|
---|
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
~'?
k, I
UNITED STATES Y
fn ,
LEARwAssmoTon, REGULATORY COMMISSIOq '
o.c.nossa -
%, . . . . ,, e October 9, 1979 .
MEMORANDLH FOR: Chairman Hendrie h Commissioner Gilinsky Commissioner Kenne.iy
)
Commissioner Bradford Commissioner Ahearne hROM: Bernard J. Snyder, Acting Director, OPE .h - ,
SUBJECT:
OPERATION OF THE EPICOR-II SYSTEM AT TMI-2 1 The purpose of this memorandum is to provide views on the operation of the EPICOR-II System for processing approximately 400,000 gallons of contaminated
> water collected in auxiliary building tanks. This memorandum covers three technical and' policy aspects: process adequacy, solidification of resins, and suggested questions for the staff along with the most significant public coments . I understand that OGC is providing a separate memorandum regarding the litigative aspects.
Recommendation I recomend that the Comission approve operation of the EPICOR-II system as soon as the dewatering process for radioactive resins is demonstrated to eeet the criteria of no free-standing water and subject to other conditions discussed below. I recommend that a minimum time period for beginning -
solidification of resins now be established by the staff with Comission ~
concurrence, and subsequent shipments be made after that time only if resins are solidified. I suggest that you may want to obtain the staff's response to the questions and coments in Section III of this memorandum as part of your decision process.
Discussion I. Adequacy of the EPICOR,-II System The basic goal of decontaminating the~ collected water is to fix the radioactive fission products in a less mobile form and reduce the risk of exposure for the public Ud on-site workers. Processing of radioactive water by the use of isn-exchange resin bed demineralizers, such as EPICOR-II, is a well-established practice. From the operation of the earliest water cooled reactors to the present, both central station power plants and Naval propulsion reactor plants have used resin bed demineralizers. The performance of such systems is predictable and the process can be considered reliable and effective.
' I Contact >
Bernie Snyd&r, OPE \
63-43276 g40g8890329f PER LMA N89 PDR;
([ -
jM7 h
p
.. ' ??*l l'
.f .,y ,
' Conuts~sion b 7 "
yI [;
I .The only viable' alternative
- to demineralization is to utilize an evaporative process. This alternative and some~of its disadvantages--
were briefly discussed in the staff's Environmental Assessment (Section
'6.0). However, the staff did not discuss a number of disadvantages that would result if an' evaporator was used. An evaporative process' would produce a very high activity sludge as .the " bottoms". of .the L evaporator. Probably these bottoms would have a much higher specific activity than the hottest EPICOR-II resins. -A frequently encountered problem is that evaporator bottoms containing chemical residues which 1
are difficult to solidify. Considering both the~ higher specific ,
i l activity and difficulty of solidification, a much higher man-rem exposure-would probably result if an evaporator were used instead of -
, 'EPICOR-II.
- J.
. . o On balance, the EPICOR-II system, if properly operated, would be the best approach. The major but I believe manageable, concern in the handling of radioactive resins. Remote handling is required, with-dose rates expected to range from'1000 rem /hr. for the prefilter/deminerah ;
h: down to 3 rem /hr. for the post-filter. Since' 50 change-outs' of !
demineralizers ar_e anticipated to be required to process this >ater, l the possibility is f airly high that leakage could occur from improper I
-connections. ~If leakage were _to occur it would be in arsas'outside "
the shield walls which require manned access to make and break the quick-disconnect fittings. Clean-up of any' spill could- be a significant-
. occupational dose. contribution. For this reason, I suggest that the Consnission require that a hydrostatic test of the system (with clean
' water) be conducted after each demineralized unit replacement,- before-introducing further contaminated water for processing. Furthermore, the licensee should be required to process the lowest activity water first. (Some additional. points are covered in the suggested questi6ns,Section III of'this memorandum).
I I .~ Solidification of EPICOR-II Resins As discussed at the last Comission briefing, the quest'on of solidi-
_fication of the EPICOR-II resins has not been fully resolved. Prior i to generating any radioactive resin, I believe resolution should be reached. In,_mak.in_g_ a decision for TNI-2, it should be recognized that the Scitest EPICOR-II resins will have a specific . activity of about 10 curies /ft3 (mostly Cs-137). This specific activity is roughly 5 to'10 times higher than the hottest resins encountered in normal operation of a nuclear power plant.
- Leaving the water in the tanks at TMI indefinitely would not satisfy what I believe to be the basic goal of reducing the mobility of the radioactive i contaminants, considering the 30 year half-life of Cs-137.
1 I
4
, i.;
Commission , ,
, 1 <.
t' i .
- Although some reactor licensees'have solidified resins in the past,
, there is currently no NRC requirement for solidification.* Based on gL a staff survey, less than one-fourth 'of the currently operating;
. reactors nave solidified resins in the past. ~0f these, most have s
used UF (ureaformaldehyde) or cement solidification. processes. The UF process has been the source of recent problems at the low level waste burial grounds (i.e., leakage resulting from incomplete solidi-
. fication). Generally, it appears that cement systems have been more satisfactory. However,, since some problems have been experienced with both types of systems, whether. portable or permanent on-site any solidification process proposed by Met. Ed. will require detailed l review by NRC staff.
- As presently designed, the EPICOR-II system does not have capability for solidification within the resin liners. 'Without changing the design of the liners, resins would have to be flushed out and processed through an add-on solidification system. This is not'an insurmountable problem. However, some increased radiation exposure to workers would result with . additional processing of the resins. Trade offs among I the options of
- solidification in an add-on system; solidification within redesigned resin liners; or dewatering resins within the - l
- liners appear to be necessary.
Requirements placed on the licensees of the three operating comercial disposal sites presently specify no free-standing liquids in low- ,
level waste accepted for burial. In order to meet stricter enforcement I of this requirement, tests are,being conducted by Met. Ed. to ensure that the no' f ree-standing water criteria can be met. Earlier tests involving a simple suction pumping technique yielded about.a gallon .
'of water when the bottom of a "dewatered" liner was punctured. Since this procedure did not result in an acceptable product, improved ,
techniques including warm air drying are being tested. In addition, i there is concern that-an initially dewatered resin may yield further water af ter transportation ..You should obtain f rom the staff- the latest results from testing of the dewatering process before approving {
operation of EPICOR-II. Assuming improved dewatering techniques are !
successful in meeting the no free-standing water criteria, test results should be made available to the waste burial f acility licensees, the appropriate states, and the public. Prior to any off-site shipment of EPICOR-II resins, the best possible dewatering process should be used (after conclusive demonstration with non-radioactive resins).
In order to reduce exposures and possible risks due to accidents, ,
handling of resin liners should be minimized at the TMI site. l l
- Although NRR established a Branch Technical Position in 1975 that solidification of resins should be required, this has not yet been implemented.
i i
l
. I
Convaission
-4 l The' question.of solidifying EPICOR-II resins before shipment has
.been considered by the NRR and NMSS staffs. As you were told at.the-last briefing, there .is some disagreement between NRR and NMSS, but this disagreement appears to have been narrowed down only to the' issue of when a fully operational solidification system can be avail-able at the site. Based on the attached memorandum from William.
Dircks to Harold Denton, dated October 3, and further discussions
' with'the staff, I understand that.-both agree that unti1~a satisfactory.
solidification system is operating, dewatered resins should be shipped
- - to burial sites. Although not explicitly stated in the attached memorandum, presumably these resins'would have to meet the no free- ;
j standing water criteria. 'I suggest you obtain confirmation of this '
from the staff,.in order to ensure meeting the requirements where ~
- , LLW is buried. I also understant that NRR will provide you with
) .their best estimate as to how soon a satisfactory solidification system can be available at TM14 Both NRR and NMSS apparently agree that solidification should be carried out as soon.as possible, and .
p that-no -long-term storage cf resin liners should be considered at !
[ the TMI' site. . '
Under the,present circumstances, the best course appears to be to proceed with EPICOR-11 processing and off-site shipment ofiresins. as~
soon as the dewatering process is- demonstrated to meet the no free-standing water criteria. A minimum time period for beginnin'g solidification ,
should be established now by the staff, with Comission concurrence and subsequent shipments should be made,after that time only if they are solidified.
L III.
~
Suggested Questions for the-Staff (including major issues' raised in , '
public coments)
The following are some questions which were identified in OPE's review'which you may wish to' address to the ' staff:
- 1. If there was any leakage along the transfer pipe between' the O,8 Auxiliary Building and the EPICOR-Il building how would it be V
<s#
8 detected and what corrective actions would be taken? Does the 5, / guard pipe surrounding the transfer pipe (which would contain any leakage) slope toward the EPICOR-Il building sump for gravity drainage?
2 i
- ,s . ..
1 l