASH 1400' afterstudy was that greater attention need be paid to operator error as related to reactor safety.
The principal itet.s I emphasited during the discussion were:
i
- 1. Development of criteria and is methods for determining and what incremental
?
Just what an " improvement" benefit to reactor safety any given improvement wou make. In my opinion, this should be a principal item of regulatory research,~since it (a) provides a system-
~
a' tic basis for cost benefit analysis, and (b) is manda-tory before a quantification of acceptable risks can be - --
made. Without these two items, the nuclear power industry will continue to be at the mercy of the regulatory agency, wherein almost any means for improving reactor safety can be mandated without the agency being held accountable '
for its impact.
- 2. I stated that many of the elements related to determina-tion of sub-cooled blowdown loads and otherrealistic loads associ-ated with the LOCA areIinstated need of a more that this was particularly research f ndation.
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f true of j et plume definition, discharge of fluids at high pressure from large diameter pipes, and struc-tural/ fluid interaction. I also mentioned research into means for reducing occupational exposure thru
' innovative design and maintenance features and re-search into the development.of better incore instru-mentation for defining more precisely the nuclear, thermal, and hydraulic state of the core at any given time.
At one point during the discussion, one member of the NRC stated that the review group would be reviewing very carefully and with great interest the safety systems cad criteria that are in use or being considered for use in Germany. With flushed face and rapidly accelerating heartbeat, I rose to my feet to caution those who viewed the German situation with great envy to make certain that they fully understood how and why the German approach to teactor safety had developed as it has. I mentioned that popula . ion < rnsity differences, the different relationship between the licensing t, view body and government, differences in federal versus state licensing responsi-bilities, the lack of any suitable alternative to nuclear power, ,
etc., as important considerations in viewing current Carman safety systems and regulatory practices. Many NRC voices were raised in
' support of German safety requirements and review procedures, and I ,
continued to iterate my view that the approach here in the U.S.
could be and should be conducted in an entirely independent way reactor safety arising from whatever and source, thatforeign ideas or fordomestic, improving 'should be reviewed quantitatively and systematically for benefic versus cost impact using the methods i
and' criteria which I believe the regulatory authority is obligated to generate.
l One gentleman member of the consulting staff stated that a small, but highly influential elem'ent of the anti-nuclear group cannot or will not consider the probabilistic aspects of any given event.
He termed this element the catastrophic group in contrast to the i
' actuarial group. It was his opinion that we should spend rdsearch dollars to design and implement systems which would satisfy this extremist grou With Warren Owen of Duke Power Company,p of nuclear Romano opponents.
Salvatori of Westinghouse, and Bill Corcoran
'of Combustion Engineering nodding in agreement, I stated that "if
_,_. the* viability of this industry depends upon the quieting of _the [
catastrophe-minded anti-nuclear group, I believe I can speak for the Babcock & Wilcox Company in voicing the opinion that we would rather abandon the industr7' than spend one dollar of public money to assuage the extremists. ,
t In su= mary, there were very few innovative ideas not already contained in ERDA, EPRI, or NRC research programs or contained in the list of ACRS generic concerns or already part of the NUREC 0138 listing brought forward at this first meeting of the review group and its consultants. I stated during the meeting that it seemed l co me that there is a conflict of interest in Congress' assigning this task to the NRC. It appears to me that to provide an avenue CONFlDENTIAL
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.6 9 f rather well-defined ll-specified methods in by systems which the NRC or require the use can of force rather we the inclusion in an of inde-nuclear power the design and construction o tems and method:omulgated by the agency the task of reviewing these same sys the U.S. tax pendent way against the safety criteria prIt seems to me 21so that'cou is a conflictCongress payer,with of interest. acting as his agent, h projects with h hile. little Ior of money on nuclear regulatory researcthe improvee:ent in safety is wort w no assurance strongly recocznend that that we aa. through the AIF and through theInsular Af Congressional Cocuaittee on Interior i and to obtain theirpriority researchl tions other appropriate Congressional for our position that one of the highest organ za long the lines of support incremental contribution WASH 1400, for quantitatively k t;o reactorassessing safety. theitems any system modification or addition ma esh duled for February 10, t will be available The second meeting of the review group is sc e19 for review. .
.DHR/ebf \,,
Attachmente cc: (V/ att)
Ja H. Taylor G. E. Kulynych ,
File
. (w/o act) .
R. M. Ball C. W. Pryor C. D. Morgan J. S. Tulenko K. E. Suhrke k' I,. J. Stanek i T. M. Schuler
! J. C. Deddens CONFIDENTIAL qm. G O
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DUTLINE OF REPORT TO U.S. CONGRESS 04 1
STUDY OF LONG-RANGE PLM ON IMPROVED SAFETY SYSTEMS I
- 1. INTRODUCTION Objectives ,
i The FY 1978 Authorization Bill for the U.S. Nuclear Re.gulatory Cocaission includes an amendment to the Energy Reorganization Act of 1974 (42 U.S.C. 5875) by adding a new subsection (f) to
. ,f; Sectfon 205:
I "The Coamission shall develop a long-term plan for
- t
,jI; projects for the development of new or improved safety il systems for nuclear power plants."
,ij .
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The Conference Kepcrt (involving the House Comittee on Interior and
((
I' Insular Affairs and Senats Comittee on Envlionment and Public Werts amplifies the meaning of the legislation change by identifying the j,
I need for the NRC to take the 'inttf ative in the development of i
. improved safety for nuclear power plants and by stating "that l-the basic purpose of this research is the improvement of reactor safety and not the enhancement of the economic attractiveness of
.} .
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nuclear power versus alternat'ive energy sources." It also calls for an annual report from NRC to the Congress by February 1 of i
4
! each year, with the first report due an April 12. 1978.
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d brief The Conference Report notes that the dplan for each should inclu e description of the projects which are proposed, c!.e nee h project, and project, e timetable for icplecentation of eac the cost of the project.
Coor .ination with other involved
' acencies such as COE is encouraged.
i dful In preparing the long-range plan, the Cocnission is als ted f:RC and
~
of the Energy Reorganization Act of 1974, ThewhichEnergy crea t
the background leading to the passage of thisl ac .
s, Reorganization Act specifically created f r research an Office of Nu i
J. Regulatory Research to (1) develop reco::cendat licensing ons o deetoed.necessary for perfqr ance by ntract the Cocnission for N
and related regulatoy functions and (2) engage f mance in or co I
}; research which the Cccuission deems necessary for th i
l-i of its ifcensing and related regulatory funct ons.
HRC's research charter as estabitshed under the Energy i
f Reorganization Act of 1974 encoepasses ' confirm I h rosearch as distinct from "developcental* safety ~
h researc Confirmatory safety research is taken to ifiedmean that res deemed necessary to,provido NRC with an objectively l tory _ , , , v basis for evaluatica of an application cade'to t or it for re judgeent, or to provide a basisjdfor enal a regulatory re policy, or to provide NRC with the' physical t ials.or u gm capability to regulate the use of nuclear pcteer and 9
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i Ir. centrast, developeental safety research is research conducted to evaluate the safety of materials, processes, equipment, etc..
I that would or might be' prnposed by an appifcant for an NRC ifcense, or a possessor of such a Ifce.nse, in support of an
- appitcation for a favorable regulatory judgment.
WIthin these guidelines fiRC has the charter to tfevelop general i -
analytical methods to assess the i.erforance capabf11ty of -
1
, , systems that are related to the safety,of nuclear power plants, reccgnizing that data obtained to verify these methods could also be used in
. D, -
{ the design of improved safety systems. Against this background,
[ the new Congressional requiremnt for the " development of new
, or' improved safety systems" for fiuclear power plants could give rise
,; to some difficulty if the f4RC were to develop design
[;
fcprovements in sufficient detail so they could be incorporated f into plants by designers. Such a course would place the NRC in the difficult position of reviewing and approving as part of its licensing process designs that it trad developed. A simple way td I
solve this problem is for flRC not to create detaffed designs,
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but rather to gather physical data and create analytical models - - -
k I i for the analysis needed as part of the approval of improved I i safety concepts (such a,s vented containment). Such an approach would enable the MRC to evaluate the safety significance of feprovecents without performing the detailed designs. Of course.
in some areas where it might be espe.:f ally useful to have detaffed design perforced, this could be worked out in, coordination with 00E.
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e n Peactor Safety The principal- aim in reactor safety is to prevent undue risk to
- the health and safety of the public from the operation of nuclear I. power facilities. The basic trpreach used to ensure the safety E
of nuclear power plants is to design the plants according to a Il defense-in-depth philosophy, that is, to butid in three levels I
of nuclear safety: (1) design and fabricate the plant for .
i j maxis:uct safety. (2) pmvfde protective systems to monitor and correct off-nor=al conditions, and (3) install engineered safeguard features to mitigate accident consequences. This philosophy is reflected in the design of three separate barriers y
- j to contain racioactive caterial
- (1) fuel cladding, (2) pressuru vessel and piping, and (3) reactor containment, il
!. ; The designs of engineered safeguard features used in the defense-i i j i in-depth philosophy are based primarily on the calculated 4 :
j l consequences of a series of design basis accidents. In its
- i .
l l 1fcensing process, NRC evaluates the safety of nuclear plants s
against these design basis ace' ants, including various system transients and cocponent' failures. The singleifailure criterion ~ ' ' ~
[ is also applied to assure adequate reif ability is achieved for I
L systems 'and components icportant to safety.
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The defense-in-depth concept is embedded in the fiRC regulations 9
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(see. for example. Appendices A. " General Design Criteria for i.
'tuelear Power Plants" and 8. " Quality Assurance Criteria for ;
I I:uclear Power Plants and Fu'el Reprocessing Plants" of 10 CFR i
Part 50) and in the guidance provided by flRC to the nuclear industrw Perhaps more than any other factors, the defense- i
. (
in-depth concept and the conservative approach taken in nuclear l i
power plant designs have been responsible for the good safety I:
record experienced to date. .
! Appveach to Study In approaching the question of how to fsprove ca existing safety. 's f
i U
a logic ~ structure is needed to allow the categortration and >
I
!\ evaluation of suggested improvements. The structure indicated 4, - .? !.
l
. J' . .4 f below suggests itself in that (1) it is organized te identify areas of risk reduction into which specific suggestions can be
!j !
placed and (2) it attempts to list all areas in which improvements '
sight reduce risk. frorovements_
_ategorizatien C of Succested Safety A. Reduce likelihood of accidents due to
- 1. Internal plant failures
- a. ReIfuce likelihood of initiating events (1)Pipebreaks (2) Vessel breaks (3) Transients 4
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' b. Reduce likelihood __of failures of systems designed r
to cope with all above.
- 2. External events
- a. Natural (earthq'akes, tornador., floods)
- b. f!an-made (aircr' aft crashes, turbine missiles, i 1
explosions) j
/ 3. Sabotage f
d B. Reduce probability of large ons uence accidents by reducing j
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the likelihood of reTease of large amounts of airborne f
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( 2. '
SUF!!ARY OF CURRE.:T REACTOR SAFETY RESEARCH l
i l-Chapter 2 will be devoted principally to providing surrary j l background information on ongoing reactor safety research. It } [
will cover the principal areas of NRC research in the (feld of -
water reactor safety as well as summartes of research being I
conducted by reactor vendors (PR), 00E and foreign governments.
The principal topics to be covered will be: ,
- 1. Safety design and protection of the integrity of the reactor
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pressure vessel and piping. -
. . I
- 2. Therr.al-hydraulic tests of hypothetical or design-basis accidents and the effectiveness of engineered safeguard features, ;
- 3. Fuel-red behavicr in hypothetical accidents and associated
! failure limits, .
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- 4. Computer code deve60pment for accurate predictions of the consequences of hypothetical reactor accidents. .*
- 5. Operational safety studies of the adequacy of safety designs.
standards and criteria used in c,perating plants, such as fire protection crite:ria, qualiflcation testing standards and !
reactor operator actions, -
f
- 6. Assesscents of the potential effects of severe natural phenonena f
such as earthquakes, floods, ter idoes, and hurricanes on f
nuclear facilities to aid in determini .g facility safety -
design requirements in these areas, Application of risk assessment methodology to obtain an
'l i 4 improved understanding of 'the risks to the public free -
i l
potential accidents in light water reactor's and fuel cycle
, .i facilities. i i,
f l
- 3. SUGGESTIONS 03 RESEARCH TO IMPROVE REACTOR SAFETY!
{',
Chapter 3 will te devoted to su::carizing a series of documents
- which over the years have recoc= ended various types of research t i
.s on improvements to reactor safety and will also sumarize the '
suggestions for research on improved safety to be made by The c: embers of and corrsultants to the.Research Review Group.
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following set of documents, and others as appropriate, will be l
reviewed to extract and Jumarize appropriate recomendations l .
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- a. ACRS documents , ,
- 1. Letters on react:r safety research
- 2. List of generic items
- 3. Report to Congress on reactor safety research program ;~
- b. ECCS Acceptance Criteria and Heiring Record
- c. Report to the American Physical Society by the Study Group .
on Light-Water Reactor Safety
- d. A Review of Light-Water f!eactor Safety Studies (LSL-5286)
- e. Environmental Quality Laboratory Report (EQL No. 9)
- 4. ASSESSME?iT OF SUGGESTIOf!S FOR RESEARCH Off !PtPROVED SAFETY , j Chapter 4 will contain an assessmant and priority listing of the - '
, I g
suggestions for research on improved safety that are listed in j Chapter 3. Various techniques will be used to perfons these .
assessments. Where appropriate, the potential risk reductions i relative to risks predicted in WASH 1400 will be used. Of I i course, care will have to be taken to ensure the applicability ; .
of. such comparisons and to take into account the uncertainties ,
, t in WASH 1400 modeling. An exam;1e of such coep .rison vould be { {
.. an analysis of risk reductions potentialTy achieveable by the - '
use of vented centainment. On the other hand some suggestions , ,
such as ones appilcable to improvedseismic design might be quite f f
difficult to quantify in terms of potential risk rehetion. Here.
- a rcre judgmental approacn will have to be used. Of course. ;
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estimatesof changes in plant cost.will be made to help provide .
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- t some sort of value/fepact analysis.
- 5. CONCLUSIONS AND RECOMtENDATIONS ~
I This chapter will sumarize the final recomendations of the report g
on those research projects 'which should be undertaken. -
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