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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] |
Text
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April 21, 1980 .
i l Note to James P. Murray, OELD l
TMI INVESTIGATION ,
The attached set of 45 questions was given to Stello and Moseley at their meet-ing with llenry Meyers of Udall's staff last Friday, April 18, 1980. With one or two minor exceptions, the questions duplicate, and add to, those submitted by Meyers in his draft of April 3,1980. (I have noted the numbers of the questions from the previous set on the current one where they correspond.)
l l Considering the apparent confusion about the direction of the IE inquiry, ! !
! highly recommend that you and I meet with Stollo and/or Moseley to sound them l l out as to their perception of the scope of the investigation. At the time of l this writing, there is nothing to show that the IE TMI task force is doing !
anything more than a reevaluation of the three items of noncompliance omitted 1 from the Met-Ed civil penalty package. I feel we owe it to our clients to !
suggest they shape this investigation as a response to the Udall questions. l l 4 m ( ;
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{ ' Richard G. Bachmann '-~ i Attorney i Rulemaking and Enforcement Division !
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- 1. At what time and to what extent were (1) Gary Miller, (2) off-site senior officials of Metropolitan Edison and/or General Public Utilities and (3) NRC officials informed that for a period of approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 18 minutes primary
"*" coolant had been lost via the open PORV and letdown system '
4 and that during this period high pressure injection had been throttled?
4*** 2. On March 28, what efforts were made prior to 9:00 a.m. to determine the amount of primary system inventory loss prior to 6:20 a.m.? - <
. e u. ' 3. l What was the rationale for initiating high pressure (See Kemeny, TATF injection at approximately 7:19 a.m.
Vol. 1, p. 113) throttling it at approximately 7:37 a.m.,
and initiating sustained flow at approximately 8:26 a.m.?
.h. ,I Which of the TMI supervisors present in the control room on March 28 believed that day that the core had been uncovered for some portion of the period between 6:00 a.m. and 9:00 a.m.?
Which between 9:00 a.m. and 8:00 p.m.?
- 5. Was a record kept of data indicated by the extended scale readout device connected to the hot leg RTD7 (See E&E, TMI-2, <
- p. 297.)
- 6. What interpretation ,was assigned to the rapid hot leg temperature increase that occurred following shutdown of the reactor coolant pumps and which was recorded on a multipoint recorder located in the control room?
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- 7. 'Which of the supervisors who observ.ed the temperatures indicating superheated conditions in the TMI primary system
."- believed that these temperatures did not necessarily mean the core was or had been uncovered? To the extent that the supervisors did not believe the core was or had been uncovered how did such supervisors explain such high temperatures?
8.' Did Ivan Porter direct the technicians to take a second ,
set of thermocouple readings using a digital volt meter? <
- 9. ' Did the technicians inform Ivan porter of all or part of the results of the second set of thermocouple readings; e.g.
the set made using the digital volt meter?
- 10. What did.Ivan Porter inform Gary Miller as to the reliability of measuromonts indicating temperatures in excess of 2000 degroos?
31, Did Gary Miller believo prior to 10:00 a.m. on March 28 that in-coro temperatures might havo boon 2500 degroos or higher? (Sco I&E Tape 159, p. 51-52.)
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- 12. What inference did Gary Miller draw from the fact that the in-core thermocouples might have gotten sufficiently hot, possibly hot enough that new junctions were formed, but in any case hot enough that their calibration would not be reliable? Did Gary
, Miller recognize that temperatures of sufficient magnitude to destroy the thermocouples would imply at a minimum that .
the core was uncovered? Did Gary Miller recognize that temperatures of sufficient magnitude to destroy the thermocouples might imply existence of a chemical reaction between the steam and zirconium cladding?
! ***= 13.l When Gary Miller said that the incores were hot enough that they sdared him, that the direct measurements told him
, why the computer was off scale at 700 degrees, and that he knew "we were superheated and all that sort of thing", was he nne. g stating that core temperatures, in his view, were or had l been in excess of saturation temperature? In making this statement was he confirming that he believed the core was or has been uncovered? If he did not believe superheated temperatures were synonymous with core uncovery , what did he believe to be the source of such temperatures.
14.l Ivan Porter told the I&E investogators that he was afraid the thermocouple measurements (e.g. indicating temperatures lu excess of 2000 degrees) were real. How is this statement
, to be reconciled with others modo by Porter to the effect I
that ho discounted these moacuromonts?
Which of the TMI suporvisors present on March 28 were aware 15.' on March 28 of direct measurements of the in-core thermocouplc voltagos?
- 16. During the period March 28 through May 7 what happened
'-~"4 to thethe with sheet on which digital the March volt meter were28 in-core measurements mado recorded?
17* khich of the TMI supervisors proson't on March 28 were aware
.. . on March 28 of the in-core thermocouple data printed by the computer at 8:34 a.m., 8:47 a.m., 11:10 a.m., 12:40 p.m.,
4:11 p.m., 6:30 p.m., 7:59 p.m., 8:56 p.m., and 9:56 p.m.?
How was this data interproted?
- 18. t Was Gary Miller or any other TMI supervisor aware of Mr. Flint's monitoring the in-core thermocouples during the day on March 287
- 19. On March 28 to whom did John Flint report with regard to in-coro thormocouple or other data that he observed on that day? .
- 20. On March 28, did any employees of Motropolitan Edison or Gonoral Public Utilition mako calculations as to the extent of fuel failure based on data from the domo monitor or other instrumonts? Was any such analysis provided to the NRC7 c.: ;
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- 21. I On March 28, did TMI personnel monitor the recorders which j displayed containment building temperatures? If so, what interpretation was assigned to the temperature increase that occurred approximately coincident with the reactor building pressure pulso at about 1:50 p.m.?
- 22. lOnMarch28,didTMIpersonnelmonitortheprinterthat displayed the alarms received at about 1:50 p.m.? If so, what-interpretation was assigned to these alarms?
23.l What were the circumstances leading to recording of the
""**d 1:50 p.m. reactor building pressure pulse as 4 psi on one log and about 5 psi on another? .
24.! Was Mr. Frederick in the control room at approximately 1:50 p.m. on March 28 at the time of occurrence of the reactor building pressure pulse and related events?
25.l Uhich of the TMI supervisors present on March 28 was aware of the following which occurred at approximately 1:50 p.m.:
pressure pulse, actuation of containment sprays, increase in containment temperaturos, negatovo pressure pulsos on instruments that used containment prossure as a reference, and subsequent alarm print out.
Which of the supervisors present on March 28 were aware 26.
prior to that day that actuation of the containment sprays required detection of a pressuro pulso of at least 28 pri by at least 2 pressure sensors?
- 27. Was Gary Millor informed of the 1:50 p.m. pressure pulse and associated actuation of the containment sprays?
--og, Was Mr. Illjos informod of the pressuro pulse after pg,iving arr in the TMI control room on the afternoon of March 28? Did Mr. Illjos discuss with others in the control room on March 28 the possibility that a hydrogon explosion had occurred on that day? If such discussions did not occur on March 28, on what day and approximately at what hour did they occur?
- 29. Which TMI omployous were instructed that they should not start equipment in the reactor building apparently out of concern that such action might produce an electrical discharge that would causo an explosion? Who issued such instructions? On what day wore such instructions issuo d?
What reconcilation can be mado betwoon Mr. Chwantyk's rocollection that he was not in the shift supervisor's office on March 28 and Ross' contrary rocollection?
- 30. Who lnotructed Mr. Chwastyk to establish a bubblo in the pressurizer which ho tried to do somotimo after 2:00 p.m.
during which offort the pressurizar block valvo and/or PORV was closed at approximately 3:10 p.m.?
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- 31. With whom did Gary Miller conduct telephone conversations during the period when he was at the Lt. Governor's office on the afternoon of March 28? What was the substance of such conversations?
- 32. What was the. cubstance of the telephone discussion between-Gary Miller and Lt. Governor Scranton that occurred at approximately 9:00 a.m. on March 28? Did Af/#N M/c' m.
Scranton that a general emergency had been declared and
% what was the significance of a general emergency?
- 33. [Whatwasthesubstanceofthediscussionthattookplace when Lt. Governor Scranton was briefed by Messers Herbein and Miller beginning at approximately 2:30 p.m. on March 28?
- 34. l With whom did Mr. Dieckamp confer prior to drafting his statement in a May 9, 1979 mailgram to Mr. Udall that: "There is no evidence that anyone interpreted the ' pressure spike' and the spray initiation.in terms of reactor core damage at the time of the spike nor that anyone withheld any information? "
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- 35. Did Mr. Dieckamp's failure to correct the foregoing erroneous statement in the mailgram sent to Mr. Udall and various NRC officials constitute a violation of any explicit or implicit NRC regulations.or licensing conditions?
- 36. Which of the following would have been required on March 28 at TMI-2 by explicit or implicit NRC regulations or licensing conditions:
- calculation of primary coolant loss.
- Monitoring and interpretation of incore thermocouple data.
- Monitoring and interprontion of multi-point recorder dat-indicating hot-leg temperatures.
- Monitoring and interpretation of chart recorder indicating roactor building temperatures.
- Monitoring and interpretation of alarm and utility printer printouts.
- Calculation of fuol damago based on contaiment '
f building radiation measurements and other data.
- 37. What violations of Nhc regulations or licensing conditions may have occurred as a result of the failure to take any or all of tho actions listod in the provious question?
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- 38. The sheet on which the digital voltmeter measurements of incore thermocouple voltages were recorded was not made available to the NRC until approximately May 7 or later.
Did the failure to provide this data to the NRC in a more timely fashion constitute a violation of explicit or implicit NRC regulations or licensing conditions?
- 35.
- Is there any indication that data recorded in the control room on March 28 was lost or destroyed.before it M=9 examised- by Jamany -etM-f-or-NRC N i estigators? What kinds of datufhan1" 4 0. . Did the incorrect recording in TMI-2-logs of the magnitude of the pressure pulse (i.e. 4 psi and approximately 5 psi instead "M '
of 28 psi) constitute a violation of explicit or implicit NRC regulations or licensing conditions?
- 41. If Mr. Chwastyk sough ~n the afternoon of March 28 to establish a bubble in th pressurizer without receiving
~
permission from the tation manager or other authority designated by the otation manager,.would such an action constitute aj io'ation l by Mr. Chwastyk of any explicit or implicit JUIC regulation or licensing condition?
/
4 2. Uhre ir. Miller and/or other Metropolitan Edison officials obliged by explicit or implicit ~URC regulations or licensing conditions to report on March 28, any or all of the following to State and/or Federal officials:
-- loss of coolant via open PORV and letdown system and throttled high pressure injection between 4:00 a.m.
- A.,
and approximately 6:20 a.m.
-- incore thermocouple data indicating temperatures
- in excess of 2000 degrees F.; .
-- computer print-outs of incore thermocouple voltages indicating presence of superheated conditions (and partial core uncovery);
-- hot-leg temperatures indicative of superheated conditions prevailing for most of the periq3s between 6:00 a.m. and 8:00 a.m.;
-- the pressure pulse recording and other manifestations of a hydrogen detonation in the containment at 1:50 p.m.;
-- tha't the reactor was being cooled via a process not described in the plant's operating procedures or one in which the operators were schooled; e.g. an event not analyzed in the TMI-2 FSAR, and
-- uncertainties during the day as to whether the
< 7 core was uncovered?
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- 43. Did the failure of Metropolitan Edison officials to report any.of the foregoing in a timely fashion constitute a' violation of requirements imposed explicitly or implicitly by NRC regulations and/or licensing conditions?
44, To what extent has Metropolitan Edison and/or General Public
- Utilities conducted-an inquiry into the causes of the failure of Messers Herbein and/or Miller to fully inform their k superiors as to conditions at Three Mile Island Unit 2 on March 28? I
~M ~
45.1 Does any failure of Metropolitan Edison and/or General Public Utilities to conduct any such inquiry as mentioned above constitute a violation of requirement imposed explicitly or c '.;
implicitly by NRC regulations and/or licensing conditions?
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