|
---|
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
- . -- . . _ -. - -- __. _ - - .. _ _ _
VW * (~ "t *
.qMM N
~
Tso sTATas M
Qg
'c, NUCLEAR REGULATORY COMMtsslON
. -[g j;ff),,. .,cgg g g >g % .29NcToN.o.c.rosss I#
' February 24, 1983 ustw yedM'
~%T./ .
ATTACHMENT 7 Lake H. Barrett, Deputy Program Director MEMORANDUM FOR:
TMI Program.0ffice .
FROM:
Philip J. Grant, Nuclear Engineer
" TMI Program Office
SUBJECT:
PROCEDURE PROBLEMS ASSOCIATED WITH RCS DRAINDOW CORRECTIVE ACTIONS- .
s
- As per your request, I have sumarized below some of the major deficie identified on the subject procedures.
poor quality, inadequate PORC review, inconsistencies wi ,
. procedures and safety precautions. -
In regard to safety significance, next to head lift and fuel removal, these procedures are of prime importance in assuring and maintaining safe conditions within the reactor core and reactor building, and provide guidance and
- direction to the operators in taking the necessary corrective actions.
Specific Comments p ,
i '
- 1. Two procedu es (2104-10.1 and 10.2), approved by PORC would have alloweti.
secondary system pressure to exceed RCS pressure. This would violate 320 M6' limits and conditions' established in, existing procedures, as well as exceed the boundaries of the SER's for both " Quicklook" and the planned 4
underhead characterization task.
- 2. Procedure (2104-10.2), would have allowed RCS draindown to exgged limit This (328 ELV) established by GPU Licensing letter to NRC dated 2/rW 83'.
action would have also exceeded condition's' previously bounded by the above
- 3. Procedure (2202-5.5), on " Loss of RCS Level Indication", did not incorporate the new RCS standpipe level indicator, nor properly correct for pressure compensation on existing level indicators and the procedure may have mislead the operator to make an improper corrective action.
Valve lineup procedure (2104-10.1), to insure operability of OTSG 1evel l J indicator (HeiseGage),wasinadequateandrequiredcorrection.
e f
- f .
M.A
--,-e -
,,- * --r--- - *y. ""* "
~T-- - -' - " "'W " ' " ' - - ' ' '-"'Pe''****'"f'-'*~&"*-Y v** M
~> - .
February 24, 1983 1.ake H. Barrett - _ _ _ . . . . -- - .- . _.__ - -
~-
)
t
!d?.{Ck.- ('olation 6 /2-- of SPC system did not include SPC-V-73 which bypasses isolation
- 5. Is
) valve SPC-V-71. This could have allowed inadvertent injection of waterj u
into RCS and possible overflow of RCS out the CRDM openings
- 6. Inconsistencies existed between RCS water level eleva' tion and meas ,
on water level indicators (inches).
7.- Isolation of demin water sources did not address the RCS (Reactor Coo Feed System), and the possible boron dilution event from cperator error.
- 8. The surveillange testing section of systems (e.g., DHR, MDHS, CFS, ICCN, etc.),wasnot consistentwithGP$apparentplansforfuturetesting.
These com.T.ents, in addition to less significant items, have beenCurrently fcmardedweto GPU and corrections have been made to the existing procedures.
are awaiting four procedures before RCS draindown can be implemented.
M Philip J. Grant Nuclear Engineer -
TMI Program Office cc: A. Fasano J. Wiebe ,
e
+
4 0
.I e ..
/h'd b.bGrrC Y y/
pg ATTACHMENT 8 I p1* GPU Nuclear Corporation
- ",/f h 7, y/ gD
[dk jRUCIear l'M S
- i. *souin'8 Middletown. Pennsylvania 17057 717 944 7621 TELEX 84 2386 Writer"s Direct Dial Number:
March 4, 1983 Mr. L. P. King 704 Linden Avenue Hershey, Pennsylvania 17033
Dear Mr. King:
Subject:
Concerns of Mr. L. P. ' King Regarding TMI-2 Activities Attached hereto is a memorandum setting forth what I understand to be the concerns you have about TMI-2 activities. Please let me '
know if you have anything to add to this memorandum. The Company will be investigating and evaluating the potential issues you have raised.
Very truly yours l %
R. C. Arnold President Attachment slm GPU Nuclear Corporation is a subsidiary of tne General Public Utilities Corporation
Inter-@ffico Momerandum 5
Date Ibrch 4, 1983 Concerns of Mr. L. P. King Ir p1NuoDear Subject Regarding TMI-2 Activities Location To L. P. King The purpose of this memorandum is to set forth concisely and fully the con-cerns that you have with regard to TMI-2 activities.
This includes those items identified in the discussion held at your request with Mr. Clark on February 25, 1983. I have reviewed with Mr. Clark his notes from that discussion, and he has reviewed the draft of this memoran-dum to help ensure that your concerns are understood and properly recorded l
here.
While we are particularly interested in any concerns you have regarding safety, we are also interested in those concerns you have regarding effec- l tive and efficient conduct of all activities at TMI-2.
I recognize that our discussion of these issues is potentially affected by I I
our serious concerns which we have identified to you about your involvement
in, or knowledge of, the hiring of GPU System employees by Quiltech, a com-pany of which we understand you are president. However, those issues will j
l be addressed separately. 1 In the area of safety concerns, it is my understanding that you have the following general concerns:
l
- 1. The emphasis on meeting schedules tends to prevent and dis-courage adequate consideration of potential safety issues.
i
- 2. The willingness of sore members of TMI-2 management (in-cluding Messrs. Kanga, Barton, and Thiesing) to fully con- -
sider potential safety issues is inadequate and tends to dis-courage issues from being raised.
- 3. Based upon your experience, you concluded that Thiesing can-not be trusted to tell the truth and thus one cannot rely upon his technical work, judgments, and statements relative to safety issues.
AOCC0648
L. P. King
, - Page 2 March 4,1983' 4
- 4. There is insufficient involvement by Messrs. Arnold and/or Clark for them to be aware of the fact that sa_fety issues ,
3 are not being considered adequately in TMI-2 activities.
- 5. Site Operations Department does not always-have sufficient time, and in some instances sufficient technical information, to assure they can adequately fulfill their role relative to safety implications of cleanup activities. For example, the Safety Evaluation Report (SER) may not be available ~on a timely basis for careful checking by. Site Operations of the related
. procedures against the final SER.
- 6. The practice of providing " draft" procedures to the NRC is being used to pressure Site Operations to sign off on pro-cedures without adequate consideration of potential safecy issues.
- 7. Bechtel's initial technical work products are sometimes in-adequate.
- 8. Preparation of engineering changes and procedures which con-trol TMI-2 activities is sometimes not in accordance with appropriate requirements; e.g., sometimes systems, equipment, engineering changes, or procedures are inappropriately classi- '-
fied as not "important to safety" and thus related activities are not subjected to the appropriate safety and QA/QC reviews (this problem is partly the result of the need to update the Quality Classification List which helps to control and deter-mine those decisions).
- 9. Minutes of some meetings do not document potential safety issues that are raised during the meetings.
- 10. There is insufficient involvement by Q'A/QC, Site Operations, and ,
the Safety Review Group in work done by Mr. Thiesing's department and thus inadequate assurance of safety; e.g., the polar crane repairs and modifications will not get reviewed by Site Opera-l tions and QA until after the crane has been used to make sig-i nificant lifts above the reactor.
While it is my understanding that you do not know of any activity that has been carried out that was unsafe, there are specific examples (in addition to those cited above) as to how those previously described circumstances have created the potential for work to be done without adequate require-ments for safety. You have documented a number of these over the last several months by means of memoranda and copies of these memoranda are
! contained in Site Operations files. Some of the specific ones that you can recall are:
)
L. P. King .
S Page 3 '
March 4,1983
- l. NRC contacted you about improper safety classification of some equipment or procedures and you told them this 'was a .
frequent problem. NRC (Barrett) said NRC would follow up and you believe the classification was changed. Ron Warren has documented concerns about the issue in several memoranda.
- 2. Minutes of Head Lift Status Meetings do not reflect issues raised during th'e meetings.
- 3. You and Mr. Gischel (who is very knowledgeable about cranes) were specifically instructed not to get involved in the prepara-tion for restoration and testing of the polar crane because it was not the responsibility of Site Operations.
- 4. Mr. Barton was critical of your memorandum which documented that you and Mr. Gischel had been told not to get involved in the preparations for the polar crane restoration and testing.
- 5. The Bechtel-prepared draft SER for the polar crane restorati.on and testing was considered by the.NRC to be of very poor quality, and they requested a thorough review of the SER by GPUN.
- 6. You concluded the subsequent revised SER for the polar crane was
, also technically inadequate. ,,
- 7. Messrs. Kanga and Barton were unwilling to address adequately your concerns about the polar crane. However, you agree that if the load drop accident calculatio'sn are valid and a careful re-view by QA/QC is accomplished properly (and any items _ identified t are resolved) then the polar crane restoration and testing pro-gram will be technically adequate. Nevertheless, you advocate a review of whether ALARA and schedule considerations in fact outweigh the benefits of a more extensive testing and inspection sequence for requalification of the polar crane.
- 8. Site Operations (specifically Mr. Gischel and you)' had inadequate opportunity to review.the basis for the polar crane restoration -
and test program before being asked to " sign off" on the polar l J
crane SER.
- 9. You and QA (Ballard) had to force the issue to get Freemerman to agree that administrative procedures AP 1043 and AP 1047 applied to polar crane testing.
- 10. You are not sure that all repairs to the polar crane involved re- l placement "in kind." If that is not the case, the work should !
have been controlled as a modification to the crane.
c . g, ,
+
t y-L. P. King Page 4
- March 4,1983 3 11. You are not sure that the load drop analysis described in the .
polar crane SER was in fact actually done although Bechtel claims it was done.
- 12. You are not sure that the GORB minutes, Recommendations, and Action Items reflect the issues ~ discussed by them during their
- review of the polar crane program.
- 13. The draft SER for the neasurement of radiological conditions "
under the reactor head was not finalized in time to support
' the schedule so a decision was made to proceed based upon the SER for the " Quick Look." You question.whether the procedures prepared based on the draft SER was consistent with the " Quick Look" SER. Only the Safety Review Group (Kunder) reviewed the draft procedures'against the " Quick Look" SER--the Site Opera-tions staff did not. The SRG approved;the procedures " subject to comment" which is not the normal practice. The draft pro- ,
cedures were-furnished to the NRC and they commented negatively on the preparation process for the procedures. .
With regard to the effectiveness of the management of the TMI-2 program, you have the following general concerns: .
- 1. Bechtel personnel are inefficient and in many instances incompe- '_
. tent.
1 i 2. Activities such as engineering, procurement, and procedure prep-aration are not being scheduled on an integrated basis along with the field work. This is causing inefficiencies as well as having i
the implications to safety discussed above.
- 3. You have tried to have your concerns addressed by Messrs. Barton and Kanga without success. In' addition, they are either failing j- to identify your concerns to me or I am failing to address them and " hiding behind" Mr. Kanga.
Some specific examples you consider to be illustrative of the deficiencies of the management are:
i
- 1. Bechtel failed to complete on time the ECM for installation of equipment for measuring water level during the d. raining of the Steam Generators. Therefore, you had to provide an alternative means and get NRC approval for the associated procedures.
- 2. GPUN established a schedule of mid-1983 for obtaining gas and liquid samples for the purification system demineralizer and then advanced the schedule to an earlier date because of pres-sure from the NRC. This caused you to have~to pursue the effort on a " crash" basis instead of at a more deliberate pace.
e
-L. P. King i Page 5 March 4,1983 -
- 3. You believe' Site Operations has accomplished decontamination in the Auxiliary Building at a much lower cost then would have been the result if Bechtel had managed that work as originally planned.
- 4. You tried to get these concerns addressed by Barton and his management at the time of your annual performance review and.
were. unsuccessful.
On a related subject, you believe that Bechtel (perhaps with directions from GPUN) contacted Quiltech, the company of which you are president, for the pur-pose of either:
- 1. Offering work to your firm in return for your being quiet ,
about your concerns; or
- 2. Trying to compromise you with GPUN (perhaps relative to the ,
GPU Conflict of Interest Policy).
I also understand that you believe you were suspended on February 24, 1983 (while the Company investigated your involvement with Quiltech and its employment.of GPUN personnel) in retaliation for your having stated your concerns about THI-2 activities.
' To the best of my knowledge this memorandum describes all of your significant-general concerns as to safety and effectiveness of TMI-2 activities. Please let me know if there are any other concerns which you believe need to be.ad-dressed and resolved. ;
I i
f j
Q R. C. nold slm .
cc: P. R. Clark H. M. Dieckamp B. K. Kanga y , e ~- + - - - -