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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20199E1051999-01-13013 January 1999
Summary of 981119 Meeting with Util to Discuss Pge Preliminary Plans for Final Site Radiation Surveys at Trojan Nuclear Plant.List of Attendees Encl
ML20198B7641998-12-16016 December 1998
Summary of 981119 Meeting with Util & NRC Re Issues Pertaining to Portland General Electric ISFSI Emergency Plan.Attendance List Encl
ML20155C5561998-10-28028 October 1998
Summary of 981008 Meeting with Portland General Electric in Rockville,Md Re Util 10CFR72 License Application.Attendance List,Agenda & Slide Presentation Matl,Encl
NUREG-0782, Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl1998-06-16016 June 1998
Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl
ML20141H7051997-05-19019 May 1997
Summary of 970508 Meeting W/Util Mgt to Provide Info to NRC Re Decommissioning Plans for Plant.List of Meeting Attendees Encl
ML20129E2231996-09-24024 September 1996
Summary of 960911 Meeting W/Licensee in Washington,Dc Re Plant SFP Debris Recovery Program.List of Attendees & Copy of Licensees Handout Encl
ML20129G2581996-04-11011 April 1996
Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo)
ML20059F2621994-01-10010 January 1994
Summary of 931130 Meeting W/Util at Plant to Discuss Variety of Topics Related to Efforts by Licensee to Decommission Facility
ML20058B5681993-11-18018 November 1993
Trip Rept of 931102 Meeting Between NRC & Util Re Planned Research on naturally-aged Cables from Plant
ML20055G9391990-07-19019 July 1990
Summary of 900612 Meeting W/Util Re Reactor Protection Sys Walkdown Results & Proposed Mods.List of Attendees & Handouts Encl
ML20196C2491988-11-30030 November 1988
Summary of 881110 Meeting W/Util & B&W to Discuss Use of B&W Mfg Fuel at Facility.Handouts from Meeting & List of Attendees Encl
ML20155B8231988-09-20020 September 1988
Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams
ML20196L2221988-06-23023 June 1988
Summary of 880531 Meeting on Pressurizer Surge Line Movement & Pipe Whip Restraint Program.List of Attendees & Presentation Handouts Encl
ML20196F9951988-02-24024 February 1988
Partially Withheld Trip Rept of 880209-11 Mgt Team Visit to Region V & San Onofre & Trojan Sites Re Integrated Assessment of Mgt Effectiveness Associated W/Regionalized NRR & NMSS Programs
ML20148H6621988-01-15015 January 1988
Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl
ML20235R3671987-09-30030 September 1987
Summary of 870820 Meeting W/Util Re Adequacy of Support Design Verification.List of Attendees Encl
ML20235G8061987-09-25025 September 1987
Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation Encl
ML20237J6311987-08-13013 August 1987
Trip Rept of 870722-23 Site Visit to Gather First Hand Info Re Main Feedwater Line Pipe Wall Thinning Problem,Review Licensee Pipe Wall Thinning Monitoring Program & Evaluate Results of Licensee Failure Analysis
ML20236L3451987-07-30030 July 1987
Summary of 870617 Meeting W/Util,Bechtel & Impell Re Results of Analyses Concerning Accumulator Fill Line Failure,Main Feedwater Failure & Main Steam Line Thin Wall at Plant.List of Attendees & Viewgraphs Encl
ML20245B9271987-06-25025 June 1987
Summary of 870317-18 Meeting at Facility Re SPDS & Dcrdr. Dcrdr Discussions Centered on Certain Human Engineering Deficiencies Whose Resolution Required Addl Info &/Or in-plant Verification
ML20215J2291987-06-22022 June 1987
Summary of Meeting W/Util on 870408 in Bethsda,Md Re Technical Issues Related to Util Amend Request for F* Steam Generator Tube Plugging Criteria.Attendees List & Meeting Viewgraphs Encl
ML20204E4951987-03-19019 March 1987
Summary of Operating Reactor Events Meeting 87-07 on 870316. List of Attendees,Events Discussed & Significant Elements of Events Presented & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20210L7201986-09-24024 September 1986
Summary of 860529 Meeting W/Util in Bethesda,Md Re Inoperable Steam Generator Hydraulic Snubbers Relationship to Restrained Thermal Growth of Rcs.Supporting Info Encl
ML20214Q8211986-09-19019 September 1986
Summary of 860528 Meeting W/Util & Bechtel in Bethesda,Md Re Control Room Emergency Ventilation Sys,Per TMI Action Item III.D.3.4 on Control Room Habitability.List of Attendees Encl
ML20203N0411986-09-18018 September 1986
Summary of 860513-14 Meetings W/Util at Site & in Portland, or Re Current Licensing Activities & to Meet W/Plant & Corporate Staff as Result of Appointment of New NRC Plant Manager.Attendees List Encl
ML20210S2271986-05-15015 May 1986
Trip Rept of 860510-11 Site Visit to Participate in Licensee Cold Walkdown of Reactor Coolant Loop Piping & Components, Including Supports,To Assess Whether Cause of LER 85-013, Rev 1 Determined
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20151Y0031986-01-29029 January 1986
Summary of 860108-09 Meetings W/Util in Bethesda,Md Re Current Licensing Activities & Reestablishment of Compatible Priorities & Schedules Since NRR Reorganization.Attendee List Encl
ML20137M6361986-01-14014 January 1986
Summary of 851126 Meeting W/Util at Site Re Five Requested Exemptions from Specific Requirements of Section Iii.G of App R (Fire Protection).List of Attendees & Request for Info Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20136C5141985-11-11011 November 1985
Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl
IA-85-353, Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl1985-07-15015 July 1985
Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl
ML20134A5161985-07-15015 July 1985
Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20062J7361980-10-20020 October 1980
Summary of 800930 Meeting W/Util & Westinghouse Re Lab Examination Results for Steam Generator Row 1 U-bend Tube Samples Removed from Plant
ML20125C1751979-12-19019 December 1979
Summary of 791205-06 Meeting W/Util & Bechtel Re Discussion of LER 79-15 Wherein Certain Problems W/Masonry Block Walls & Support Reactions of Equipment/Piping Attached Thereto Were Identified
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-01-13
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20199E1051999-01-13013 January 1999
Summary of 981119 Meeting with Util to Discuss Pge Preliminary Plans for Final Site Radiation Surveys at Trojan Nuclear Plant.List of Attendees Encl
ML20198B7641998-12-16016 December 1998
Summary of 981119 Meeting with Util & NRC Re Issues Pertaining to Portland General Electric ISFSI Emergency Plan.Attendance List Encl
ML20155C5561998-10-28028 October 1998
Summary of 981008 Meeting with Portland General Electric in Rockville,Md Re Util 10CFR72 License Application.Attendance List,Agenda & Slide Presentation Matl,Encl
NUREG-0782, Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl1998-06-16016 June 1998
Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl
ML20141H7051997-05-19019 May 1997
Summary of 970508 Meeting W/Util Mgt to Provide Info to NRC Re Decommissioning Plans for Plant.List of Meeting Attendees Encl
ML20129E2231996-09-24024 September 1996
Summary of 960911 Meeting W/Licensee in Washington,Dc Re Plant SFP Debris Recovery Program.List of Attendees & Copy of Licensees Handout Encl
ML20129G2581996-04-11011 April 1996
Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo)
ML20059F2621994-01-10010 January 1994
Summary of 931130 Meeting W/Util at Plant to Discuss Variety of Topics Related to Efforts by Licensee to Decommission Facility
ML20055G9391990-07-19019 July 1990
Summary of 900612 Meeting W/Util Re Reactor Protection Sys Walkdown Results & Proposed Mods.List of Attendees & Handouts Encl
ML20196C2491988-11-30030 November 1988
Summary of 881110 Meeting W/Util & B&W to Discuss Use of B&W Mfg Fuel at Facility.Handouts from Meeting & List of Attendees Encl
ML20155B8231988-09-20020 September 1988
Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams
ML20196L2221988-06-23023 June 1988
Summary of 880531 Meeting on Pressurizer Surge Line Movement & Pipe Whip Restraint Program.List of Attendees & Presentation Handouts Encl
ML20148H6621988-01-15015 January 1988
Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl
ML20235R3671987-09-30030 September 1987
Summary of 870820 Meeting W/Util Re Adequacy of Support Design Verification.List of Attendees Encl
ML20235G8061987-09-25025 September 1987
Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation Encl
ML20236L3451987-07-30030 July 1987
Summary of 870617 Meeting W/Util,Bechtel & Impell Re Results of Analyses Concerning Accumulator Fill Line Failure,Main Feedwater Failure & Main Steam Line Thin Wall at Plant.List of Attendees & Viewgraphs Encl
ML20245B9271987-06-25025 June 1987
Summary of 870317-18 Meeting at Facility Re SPDS & Dcrdr. Dcrdr Discussions Centered on Certain Human Engineering Deficiencies Whose Resolution Required Addl Info &/Or in-plant Verification
ML20215J2291987-06-22022 June 1987
Summary of Meeting W/Util on 870408 in Bethsda,Md Re Technical Issues Related to Util Amend Request for F* Steam Generator Tube Plugging Criteria.Attendees List & Meeting Viewgraphs Encl
ML20204E4951987-03-19019 March 1987
Summary of Operating Reactor Events Meeting 87-07 on 870316. List of Attendees,Events Discussed & Significant Elements of Events Presented & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20210L7201986-09-24024 September 1986
Summary of 860529 Meeting W/Util in Bethesda,Md Re Inoperable Steam Generator Hydraulic Snubbers Relationship to Restrained Thermal Growth of Rcs.Supporting Info Encl
ML20214Q8211986-09-19019 September 1986
Summary of 860528 Meeting W/Util & Bechtel in Bethesda,Md Re Control Room Emergency Ventilation Sys,Per TMI Action Item III.D.3.4 on Control Room Habitability.List of Attendees Encl
ML20203N0411986-09-18018 September 1986
Summary of 860513-14 Meetings W/Util at Site & in Portland, or Re Current Licensing Activities & to Meet W/Plant & Corporate Staff as Result of Appointment of New NRC Plant Manager.Attendees List Encl
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20151Y0031986-01-29029 January 1986
Summary of 860108-09 Meetings W/Util in Bethesda,Md Re Current Licensing Activities & Reestablishment of Compatible Priorities & Schedules Since NRR Reorganization.Attendee List Encl
ML20137M6361986-01-14014 January 1986
Summary of 851126 Meeting W/Util at Site Re Five Requested Exemptions from Specific Requirements of Section Iii.G of App R (Fire Protection).List of Attendees & Request for Info Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20136C5141985-11-11011 November 1985
Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl
ML20134A5161985-07-15015 July 1985
Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl
IA-85-353, Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl1985-07-15015 July 1985
Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20062J7361980-10-20020 October 1980
Summary of 800930 Meeting W/Util & Westinghouse Re Lab Examination Results for Steam Generator Row 1 U-bend Tube Samples Removed from Plant
ML20125C1751979-12-19019 December 1979
Summary of 791205-06 Meeting W/Util & Bechtel Re Discussion of LER 79-15 Wherein Certain Problems W/Masonry Block Walls & Support Reactions of Equipment/Piping Attached Thereto Were Identified
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-01-13
[Table view] |
Text
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$t" UNITED STATES NUCLEAR REGULATORY COrAMISSION if WASHINGTON, D.C. 20555-0001
...../ May 19, 1997 h-YY MEMORANDUM TO: MichaelT. Masnik, Acting Chief Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Y
i ROM: Lee H. Thenus, Project Manager [
Non-Power Reactors and Decommissioning l Project Directorate Divison of Reactor Program Management I
SUBJECT:
TROJAN MEETING
SUMMARY
A public met.tng was held cn May 8,1977 at 1:00 PM between Portland General Electric's (PGE) Trojan plant manage nent and the NRC Executive Director for Operations and other members of the NRC staff. The meeting was attended by an official from the Oregon Department of Energy and several members of the public. A list of attendees is attached.
The public meeting was started with the introduction of the participants. Lee Thonus, NRR, announced that the meeting was open to the public and that the purcose was for PGE to provide information to the NRC staff regarding their decommissioning plans for Trojan.
Steve Quennoz, PGE Trojan Site Executive, stated that the three key projects for the Trojan decommissioning were the licensing and construction of an independent spent fuel storage installation (ISFSI), the removal preparation and shipment to the burial site of the Trojan reactor vessel (RV), and the processing of tne fuel debris located in the Trojan spent fuel pool. He stated that PGE wanted to complete a known decommissioning at a known cost to provide a j data set for the many interested parties in the NRC and industry. He further shted that placing i the fuelinto dry storage was a priority because it would allow T'GE to procee. .vith the remaining decommissioning activities at the site using experienced personnel.
Mr. Quennoz described the advantages of PGE's prepowd plan to ship the reactor vessel and intemals intact versus removal of the reactor vessel intemals prior to preparation of the RV for shipment. PGE listed the advantages as lower dose to plant workers, to shippers, and to the public; one shipme't vs. 55-89; and no Greater Than Class C (GTCC) waste from intemals segmentation that would have to be stored onsite. Next Mr. Quennoz discussed the restrictions which would be placed on toe RV shipment, probabalistic risk assessment of the shipment, and [
special features associated with the transport barge and with the RV tiedown system to meet the O 12 10-e probability of failure criterion. PGE acknowledged : hat they will likely need exemptions ;
from the regulations on rollover and brittle fracture requirements. PGE's accident analysis shows that the consequences of a breached RV 9ackage would be less than the acceptance criteria for accidents involvic,g type A packages.
Y3
.A David Stewart-Smith of the Oregon Department of Energy discussed the Oregon Energy Facility Siting Council review of the proposed RV shipment. He believes that shipping the RV and intemals .'ntact has many advantages. They include fewer shipments and less exposure. He believes that PGE's proposal should receive a fair hearing. The state of Oregon has experience with similar shipments and they are well trained and prepared to deal with radioactive material transport & tion issues.
4 W
.. - - - . . ~ - - .- _. . - -
2 May 19, 1997 Mr. Quennoz stated that PGE needs to grout the RV in October of 1997 in order to meet their schedule for a July / August 1998 shipment. The size of the RV would be similar to one of the steam generators previously shipped but it would weigh twice as much. It would be similar to a navy reactor compartment shipment.
Earl Easton of the NRC staff asked about the difference between the November 1997 requested NRC completion and the October 1997 grout. Mr. Quennoz acknowledged that PGE may need to perform some work at risk of not having the shipment approved. Mr. Easton asked if PGE would need any exemptions to 49 CFR regulations. The PGE representatives did not know of any but would check to make sure.
John Greeves of the NRC stated that the 2 million curies proposed for burial was large and that GTCC material was not normally allowed in shallow lard burial. Mike Lackey from PGE replied that PGE had already discussed the disposal with the state of Washington (regulatory authority for the disposal site) and that they had agreed that the RV and intemals package would fall within licensing guidelines after averaging of tot.91 mass.
The meetir.g was adjoumed at approximately 2:00 PM.
Docket File No. 50-344
Attachment:
As stated i cc: See next page i
l DISTRIBUTION.
HARD COPY IDocket File No.750-3447?
PUBLIC PD# Reading OGC E-Mall ;
SCollins/FMiraglia LThonus MMendonca RZimmerman EHylton ,
MSlosson EJordan (JKR) i SWeiss NRC Participants Region IV KPerkins 1
PDND:PMg :LA PDND:(A)SC MMasnik MIq PDND:(A)D LThonus on MMendonca 7/l$/97 f /11/97 T/ li/97 OFFICIAL RECORD COPY , / /97 DOCUMENT NAME: G:\SECY\THONUS\TROMYG. SUM i
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2 Mr. Quennoz stated that PGE needs to grout the RV in October of 1997 in order to meet their schedule for a suly/ August 1998 shipment. The size of the RV would be similar to one of the steam generators previously shipped but it would weigh twice as much. It would te similar to a navy reactor compartment shipment.
Earl Easton of the NRC staff asked about the difference between the November 1997 requested NRC completion and the October 1997 grout. Mr. Quennoz acknowledged that PGE may need to perform some work at risk of not having the shipment approved. Mr. Easton asked if PGE would need any exemptions to 49 CFR regulations. The PGE representatives did not know of any but would check to make sure.
John Greeves of the NRC stated that the 2 million curies proposed for burial was large and that GTCC material was not normally allowed in shallow land burial. Mike Lackey from PGE replied that PGE had already discussed the disposal with the state of Washington (regulatory authority for the disposal site) and that they had agreed that the RV and intemals package would fall within licensing guidelines after averaging of total mass.
The meeting v is adjoumed at approximately 2:00 PM.
Docket File No. 50-344
Attachment:
As s ta ted cc: See next page
. - _ . _ . ..__._._.__.______._____....m .. . _ . , _ _ _ _ . _ ._
q-1 t .
j Mr. Stephen M. Quennoz Trojan Nuclear Plant
- Portland General Electric Company Docket No. 50-344 cc
Chairman of the Board of County ;
Commissioners .i Columbia County St. Helens, Oregon 97501 Mr. David Stewart-Smith Oregon Department of Energy 625 Marion Street, N.E.
Salem, Oregon 97310 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower and Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas . 76011-8064 l
Mr. H. Ray Pate Manager Licensing, Compliance and Commitment Management ;
Portland General Electric Company Trojan Nuclear Plant >
71760 Columbia River Highway i Rainier, Oregon 97048 Mr. Lloyd K. Marbe,t 19142 S.E. Bakers Ferry Road Boring, Oregon 97009 Mr. Jerry Wilson - '
Do it Yourself Committee 570 N.E. 53rd ;
Hillsboro, Oregon 97124 '
Mr. Eugene Rosolie Northwest Environmental Advocates 302 Hasettine Building 133 S.W. 2nd Avenue Portland, Oregon 97204 ;
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L.'*~ l I
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L ATTACHMENT - LIST OF ATTENDEES NRC S. Bums, Associate General Counsel, OGC L. Callan, Executive Director for Operttions S. Collins, Director, NRR S. Droggitis, OSP E. Easton, Section Leader, NMSS/SFPO J. Everett, inspector, RIV
. M. Fairtile, Senior Project Manager, NRR/DRPM J. Greeves, Director DWM, NMSS T. Johnson, Section Leader, NMSS/DWM B. McCabe, Regional Coordinator, OEDO l M. Masnik, Senior Project Manager, NRR/DRPM M. Mendonca, Acting Director, PDND, NRR/DRPM
. C. Paperiello, Director, NMSS l' D. Reid, Project Manager, NMSS/SFPO l M. Slosson, Acting Director, POND, NRR l- D. Spitzberg, Chief, NLMB, RIV l L. Thonus, Project Manager, NRR/DRPM l M. Webb, Project Manager, NRR/DRPM l
Oreaon Department of Enerov l- D. Stewart-Smith, Administrator l-PGE
[ M. Lackey, General Manager Engineering / Decommissioning l H. Pate, Manager, Licensing l S. Quennoz, Trojan Site Executive P. Yundt, General Manager, Plant Support / Technical Functions
- Public K. Ainger, Commonwealth Edison l ' N. Chapman, Bechtel L. Hendricks, NEl M. Neal, NUS/LIS l
l' .-
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