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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] |
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i *
- aeg%, UNITED STATES Enclosure 17 8 o NUCLEAR REGULATORY COMMISSION l E j casenwaroN, C. C. 30858 i
l
(*.,...,/ August 27, 1985 s
MEMORANDUM _FOR: Harold R. Denton, Director ~ ~
_ Office of Nuclear Reactor Regulation
~
FROM: William T. Russell, Acting Director Division of Human Factors Safety, NRR ,
SUBJECT:
RESULTS OF JOINT OI/NRR INTERVIEW WITH LYNN 0. WRIGHT
Reference:
- 1. Memorandum from S. J. Chilk (SECY) to 8. B. Hayes (01) and W. J. Dircks (EDO) dated April 2,1984
Subject:
Staff Requirements-Discussion of Pending Investigation-
, TMI
- 2. Memorandum from H. R. Denton (NRR) to B. 8. Hayes (01) dated May 3, 1984
Subject:
NRR Review of 01 ,,
Investigative Materials Concerning Hartman Allegations of Falsification of Leak Rate Data at TMI, Unit 2
- 3. Memorandum from W. T. Russell (DHFS) to H. R. Denton (NRR) dated December 14, 1984,
Subject:
Results of Joint DI/NRR Investigation and Evaluation of Dennis I. Olson O 4. Memorandum from W. T. Russell (DHFS) to H. R. Denton (NRR) dated January 4, 1985.
Subject:
Results of Joint 01/NRR Interview with Mark S. Coleman 5.MemorandumfromW.T. Russell (DHFS)toH.R.Denton (NRR)datedJanuary 24, 1965
Subject:
Follow-up Action on Additional TMI-2 Operators The purpose of this memorandum is to document the results of the March 27, .,
1985 joint 01/NRR interview with Mr. Lynn 0. Wright. The interview with Mr. j Wright was conducted in order to obtain additional background information on ,
reactor coolant system (RCS) leak rate surveillance testing practices at l TMI-2 during the period September 30, 1978 through the date of the accident. 1 March 28, 1979. During that time frame, Mr. Wright was a licensed Control l Room Operator (CRO) at TMI-2 assigned to Shift "D." Mr. Wright is currently self-employed and is no longer in the nuclear industry.
NOTE: This memorandum and enclosure discuss information which is the subject of an ongoing 01 investigation. This memorandum and enclosure may not be disseminated outside the NRC without coordination with NRR and the permission of the EDO or the Director 01. Internal access and distr 7bution should be on a "need to know" basis.
O .
B605270211 860516 gff PDR P
ADOCK 05000320
. PDR
~
i Harold R. Denton August 27, 1985 1 l-I
. Background i As a resul.t of a Comission meeting on March 23, 1984, NRR was directed by Reference 1 to review OI investigative materials concerning falsification of
{ RCS leak Pate surveillance tests at TMI-2 and refer back to 01 those matters s j which required further investigation. The results of NRR's review was - '
4 provided 10. Reference 2. The review determined that follow-up investigation j by 01 and further evaluation by NRR was needed in the case of seven licensed
'i operators. Mr. Dennis I. Olson, currently a Senior Reactor Operator (SRO) at -.
Waterford 3, was one of the seven individuals identified as needing i additional investigation and evaluation. Mr. Olson was interviewed under l oath in New Orleans, Louisiana by OI/NRR on November 15, 1984. During the
- interview, many of the statements made by Mr. Olson did not appear credible in light of the technical evaluation of Mr. 01 son's leak rate surveillance tests and statements made in 1980 by his former shiftmate Mr. Mark S. Coleman i
Mr. Coleman was interviewed again on the subject by OI/NRR on December 14, 1984 in order to gain additional evidence that would either support of refute
~
the statements made by Mr. Olson. The results of the investigation and evaluation of Mr. Olson and the results of the interview with Mr. Coleman were provided as References 3 and 4. respectively.
4 i Because of information learned during the on-going investigation, Reference 5
! expanded the list of former operators to be investigated and evaluated from seven to ten. One of the individuals added was the former Shift Foreman of Shift "D," Mr. Adam W. Miller. Mr. Miller is currently the Manager, Plant j Operations THI-2.
t Because of the conflicting testimony presented by Messrs. Olson and Coleman l and because of the need to investigate and evaluate Mr. Miller, 01/NRR 1 determined that interviewing Mr. Wright would provide additional background j information on the leak rate surveillance testing practices of Shift "D."
Past Involvement in TMI-2 Leak Rate Testing Irregularities ~
[
l On March 27, 1985, a joint 01/NRR interview with Mr. Wright was held in the
! law offices of Killian and Gephart, Harrisburg, Pennsylvania. The interview l was conducted under oath and in the presence of Mr. Wright's personal
! attorneys. The interview was conducted by Mr. Keith Christopher, Director, j Office of Investigations, Region I and Mr. Robert Capra, currently on detail i to DHFS/NRR.
I
- A complete sumary of Mr. Wright's interview is contained in the enclosed 3 memorandum from R. Capra to me dated August 27, 1985
Subject:
Sumary of l Jo. int OI/NRR Interview with Lynn 0. Wright. Capra's memorandum also contains
- a copy of the transcript of Mr. Wright's interview and a copy of NRR's
- evaluation of TMI-2 leak rate tests performed during the period September 30, 1978 through March 28, 1979. The following key points were brought out by
{ Mr. Wright during his interview:
j . 1.. Mr. Wright had little faith in the RCS leak rate test calculations which wer.e ILerformed to show compliance with the technical specifications. He believed the leak rate test results were erratic and provided results that were meaningless and did not reflect true plant leakage.
! 2. While the TMI-2 Technical Specifications required a leak rate j surveillance test to be perfomed at least on'ce every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, it was common practice to run leak rate tests several times per shift until an j '
i .
- . .- _ -.- - -.s- - -.- -. --. -
Harold R. Denton August 27, 1985
! acceptable result was obtained. The acceptable tests were retained to show compliance with the technical specifications and the unacceptable 1 tetts'were thrown away. Tests were thrown away with the knowledge and/or
! consent of his Shift Foreman and Shift Supervisor. -
1 l 3. Acdording to Mr. Wright, no changes were made in leak rate testing
! practfces following the October 18, 1978 incident that resulted in the _.
! generation of LER 78-62/1T. Mr. Wright stated that at some point
- operators were told to retain all leak rate tests; however, that policy
! was discontinued after a short period of time and he did not know if that
! guidance was associated with the October 1978 incident.
l 4. Contrary to the commitment contained in the narrative of LER 78-62/1T, Mr. Wright was not instructed to enter the action statement of the
- technical specification when leak rate test results exceeded the limiting l condition for operation.
l S. Mr. Wright stated that prior to the accident, he was not aware that i hydrogen additions to the makeup tank (HUT) during the Tast few minutes !
! bf the test could influence MUT level indication and and consequently leak rate test results.
I ~
- 6. Mr. Wright stated that on occasion he did add hydrogen to the MUT near the end of a leak rate test; however, the purpose of these additions was to establish the same overpressure in the MUT at the end of the test as j was present at the start of the test. Mr. Wright said he believed this i
' would minimize instrumentation errors. He stated that he did not add
- hydrogen in order to improperly manipulate leak rate test results.
1 1 7. Mr. Wright stated that prior to the accident, he was not aware that adding water to the RCS during the last few minutes oT'a leak rate test j could produce the same effect on leak rate test results as adding j hydrogen to the MUT.
> 8. Mr. Wright stated that on occasion he did add water to the RCS during the l last few minutes of a leak rate test; however, the purpose of these l additions was to establish the same level.in the MUT at the end of the j test as was present at the start of the test. Mr. Wright said he i believed this would minimize instrumentation errors. He stated that he ,
j did not make these water additions in crder to improperly manipulate leak i rate test results. Note: While Mr. Wright provided a reason for the water j additions, he could not' provide a reason why the amount of water included i
- in the calculation was less than the amount indicated on the MUT strip
! chart recorder.
i 9. Mr. Wright stated operators felt pressure to get good leak rate test results in order to keep the plant operating and that the pressure !
increased the closer they came to the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit. Despite the l pressure, Mr. Wright stated that he was never directed by his supervisors
= to.in}_entionallymanipulateleakratetestresults. ;
i
- 10. Mr. Wright stated that he had no knowledge of any operators.. including ,
either Olson or Coleman, falsifying leak rate tests by any means I including: unrecorded or underrecorded water additions to the RCS, j i hydrogen additions to the MUT or taking advantage of MUT level ,
transmitter instrumentation errors. Except for the unreliability of the '
test, Mr. Wright believed that all leak rate tests were performed l
- properly. l
Harold R. Denton August 27, 1985 l Conclusions All three CRO's on Shift "D" (Olson, Coleman and Wright) have been
. interviewed by 01/NRR. While their testimony is consistent regarding certain ,
. aspects ~of leak rate test practices on their shift, they are significantly
{ differentwith regarding to their personal knowledge of or participation in .. .
leak rate test manipulation.
During Mr. 01 son's testimony, he stated that following the October 18, 1978 incident, he was advised of the proper interpretation of the technical specifications and that he never threw away unacceptable leak rate tests following that incident. He stated he would staple the bad leak rate test sheets to the good test and turn the package into his Shift Foreman. Mr.
Olson's testimony regarding technical specification interpretation and the
)l i
discarding of test results greater than 1 gpm conflicts with the testimony provided by Messrs. Coleman and Wright, both of whom agree that no revised j interpretation of the technical specifications was given to the operators on j their shift and that leak rate surveillance tests exceeding the limits of the technical specifications continued to be discarded up through the date of the accident.
The testimony of Messrs. Olson and Wright regarding hydrogen additions j conflict with that of Mr. Coleman. Both Olson and Wright stated that they i were not aware prior to the accident that hydrogen additions to the MUT could ,
! sffect MUT level indication and consequently leak rate test results. Mr.
] t'oleman stated that it was consnon knowledge among CRO's that hydrogen
! additions could alter MUT level and that he had mentioned the phenomenon to
! Mr. Olson on at least one occasion. Mr. Coleman testified that he personally added hydrogen for the purpose of altering leak rate test results and that while he could not recall ever seeing Mr. Olson add hydrogen for that purpose, he found-it hard to believe that any of the operators did not know j; that this was occurring. Mr. Wright testified that he had intentionally 1 added hydrogen during leak rate tests; however, he stated his purpose was to j try and establish the same hydrogen overpressure in the MUT at the beginning
- and end of the test in order to minimize inaccuracies caused by
, instrumentation errors. The NRR evaluation of leak rate tests which were
! conducted during the period under investigation identified only one test, j performed by Shift "D" personnel, during which hydrogen was added. Based
! upon the admissions of Coleman and Wright that they did add hydrogen during
! leak rate tests, several additional tests should have been identified; r however, because of the unpredictability of MUT level response to a hydrogen 4 addition and the fact that the majority of leak rate tests were not retained, -
the evaluation can not provide additional evidence to resolve these i conflicts.
i
{ The testimony of Messrs. Olson and Wright regarding underrecorded water additions to the RCS during the last few minutes of a leak rate tests were
- also in conflict with that of Mr. Coleman. Mr. Coleman stated that he was i aware that adding water to the RCS during the last few minutes of a leak rate
] test could produce the same effect on leak rate test results as adding c hydrogen to the MUT. Mr. Coleman stated that he used this method to j manipulate leak rate test results during the last two months before the .
j accident since hydrogen could no longer be added to the MUT remotely from the
- control room. Both Olson and Wright stated that they were not aware of this j phenomenon.
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{ Harold R. Denton August 27, 1985 The NRR evaluation of the TNI-2 leak rate tests shows that during 12 of the j i last 13 tests performed by Shift "D" personnel, water additions were made -
i very close to the end of the one hour test period. In each case the amount i
! of wateT logged in the CRO's Log and manually input into the computer for the j
{ calculation was less than the amount indicated on the MUT strip chart ' !
< recorder.. Assuming the response of MUT level transmitter feeding the strip ~ l l chart recorder and the level transmitter providing input to the plant i computer were the same, the unidentified leak rate calculated by the computer.__ - '
j was less than it would have been had the MUT strip chart value of the
! addition been used. If an operator were aware of this phenomenon, as in the
- case of Mr. Coleman, he could take advantage of the phenomenon to increase his chances of obtaining a satisfactory result. The surveillance procedure <
governing leak rate testing directed the operators to avoid water additions 3 unless absolutely required. Thus, in order to detennine whether an operator i j was taking advantage of this phenomenon, it is necessary to determine why the water additions were made.
As stated above, Coleman testified these water additions were made with the intent of altering leak rate test results. Wright stated that the water ,
additions were not required for operational reasons, instead he added water l near the end of the test in an attempt to establish MUT level at the same .,, i value for the beginning and end of the test in order to minimize instrumentation errors. However, since Wright stated he used the MUT strip chart to determine the amount of water added, he could not explain why the
" total number of gallons added" that was inserted into the computer was i
- maller than the amount indicated on the MUT strip chart. Mr. Olson :
explained that the water additions near the end of the tests were necessary )
O for one of two reasons, either MUT level was approaching the lower end of the operating band or to reduce boron concentration in order to move control rods from their outer limit. Neither of Olson's explanations appears credible.
i i
First, a low level in the MUT would not have occurred prior to the end of these tests. In most cases water was added during the last five minutes of the test. Second, none of the other five shifts, which were operating the plant in the same manner and with the same control rod limits as Shift "D."
required water additions during the last few minutes of their tests. .
In sumary, based upon Mr.Coleman's testimony and the NRR evaluation of tests '
involving Coleman, Wright and Olson that shows every test performed between ,
January 11, 1979 and the date of the accident contains either an underrecordedwateradditionduringthelastfewminutesofthetest(12 l tests) or an unaccounted for feed and bleed operation (1 test), the weigh.t of j the evidence supports a conclusion that both Messrs. Olson and Wright were i not forthright and candid in their testimony regarding their knowledge of or participation in leak rate falsification at TMI-2. My conclusions and recommendations contained in Reference 3 regarding Mr. Dennis I. Olson are unchanged.
&c sd William T. Russell Acting Director Division of Human Factors Safety NRR i
Enclosure:
As stated .
. 1 cc: B. Hayes K. Christopher i J. Liebennan J. Goldberg 1
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