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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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/s .e uano, Enclosure 14
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- UNITED STATES -
' \
i NUCLEAR REGULATORY COMMISSION ,
.
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- .".:: 13 D'. 9 37
.- .. s MEMORANDIJM FOR: Harold R. Denton, Director Division of Human Factors Safety - '
THRU: Hugh L. Thompson, Jr., Director Division of Human Factors Safety [
FROM: William T. Russell, Deputy Director Division of Human Factors Safety
SUBJECT:
RESULTS OF JOINT OI/NRR INTERVIEW WITH MARK S. COLEMAN
Reference:
- 1. Memorandum from S. J. Chilk (SECY) to B. B. Hayes (OI) and W. J. Dircks (EDO) dated April 2, 1984,
Subject:
Staff Requirements-Discussion of Pending Investigation-TMI
- 2. Memorandum frcm H. R. Denton (NRR) to B. B. Hayes (OI) dated May 3, 1984,
Subject:
NRR Review of 01 Investigation Materials Concerning Hartman Allegations of Falsification of Leak Rate Data at TMI, Unit 2 0 3.
Memorandum from W. T. Russell (DHFS) to H. R. Denton (NRR) dated December 14, 1984,
Subject:
Results of Joint OI/NRR Investigation and Evaluation of Dennis I. Olson
~
The purpese of this memorandum is to document the results of the joint OI/NRR intervia with Ar. Mark S. Coleman. The interview with Mr. Coleman was to confirm info,mation provided earlier by Mr. Coleman that was in conflict with statements made by Mr, Dennis I. Olson during his November 15, 1984 interview with 01/NRR. Tne interviews of both individuals dealt with the subject of Reactor Coolant System (RCS) leak rate surveillance testing irregularities at TMI-2 during the period September 30, 1978 through the date of the accident, March 28, 1979. During that time frame, Mr. Olson and Mr. Coleman were licensed Control Room Operators (CR0s) at THI-2 assigned to the same shift.
NOTE: This memorandum and enclosure discuss information which is the '
subfect of an ongoing OI investigation. This memorandum and enclosure may not be disseminated outside the NRC without coordination with ~NRR and the permission ef the EDO or the Director, basis.Internal access and distribution should be on a "need to know" 01."
wwumne P
l _- .. ___ . . _ _ . - - - - - -- -- ^ ' - - - --~ ~'
Harold R. Denton January 4, 1985
Background
As a rescit of a Comission meeting on March 23, 1984, NRR was directed by -
Reference 1 to review 01 investigation materials concerning falsification of RCS leak' rate surveillance tests at TMI-2 and refer back to OI those matters which required further investigation. The results of NRR's review was ~
provided in Reference 2. The review detennined that follow-up investigation by 01 and further evaluation by NRR was needed in the case of seven licensed opera tors. Mr. D. I. Olson, currently a Senior Reactor Operator (SRO) at Waterford 3, was one of the seven individuals identified as needing additional investigation and evaluation. Mr. Olson was interviewed under 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 by Mr. Coleman on April 10, 1980. The results of the joint 01/NRR investigation and evaluation of Mr. Olson is documented in Reference 3. Because of Mr. Coleman's candid admission in April 1980 that he was involved in leak rate falsification at TMI-2, when first questioned about his involvement, it was recommended in Reference 2 that no follow-up investigation of Mr. Coleman was required. .
'Past involvement in TMI-2 Leak Rate Testing Irregularities On December 14, 1984, a joint OI/NRR interview with Mr. Coleman was held in p]
t A
the Office of Investigations Field Office, Region I. The interview was conducted under oath and in the presence of Mr. Coleman's personal attorneys:
Mr. Bart Gephart and Ms. Jane Penny of the law firm Xillian and Gephart. ' The interview was conducted by Mr. Keith Christopher, Director, Office of Investigations, Region I and Mr. Robert Capra, Technical Assistant, Division of Systems Integration, NRR.
A complete sumary of Mr. Coleman's interview is provided as an enclosure to this memorandum. The enclosure also includes a Report of Interview of Mr. Coleman's April 10, 1980 in'terview with IE and CIA and a summary of leak rate surveillance tests involving both Mr. Olson and Mr. Coleman during the period under investigation. The following key points were discussed during the interview:
1.
Mr. Coleman had little faith in RCS leak rate test calculations which were performed to show compliance with the Technical Specifications.
- 2. Leak rate test results were erratic. Acceptable leak-rate test results were more difficult to obtain as the date of the accident approached.
{
- 3. The operators on his shift, including Mr. Olson, were concerned about opera 11ng the plant with high identified leakage caused by valve leakage from the top of the pressurizer. Mr. Coleman stated at one point Mr. Olson recomended to his Shift Supervisor that the plant should be shut gown to repair the leakage.
4 It was common practice to run leak. rate tests several times per shift v) until an acceptable result was obtained. The acceptable tests were retained and the unacceptable tests were thrown away.
Harold R. Denton -
3- January 4, 1985 t
- 5. Mr..-Coleman believed that unacceptable test results were thrown away so '
they would not be seen by the NRC. These tests were thrown away at the-diriction of or with the knowledge and consent of Mr. Coleman's Shift ForeTnan and Shift Supervisor. .-_ e
- 6. According to Mr. Coleman, no changes were made in leak rate test practices following the October 18, 1978 incident that resulted in the generation of LER 78-62/1T.
- 7. Contrary to the consnitment contained in the narrative of LER 78-62/IT, Mr. Coleman was not instructed to enter the Action Statement of the Technical Specification when leak rate test results exceeded the Limiting Condition for Operation.
- 8. Mr. Coleman believes it was consnon knowledge among operators, including the operators on his shift, that hydrogen additions to the MUT would influence MUT level indication and consequently leak rate test results.
- 9. Mr. Coleman used hydrogen additions to the MUT to assist in obtaining leak rate test results that were within the acceptance criteria of the Technical Specifications.
- 10. While Mr. Coleman could not confirm whether Mr. Olson had ever made O hydrogen additions to the MUT to alter leak rate test results, he mentioned adding hydrogen for this purpose to Mr. Olson on at least one occasion. Mr. Coleman stated that Mr. Olson acted like he did not want
, to hear about it. Consequently, Mr. Coleman did not recall discussing the subject with him again.
- 11. Mr. Coleman stated that he was aware that adding water to the MUT during the last few minutes of a leak rate test could produce the same effect on leak rate test results as adding hydrogen to the MUT. Mr. Coleman stated that he use this method to manipulate leak rate test results during the last two months before the accident since hydrogen could no longer be added to the MUT remotely from the Control Room.
- 12. Mr. Coleman could not state whether Mr. Olson ever manipulated leak rate tests by the addition of water to the MUT during the last few minutes of the test. However, after reviewing the leak rate test data, he confirmed it would be hard to believe that Mr. Olson did not use this method.
Conclusions During the period, Mr. Coleman served as a CR0 at TMI-2 on the same shift as Mr. Olson, Mr. Coleman was involved in activities associated with leak rate test falsification. While Mr. Coleman could neither confirm nor deny that Mr. 01 son was also involved in these same actions, it is difficult to believe that Mr. Olson either did not participate in leak rate test manipulation or O have direct knowledge that this activity was going on around him.
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Harold R. Denton January 4, 1985 Mr. Olson stated that following the October 18, 1978 incident, he was advised
~
of the- proper interpretation of 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 results to the good test and turn them -
into h~is Shift Foreman.
There is no indication that the Action Statement of the Technical Specifications was entered by any of the operators on their ~~
shift, either before or after the October 18, 1978 incident. Had Mr. Olson properly applied the requirerents of the Technical Specifications, the Action Statement 1 gpm. would have been invoked whenever unidentified leakage exceeded Mr. 01 son's claim that he did not throw away bad leak rate test results and turned them into his Shift Foreman conflicts with Mr. Colem bad test results." statements that his Shift Foreman and Shift Supervisor "did not want Mr. 01 son's statement that he was not aware that hydrogen additions to the make-up tank could alter make-up tank level and consequently influence leak rate test results phenomenon is also was common in conflict knowledge with among CR0s. Mr. Coleman's statement that this Mr. Olson's statement that he was not aware hydrogen additions were being made for that purpose is in conflict with Mr. Coleman's statement that he mentioned using this technique to Mr. Olson on at least one occasion.
Mr. 01 son's statement that he never added water to the O a leak rate test also does not appear credible in light of the technical data and Mr. Coleman's manipulate admission that Mr. Coleman used this technique to test results.
only two tests that exhibited this pattern.Mr. Coleman and Mr. Olson were invohe in five tests with Mr. Wright (the other CR0 on their shift) and one testHowev where Mr. Olson alone was involved where water was added to the MUT during the last few minutes of a leak rate test.
MUT level increase than was recorded in the CRO's Log or compensated f the leak rate test calculation.
~
In surrnary, based upon Mr. Coleman's testimony, coupled with the technical evaluation of the leak rate tests involving Mr. Olson, I believe the conclusions reached in Reference 3 remain valid and that Mr. Olson w truthful in answering questions regarding his role in leak rate test manipulation. -
O i.
William T.J Deputy Russell, A Director Division of Human Factors Safety Office of Nucl, ear Reactor Regulation
Enclosure:
As stated t
cc: B. Hay ~s N K. Christopher, RI .
i J. Lieberman
_