|
---|
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] Category:RESEARCH INFORMATION LETTER
MONTHYEARML20133G5911985-10-0909 October 1985 Research Info Ltr 144, Effect of Hydrogen Gas on Downcomer Fluid Temps During TMI Accident. Forwards Cooldown Aspects of TMI-2 Accident, Based on Tg Theofanous Study of Fluid Mixing in Thermally Stratified Flows 1985-10-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
[Table view] |
Text
K s
gsa n o EES Files y4 ?, UNITED STATES c,g , g.y yg.y/f
- { ,g NUCLEAR REGULATORY COMM lS$10!f 7, /E W ASHINGTON, D. C. 20555 s
y p~
i v va.
ZPE
yy __
- o. ~
L
. a :o . ~~
~
i MEMORANDUM FOR: Harold R. Denton, Director
>? r W. '
Office of Nuclear Reactor Regulat- on
~
, ;-013 fiE~s7T& I FROM: Robert B. Minogue, Director R%m :!a K Office of Nuclear Regulatory Research-
SUBJECT:
RESEARCH INFORMATION LETTER N0. 144, "THE EFFECT OF HYDR 0 GEN GAS ON 00WNCOMER FLUID TEMPERATURES DURING THE TMI ACCIDENT" This memorandum transmits research results on the effect of hydrogen gas on the downcomer fluid temperatures during the accident at Three Mile Island (TMI).
This work was performed by Professor T. G. Theofanous of Purdue University, as part of a study of fluid mixing in thermally stratified flows. Earlier models developed through this fluid mixing research program have received extensive use in NRR's pressurized thermal shock (PTS) study.
The purpose of the research described herein has been to predict the downcomer fluid temperatures for the portion of the TMI accident during which high pressure injection (HPI) flow was actuated. The Rogovin Report (Volume 2, Part 2) states that HPI actuation occurred at 200 minutes into the accident while the primary system pressure was in excess of 1000 psia. Since this was a high pressure transient with the potential for achieving low downcomer fluid temperatures, this research may interest you from a PTS standpoint.
Shortly after the TMI accident, Babcock and Wilcox (B&W) addressed this same subject. These early analyses examined HPI fluid flow into a steam filled cold leg. The presence of steam in the cold leg was attributed to vent valve fluctuations which expose the downcomer region to the steam filled upper plenum. These vent valves open when the primary system coolant approaches stagnant conditions. Such conditions are thought to have existed when HPI flow was initiated during the TMI accident. Steam condensation on the cold HPI fluid served to warm the fluid before reaching the downcomer. As a result, the B&W analyses predicted a minimum downcomer fluid temperature of approximately ;
280 F.
During the TMI accident, large quantities of hydrogen were produced when the l zircaloy cladding, which encased the fuel, reacted with the surrounding water vapor. As a result, hydrogen may have been present in the loops during the 3 period of HPI actuation. The new analysis, presented as an enclosure to this memorandum, differs from the earlier B&W analyses in that it examines HPI fluid i flow into a cold leg filled with both steam and hydrogen. It shows that the
. presence of hydrogen inhibits the heating of the HPI fluid prior to entering i the downcomer region. As steam condenses on the cold HPI flow, a low pressure l region is created in the cold leg and upper downcomer. This low pressure region induces an increased flow of steam and hydrogen through the vent valves.
As the steam condenses, it warms the HPI fluid. However, the hydrogen does not condense and its concentration increases with time. This buildup of hydrogen 8510160039 DR 851009 p ADOCK 05000320 !
PDR l
8 05 Harold R. Denton 1 in the cold leg ,orevents further steam condensation on the HPI fluid. As a result, this beneficial warming mechanism is shut off. Because the actual conditions (volumes present, timing of events, lower plenum obstructions) during the TMI accident have not been definitively established, Professor Theofanous has performed parametric analyses. His results indicate that the downcomer fluid temperatures may have been less than 200*F. These analyses also indicate that certain sections of the reactor vessel may have been in direct contact with HPI fluid having temperatures of less tnan 100 F because of fluid deflection off of the thermal shield support clips.
It is recommended that the Office of Nuclear Reactor Regulation (NRR) review the effect of this new research on current activities related to severe accident sequences. Additional studies in the area of thermal fluid mixing in the presence of noncondensible gases are being planned. These studies will be coordinated with your staff. Any questions concerning the enclosed study should be directed to Jose Reyes (42-74422).
I d 91 4' Robert B. Minogue, D rector Office of Nuclear Regulatory Research
Enclosure:
"The Cooldown Aspects of the TMI-2 Accident, "dtd 08/85 l
1 I
l 9
i l
- s. <.
Distribution (w/o encl)
Subject Cnron
, Cir Branch R/F RBMinogue DFRoss QCT9 N OEBassett WMMorrison LMShotkin NZuber WDBeckner MEMORANDP4 FOR: Harold R. Denton, Director JNReyes Office of Nuclear Reactor Regulation JNReyes R/F F0dar FROM: Robert B. Minogue, Director Office of Nuclear Regulatory Research
SUBJECT:
RESEARCH INFORMATION LETTER N0.144, "THE EFFECT OF HYDR 0 GEN GAS ON 00WNCOMER FLUID TEMPERATURES DURING THE TMI ACCIDENT" This memorandum transmits research results on the effect of hydrogen gas on the downcomer fluid temperatures during the accident at Three Mile Island (TMI).
This work was performed by Professor T. G. Theofanous of Purdue University, as part of a study of fluid mixing in thermally stratified flows. Earlier models developed through this fluid mixing research program have received extensive use in NRR's pressurized thermal shock (PTS) study.
The purpose of the research described herein has been to predict the downcomer fluid temperatures for the portion of the TMI accident during which high pressure injection (HPI) flow was actuated. The Rogovin Report (Volume 2, Part 2) states that HPI actuation occurred at 200 minutes into the accident while the primary system pressure was in excess of 1000 psia. Since this was a high pressure transient with the potential for achieving low downcomer fluid temperatures, this research may interest you from a PTS standpoint.
Shortly after the TMI accident, Babcock and Wilcox (B&W) addressed this same subject. These early analyses examined HPI fluid flow into a steam filled cold leg. The presence of steam in the cold leg was attributed to vent valve fluctuations which expose the downcomer region to the steam filled upper plenum. These vent valves open when the primary system coolant approaches stagnant conditions. Such conditions are thought to have existed when HPI flow was initiated during the TMI accident. Steam condensation on the cold HPI fluid served to warm the fluid before reaching the downcomer. As a result, the B&W analyses predicted a minimum downcomer fluid temperature of approximately 280 F.
During the TMI accident, large quantities of hydrogen were produced w'1en the zircaloy cladding, which encased the fuel, reacted with the surrounding water vapor. As a result, hydrogen may have been present in the loops during the period of HPI actuation. The new analysis, presented as an enclosure to this memorandum, differs from the earlier B&W analyses in that it examines HPI fluid flow into a cold leg filled with both steam and hydrogen. It shows that the presence of hydrogen inhibits the heating of the HPI fluid prior to entering the downcomer region. As steam condenses on the cold HPI flow, a low pressure region is created in the cold leg and upper downcomer. This low pressure region induces an increased flow of steam and hydrogen through the vent valves.
As the steam condenses, it warms the HPI fluid. However, the hydrogen does not condense and its concentration increases with time. This buildup of hydrogen i
- - , , - . . - n .- , - - - -,rn-
(
eL 9
Harold R. Denton 9 1985 in the cold leg prevents further steam condensation on the HPI fluid. As a result, this beneficial warming mechanism is shut off. Because the actual conditions (volumes present, timing of events, lower plenum obstructions) during the TMI accident have not been definitively e,stablished, Professor Theofanous has performed parametric analyses. His results indicate that the downcomer fluid temperatures may have been less than 200'F. These analyses also indicate that certain sections of the reactor vessel may have been in direct contact with HPI fluid having temperatures of less than 100 F !
because of fluid deflection off of the thermal shield support clips. '
1 I It is recommended that the Office of Nuclear Reactor Regulation (NRR) review the effect of this new research on current activities related to severe accident sequences. Additional studies in the area of thermal fluid mixing in the presence of noncondensible gases are being planned. These studies will be coordinated with your staff. Any questions concerning the enclosed study should be directed to Jose Reyes (42-74422).
I Robert B. Minogue, Director Office of Nuclear Regulatory Research
Enclosure:
"The Cooldown Aspects of the TMI-2 Accident, "dtd 08/85 tN k)bb d Af :RSRB DAE :RSRB DAE:RSRB DAE :RSRB R :D R E JMReyes:bsd WDBeckner NZuber Pt- LMShotkin WM rison OEBassett 09/26/85 $0/3/85 0 / t /85 09/SI/85 09 /85 / jf 5 RES RE /I _ _ _ _ . . _ . .
DFRoss RB%ogue {
~
09/ /85 g7,/85 EF" _ F_il ejl
- utj oct Filo No. 2//2 f-2//b
, . _-- i 1
' T ;;;No. --
n nrch Roquc0t No. -
r 1:o . _ _ --
., 23 30. _ ..
D W.:t50. --
! ! .a u l int'No. _
' t. M r k_ d /
,e: , s o.p.:3
.. { -
l l
._ ,_ _ _ _ _ . . _ _ _ , . - . . _ _ -, _ _ _ . - _ _ _ _ . __ _ _ _ _ - . _ _ _ _ _ . _ _ . . _ _ _ _ , _ _