|
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20138G7291996-12-0303 December 1996 Summary of 961203 Meeting W/Psc in Plattville Co Re Decommissioning & License Termination of Fsv.Slides,Encl ML20137H2471995-04-12012 April 1995 Summary of 950405-06 Meeting W/Utility at Fort St Vrain Re Stier,Anderson & Malone Rept.Attendees Listed ML20128G1851993-01-29029 January 1993 Summary of 930128 Meeting W/Psc in Rockville,Md Re Briefing of NRC Staff on Status of Fsv Decommissioning Activities. Meeting Agenda & Summary of PSCs Briefing Encl ML20055J3931990-07-31031 July 1990 Summary of 900725 Meeting W/Util in Rockville,Md Re Defueling & Decommissioning of Facility.Attendees List Encl ML20246D9231989-08-18018 August 1989 Summary of 890718 Meeting W/Util to Discuss Defueling of Plant.List of Attendees,Agenda & Viewgraphs Encl ML20236C9921989-03-13013 March 1989 Summary of 890307 Meeting W/Util & Ga Technologies Re Plant Coastdown & Defueling.Attendance List,Agenda & Viewgraphs Encl ML20195D5591988-10-26026 October 1988 Summary of 881013 & 14 Meeting W/Util to Discuss Potential Decommissioning of Facility.W/O Stated Encl ML20154E4031988-09-0909 September 1988 Summary of 880831 Meeting W/Util Re Fire Protection Issues at Plant.Meeting Attendees Encl ML20151K6901988-07-18018 July 1988 Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl ML20151K7361988-04-15015 April 1988 Summary of Operating Reactors Events Meeting 88-15 on 880412.List of Attendees & Viewgraphs Encl ML20153A8551988-03-0909 March 1988 Summary of 880304 Meeting W/Util to Discuss 880122 Submittal Re Helium Circulator Failure & Recovery.Attendee List & Viewgraphs Encl ML20149L4981988-02-12012 February 1988 Summary of 871207 Meeting W/Utils in Bethesda,Md Re Licensees Revised Proposal to Comply W/Nrc Requirement for Simulation Facilities Under 10CFR55.45(b).List of Attendees & Util Simulation Facility Group Guideline Encl ML20147D8901988-01-12012 January 1988 Summary of 881202-03 Meeting W/Util,Inel & ORNL Re Status of Tech Spec Upgrade Program.Meeting Attendees & Listed Ref Encl ML20237D6921987-12-15015 December 1987 Summary of 871203 Meeting W/Util & Inel Re Protective Sys Setpoints in Tech Specs.List of Meeting Attendees Encl ML20237D2251987-12-15015 December 1987 Summary of 871204 Meeting W/Util Re Licensee Latest Proposals for Licensing Actions Concerning CRD Mechanism Temp Requalification & Position Instrumentation.List of Attendees & Related Info Encl ML20236B9121987-10-20020 October 1987 Summary of 871002 Meeting W/Util Re Specific Aspects of Util Approach to Conform w/10CFR55 for Facility.List of Attendees & Util Presentation Matl Encl ML20236A9731987-10-13013 October 1987 Summary of 870915-16 Meetings W/Four Facility Licensees in Bethesda,Md Re Proposal to Apply for NRC Approval for Simulation Facilities.Viewgraphs & Related Documents Encl ML20235Z5891987-10-0808 October 1987 Summary of 871006 Operating Reactor Events Meeting 87-34 Re Events Occurring Since 870929 Meeting.List of Attendees & Presentation Matl Encl ML20235H4401987-09-21021 September 1987 Summary of 870911 Meeting W/Util in Arlington,Tx Re Failure of Plant Circulator S/N C-2101 & Licensee Program to Recover from Failure.Licensee Rept, Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification... Encl ML20207S6271987-03-12012 March 1987 Summary of 870210 Meeting W/Util Re Emergency Diesel Generator Electrical Independence.List of Attendees Encl ML20210P0191987-02-0505 February 1987 Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart ML20212D8641986-12-24024 December 1986 Summary of 861209 Meeting W/Util Re Plant Emergency Electrical Power Sys.Fsar Commitment Re Emergency Diesel Generators revised.Marked-up Draft Rept Re Ac Standby Power Sys Encl ML20207B9781986-12-15015 December 1986 Summary of 861027-30 Meetings W/Util,Eg&G Idaho,Inc & ORNL at Site Re Tech Spec Upgrade Program.List of Attendees & NRC Comment Resolution Encl ML20214U7071986-12-0202 December 1986 Summary of 861120 Meeting W/Util,Ornl,Ga Technologies & Eg&G Re Temp Profiles for Equipment Qualification.List of Attendees & Viewgraphs Encl ML20214P8511986-11-25025 November 1986 Summary of 861105 Meeting W/Lasl Re Technical Evaluation Rept on Prestressed Concrete Reactor Vessel Tendons.Staff Requires Determination Re Listed Items.List of Attendees Encl ML20214Q0951986-11-25025 November 1986 Summary of 861027 Meeting W/Util to Discuss Schedule for Ie/Nrr Insp of Equipment Qualification Program.Attendance List & Viewgraphs Encl ML20197B8651986-10-28028 October 1986 Summary of 861001-02 Meetings W/Util,Inel & ORNL Re Staff Comments on Plant Tech Spec Upgrade Program.Nrc Comments Not Intended to Require Plant Mod or Changes to Licensing Basis of Plant ML20215L2101986-09-12012 September 1986 Summary of ACRS Subcommittee on Gas-Cooled Reactor Plants 860626 Public Meeting W/Nrc & Util in Washington,Dc Re Bases Used to Impose Requirements on Facility & Possibility of Severe Accidents.Attendance List & Viewgraphs Encl ML20215L2001986-09-12012 September 1986 Summary of ACRS Subcommittee on Fort St Vrain 860402 Public Meeting W/Nrc & Util at Facility Re Technical Problems Addressed During Recent Extended Outage & Mgt Charges. Attendance List & Viewgraphs Encl ML20206P5971986-08-15015 August 1986 Summary of 860724 Meeting W/Util,Inel,Wyle Labs,Sargent & Lundy & Tenera in Bethesda,Md Re Util Draft Documentation to Justify Qualification of safety-related Cabling at Plant. List of Attendees Encl ML20211Q6161986-07-23023 July 1986 Summary of Operating Reactor Events Meeting 86-25 on 860721 Re Events Since 860714 Meeting.List of Attendees,Discussion of Events & Status of Assignments Encl.Response Requested for Incomplete Assignments ML20207H0281986-07-21021 July 1986 Summary of 860627 Meeting W/Util Re Status of Tech Spec Upgrade Program.List of Attendees Encl ML20207H1211986-07-18018 July 1986 Trip Rept of 860625-27 Site Visit to Review QA Program, Observe Equipment Qualification Mods & Obtain Unescorted Access Status ML20203B6181986-07-15015 July 1986 Summary of 860613 Meeting W/Util in Bethesda,Md Re Status of Plant Equipment Qualification Program.List of Attendees, Environ Qualification of Plant Safe Shutdown Cable & Cable Qualification Binders Encl ML20199K4911986-06-27027 June 1986 Summary of 860604 Meeting W/Util Re Status of Licensing Actions.List of Attendees,Summary of NRC Responses to Actions & Summary of Actions Encl ML20205S2341986-06-0101 June 1986 Summary of 860502 Meeting W/Util & Inel in Bethesda,Md Re Equipment Qualification Program Problem Areas.Attendees List & Supporting Documentation Encl ML20198H4561986-05-27027 May 1986 Summary of 860505 Meeting W/Util Re Status of Equipment Qualification Program.Considerable Work Remains Before Approval of Full Power Operation Can Be Granted.Staff Recommended Util Continue to Complete Program ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197F6541986-05-0707 May 1986 Summary of 860423-24 Meetings W/Util,Ga Technologies & S&W at Site Re Fuel Block Cracking,Bldg 10 Const,Seismic Instrumentation,Pcrv Tendons & Integrated Leak Rate Testing. Attendance List & Viewgraphs Encl ML20203E8051986-04-18018 April 1986 Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation Encl ML20205J9221986-04-18018 April 1986 Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations ML20205S2591986-04-10010 April 1986 Summary of 860326 Site Meeting W/Util,Dibenedetto Assoc,Inc, Sandia & Sargent & Lundy Re Status of Qualifications of 10CFR50.49 Cables & Maint Records History Review.Viewgraphs & Attendees List Encl ML20141B7451986-03-28028 March 1986 Summary of 860313 Meeting W/Util in Arlington,Tx Re Tech Spec Limiting Condition for Operation 4.1.9 Covering Frequency of Manipulation of Reactor Controls.Supporting Documentation Encl ML20142A0661986-03-14014 March 1986 Summary of 860116 Meeting W/Util,Training Co,Inc & SM Stoller Corp Re Performance Enhancement Program. Viewgraphs Encl ML20141P1771986-03-14014 March 1986 Summary of 860130 Meeting W/Util,Inel,Tenera & Sargent & Lundy Re Equipment Qualification (EQ) Program.List of Attendees,Test Profiles & Review of Sample EQ Package Encl ML20142A0441986-03-12012 March 1986 Summary of 860221 Onsite Meeting W/Util,Inel,D Benedetto Assoc,S&W,Tenera,Ned & NPD Re Equipment Qualification Program & Steam Line Rupture Detection & Isolation Sys ML20138R7331985-10-31031 October 1985 Summary of 851029 Meeting W/Util & ORNL Re Schedule Extension to Equipment Qualification Rule.List of Attendees, Agenda & Matls Presented by Util Encl ML20138P0081985-10-21021 October 1985 Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007 ML20134F3081985-08-15015 August 1985 Summary of 850722-26 Meetings W/Util & Ga Technologies Re Tech Spec Upgrade.List of Attendees Encl ML20129E6721985-05-28028 May 1985 Summary of 850803 Meeting W/Util & Ga Technologies Re CRD Mechanism Tech Spec Problem.List of Attendees Encl 1996-12-03
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20138G7291996-12-0303 December 1996 Summary of 961203 Meeting W/Psc in Plattville Co Re Decommissioning & License Termination of Fsv.Slides,Encl ML20137H2471995-04-12012 April 1995 Summary of 950405-06 Meeting W/Utility at Fort St Vrain Re Stier,Anderson & Malone Rept.Attendees Listed ML20128G1851993-01-29029 January 1993 Summary of 930128 Meeting W/Psc in Rockville,Md Re Briefing of NRC Staff on Status of Fsv Decommissioning Activities. Meeting Agenda & Summary of PSCs Briefing Encl ML20055J3931990-07-31031 July 1990 Summary of 900725 Meeting W/Util in Rockville,Md Re Defueling & Decommissioning of Facility.Attendees List Encl ML20246D9231989-08-18018 August 1989 Summary of 890718 Meeting W/Util to Discuss Defueling of Plant.List of Attendees,Agenda & Viewgraphs Encl ML20236C9921989-03-13013 March 1989 Summary of 890307 Meeting W/Util & Ga Technologies Re Plant Coastdown & Defueling.Attendance List,Agenda & Viewgraphs Encl ML20195D5591988-10-26026 October 1988 Summary of 881013 & 14 Meeting W/Util to Discuss Potential Decommissioning of Facility.W/O Stated Encl ML20154E4031988-09-0909 September 1988 Summary of 880831 Meeting W/Util Re Fire Protection Issues at Plant.Meeting Attendees Encl ML20151K6901988-07-18018 July 1988 Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl ML20151K7361988-04-15015 April 1988 Summary of Operating Reactors Events Meeting 88-15 on 880412.List of Attendees & Viewgraphs Encl ML20153A8551988-03-0909 March 1988 Summary of 880304 Meeting W/Util to Discuss 880122 Submittal Re Helium Circulator Failure & Recovery.Attendee List & Viewgraphs Encl ML20149L4981988-02-12012 February 1988 Summary of 871207 Meeting W/Utils in Bethesda,Md Re Licensees Revised Proposal to Comply W/Nrc Requirement for Simulation Facilities Under 10CFR55.45(b).List of Attendees & Util Simulation Facility Group Guideline Encl ML20147D8901988-01-12012 January 1988 Summary of 881202-03 Meeting W/Util,Inel & ORNL Re Status of Tech Spec Upgrade Program.Meeting Attendees & Listed Ref Encl ML20237D6921987-12-15015 December 1987 Summary of 871203 Meeting W/Util & Inel Re Protective Sys Setpoints in Tech Specs.List of Meeting Attendees Encl ML20237D2251987-12-15015 December 1987 Summary of 871204 Meeting W/Util Re Licensee Latest Proposals for Licensing Actions Concerning CRD Mechanism Temp Requalification & Position Instrumentation.List of Attendees & Related Info Encl ML20236B9121987-10-20020 October 1987 Summary of 871002 Meeting W/Util Re Specific Aspects of Util Approach to Conform w/10CFR55 for Facility.List of Attendees & Util Presentation Matl Encl ML20236A9731987-10-13013 October 1987 Summary of 870915-16 Meetings W/Four Facility Licensees in Bethesda,Md Re Proposal to Apply for NRC Approval for Simulation Facilities.Viewgraphs & Related Documents Encl ML20235Z5891987-10-0808 October 1987 Summary of 871006 Operating Reactor Events Meeting 87-34 Re Events Occurring Since 870929 Meeting.List of Attendees & Presentation Matl Encl ML20235H4401987-09-21021 September 1987 Summary of 870911 Meeting W/Util in Arlington,Tx Re Failure of Plant Circulator S/N C-2101 & Licensee Program to Recover from Failure.Licensee Rept, Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification... Encl ML20207S6271987-03-12012 March 1987 Summary of 870210 Meeting W/Util Re Emergency Diesel Generator Electrical Independence.List of Attendees Encl ML20210P0191987-02-0505 February 1987 Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart ML20212D8641986-12-24024 December 1986 Summary of 861209 Meeting W/Util Re Plant Emergency Electrical Power Sys.Fsar Commitment Re Emergency Diesel Generators revised.Marked-up Draft Rept Re Ac Standby Power Sys Encl ML20207B9781986-12-15015 December 1986 Summary of 861027-30 Meetings W/Util,Eg&G Idaho,Inc & ORNL at Site Re Tech Spec Upgrade Program.List of Attendees & NRC Comment Resolution Encl ML20214U7071986-12-0202 December 1986 Summary of 861120 Meeting W/Util,Ornl,Ga Technologies & Eg&G Re Temp Profiles for Equipment Qualification.List of Attendees & Viewgraphs Encl ML20214P8511986-11-25025 November 1986 Summary of 861105 Meeting W/Lasl Re Technical Evaluation Rept on Prestressed Concrete Reactor Vessel Tendons.Staff Requires Determination Re Listed Items.List of Attendees Encl ML20214Q0951986-11-25025 November 1986 Summary of 861027 Meeting W/Util to Discuss Schedule for Ie/Nrr Insp of Equipment Qualification Program.Attendance List & Viewgraphs Encl ML20197B8651986-10-28028 October 1986 Summary of 861001-02 Meetings W/Util,Inel & ORNL Re Staff Comments on Plant Tech Spec Upgrade Program.Nrc Comments Not Intended to Require Plant Mod or Changes to Licensing Basis of Plant ML20215L2101986-09-12012 September 1986 Summary of ACRS Subcommittee on Gas-Cooled Reactor Plants 860626 Public Meeting W/Nrc & Util in Washington,Dc Re Bases Used to Impose Requirements on Facility & Possibility of Severe Accidents.Attendance List & Viewgraphs Encl ML20215L2001986-09-12012 September 1986 Summary of ACRS Subcommittee on Fort St Vrain 860402 Public Meeting W/Nrc & Util at Facility Re Technical Problems Addressed During Recent Extended Outage & Mgt Charges. Attendance List & Viewgraphs Encl ML20206P5971986-08-15015 August 1986 Summary of 860724 Meeting W/Util,Inel,Wyle Labs,Sargent & Lundy & Tenera in Bethesda,Md Re Util Draft Documentation to Justify Qualification of safety-related Cabling at Plant. List of Attendees Encl ML20211Q6161986-07-23023 July 1986 Summary of Operating Reactor Events Meeting 86-25 on 860721 Re Events Since 860714 Meeting.List of Attendees,Discussion of Events & Status of Assignments Encl.Response Requested for Incomplete Assignments ML20207H0281986-07-21021 July 1986 Summary of 860627 Meeting W/Util Re Status of Tech Spec Upgrade Program.List of Attendees Encl ML20203B6181986-07-15015 July 1986 Summary of 860613 Meeting W/Util in Bethesda,Md Re Status of Plant Equipment Qualification Program.List of Attendees, Environ Qualification of Plant Safe Shutdown Cable & Cable Qualification Binders Encl ML20199K4911986-06-27027 June 1986 Summary of 860604 Meeting W/Util Re Status of Licensing Actions.List of Attendees,Summary of NRC Responses to Actions & Summary of Actions Encl ML20205S2341986-06-0101 June 1986 Summary of 860502 Meeting W/Util & Inel in Bethesda,Md Re Equipment Qualification Program Problem Areas.Attendees List & Supporting Documentation Encl ML20198H4561986-05-27027 May 1986 Summary of 860505 Meeting W/Util Re Status of Equipment Qualification Program.Considerable Work Remains Before Approval of Full Power Operation Can Be Granted.Staff Recommended Util Continue to Complete Program ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197F6541986-05-0707 May 1986 Summary of 860423-24 Meetings W/Util,Ga Technologies & S&W at Site Re Fuel Block Cracking,Bldg 10 Const,Seismic Instrumentation,Pcrv Tendons & Integrated Leak Rate Testing. Attendance List & Viewgraphs Encl ML20203E8051986-04-18018 April 1986 Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation Encl ML20205J9221986-04-18018 April 1986 Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations ML20205S2591986-04-10010 April 1986 Summary of 860326 Site Meeting W/Util,Dibenedetto Assoc,Inc, Sandia & Sargent & Lundy Re Status of Qualifications of 10CFR50.49 Cables & Maint Records History Review.Viewgraphs & Attendees List Encl ML20141B7451986-03-28028 March 1986 Summary of 860313 Meeting W/Util in Arlington,Tx Re Tech Spec Limiting Condition for Operation 4.1.9 Covering Frequency of Manipulation of Reactor Controls.Supporting Documentation Encl ML20142A0661986-03-14014 March 1986 Summary of 860116 Meeting W/Util,Training Co,Inc & SM Stoller Corp Re Performance Enhancement Program. Viewgraphs Encl ML20141P1771986-03-14014 March 1986 Summary of 860130 Meeting W/Util,Inel,Tenera & Sargent & Lundy Re Equipment Qualification (EQ) Program.List of Attendees,Test Profiles & Review of Sample EQ Package Encl ML20142A0441986-03-12012 March 1986 Summary of 860221 Onsite Meeting W/Util,Inel,D Benedetto Assoc,S&W,Tenera,Ned & NPD Re Equipment Qualification Program & Steam Line Rupture Detection & Isolation Sys ML20138R7331985-10-31031 October 1985 Summary of 851029 Meeting W/Util & ORNL Re Schedule Extension to Equipment Qualification Rule.List of Attendees, Agenda & Matls Presented by Util Encl ML20138P0081985-10-21021 October 1985 Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007 ML20134F3081985-08-15015 August 1985 Summary of 850722-26 Meetings W/Util & Ga Technologies Re Tech Spec Upgrade.List of Attendees Encl ML20129E6721985-05-28028 May 1985 Summary of 850803 Meeting W/Util & Ga Technologies Re CRD Mechanism Tech Spec Problem.List of Attendees Encl ML20128P6271985-05-23023 May 1985 Summary of 850516 Meeting W/Util Re Emergency Electrical Power Sys Concerns Resulting from Staff Evaluation of Problems from Testing Emergency Diesel Generators on 841218. Justification for Continued Operation Requested 1996-12-03
[Table view] |
Text
. - _
fo -4 7 Public Meeting i
7:00 to 8:30 p.m.
l Tuesday, December 3,1996 l Platteville Community Center A discussion of decommissioning and l license termination of the Fort Saint Vrain
- Nuclear Generating Station i
Representatives of U. S. Nuclear Regulatory Commission and the Public Service Company of Colorado will be conducting an information l
l meeting to provide the public the opportunity to discuss the decommissioning and license termination of the Public Service Company's of Colorado Fort Saint Vrain Nuclear Generating Station.
The meeting will be held on Tuesday, December 3,1996,7:00 - 8:30 p.m. at
- the Platteville Community Center,508 Reynolds Ave, Platteville, CO 80651 U. S. Nuclear Regulatory Commission
! Office of Nuclear Materials Safety and Safeguards Washington,DC 20555 mm q o
p 888a 8u8llg
U.S. NUCLEAR REGULATORY COMMISSION jv* "*%
s.
++**+
/
DECOMMISSIONING OF FORT SAINTVRAIN NUCLEAR GENERATING STATION PLATTVILLE, CO (LICENSE NO. DPR-34, DOCKET NO. 50-267)
-l MEETING PARTICIPANTS
- Meeting Monitor, Lane Danielzuk/Plattville Administrator
- Nuclear Regulatory Commission (NRC)
Headquarters
- Clayton L. Pittiglio, FSV Reactor Project Manager ,
- Lawrence J. Kokajko, FSV ISFSI Project Manager
- David N. Fauver, Technical Specialists Region IV
- D. Blair Spitzberg, Chief of Inspection Program
- Louis C. Carson, inspector
- Breck W. Henderson, Public Affairs Officer !
- A. C. Crawford, Vice-President
MEETING PARTICIPANTS PSC CON'T
- M. J. Fisher, Program Director
- F. J. Borst, Facility Support Manager
-M. H. Holmes, Project Assurance Manager
-S. Chestnut, Licensing
-G.T. Howard, Westinghouse Project Director !
i
--_ o
AGENDA e Brief introduction about the decommissionir 3 process for Fort Saint Vrain (FSV) Nuclear Generating Station (10 minutes) e Description of the actual decommissioning /
dismantlement of FSV by Public Service Company (PSC) of Colorado (licensee) (15-20 minutes) e Brief description of the NRC's inspection Program conducted at FSV (10 minutes) e Brief Description of the NRC's LicenseTermination Process and NRC's supporting Confirmatory Surveys (10 minutes) e Opportunity for Public questions (30 minutes)
-i FORT SAINT VRAIN NUCLEAR (FSV)
GENERATING STATION'S NRC LICENSES
- Reactor License, No. DPR-34 (10 CFR PART 50, C. Pittiglio, NRC Project Manager) e Independent Spent Fuel Storage Facility, License No. SNM 2504 (10 CFR PART 72, L. Kokajko, NRC Project Manager) t
FORT SAINT VRAIN DECOMMISSIONING o Public Service of Colorado submitted an application to decommissioning FSV on November 5,1990 e NRC issued the Order to Authorize Decommissioning of FSV on November 23,1992
- To resolve technical issues related to the decommissioning of FSV more than 20 requests for addition information exchanges resulted between NRC and PSC
NRC'S CONFIRMATORY SURVEY ~
- NRC conducted an extensive Quality Assurance Audit of PSC's Final Survey Records and supporting documentation
'e Quality Assurance (QA;l Audit was conducted over an 18 month period while PSC's Final Survey was conducted t
- NRC contracted with Oak Ridge Institute for Science and Education i;ORISE;i and with the Department of Energy's Environmental Measurements Laboratory i:EML;i to support the Confirmatory Surveys
- NRC is currently reviewing PSC's Final Survey l Reports for FSV
l NRC'S CONFIRMATORY SURVEY CON'T
- NRC has also contracted with ORISE to provide technical assistance in the review of the Final Survey Reports
- QA Audits confirmed adequacy of PSC Quaiity Assurance Program
- ORISE's and EML's measurements demonstrate consistent results with PSC's Final Survey measurements for FSV i t
l
-l LICENSE TERMINATION OF ~!
1 FORT SAINT VRAIN (SPRING 1997) e NRC is reviewing PSC's Termination Survey Report for FSV 1
e NRC has conducted Confirmatory Surveys
- NRC has conducted several inspections to evaluate PSC Final Survey h
- NRC is conducting Public Meeting to discuss FSV i
decommissioning i
e NRC will terminate PSC's license in accordance with 10 CFR 50.82(a)(11)
- included will be the NRC suppra ting Safety Evaluation
t e
a -
g .
g . _
- United States Nuclear -
Regulatory ~Comniission
~
L D. Blair Spitzberg, Ph.D.
g f# " " %,,
j
~
j' -
~
g Chief,JNucleasMaterialt
\ %**+ / ,
L.icerising~Section .
= - '
9 :
8 h D.E 1.J. Sptzberg, Pli.D.'- Negion IV _
6
. I
= INSPECTION PRO.CEDURES Implemented During; Fort St. Vrain ,
... x Debommissi.oning:' -
, INSPECT 10N PROCEDURE MCDULE NUMBERS
.g .g -
m i I I I S 42700 62702 81018 83000 !
e 9ertOperatiors Martenesco Pogram Security Plai Oossoutleapedon i 6 Impemerstg Proaxbres Survey i z .
y l
- l. -
"- l 40702 64704 82N1 84101 Audtprogram Fire 3rotection Prograsi OperatonalSeetus of the RadoeceveWests ;
Emergency Preperdoness Management i1 ** ~
I l 6MI55 71707 83100 84750 l i Operation of anISFS Rant Operatons OccupatonalExposise Duing ReconceveWasteTreatmet m
3 SAFSTOR& DE'X)N Emuent& ErwironmentalMonrtonne N1: l t c_, 61700 80721 83750 86700 Eg Mance Prccedures & Records Erwironmortal Moratoring occupatonalRaciation Spent FusiPod 8 Expceure Activiies l t
m ;
$ ~
Solid RodoeciveWeste Managemert [
a -
a
._ Tenoportesonof Radoectre Malenals _
W !
l
~
i .
wm y p.E;aii Spitzberg, Ph.D. - Region IV.
FdiewupFrocesse ai -
3 2
Inspection Statistics:. -
Since.Deconunissioning Plan ~
~
i Approve:d11/92 ~
7
.=
- g '
8
=
'22 Insp#ctionsn 1
a
~
750 Inspection Hours +
~
5# -
l
~
6 CitedViolation's .
E
~
.3 Dev. .ia. tio. n. s.
~ [
2 . . ,
s ~
-2 .N. oniditsd. V.iolations. . .
r
~
L -
g
, ' ~
g .
4r"'"
ed
,O" iE ._ j g
f=
G.E iai. Spitzberg, Pn.D.- 2 Region if .
i i
l
!i
t i
e
-;l FORT ST. VRATK &
- l DECOMMISSIONNG
- i rqt f
et g:
PUBLIC MEETING ,,
e
-i Mary J. Fisher gl 1:
Decommissioning Program Director Public Service Company ofColorado $2; E!
R December 3,1996 m at G
I
t .
O t 2i
- i a,
AGFNDA v ro , l I
E a;
+ Background s,
+ Spent Fuel Disposition g s
+ Dismantlemem Methodology .
e
+ Safety and Radiological Performance r
+ FinalRadiological Survey :l w
n?
+ Repowering g w
f M
I i
l
=i 49 EI l )
1 il l
l BACKGROUND a c:
m l + Fort St. Vrain is first and only ofits kind commercial !l ni a
reactor: e l
- 330 MWe High Temperature Gas-Cooled Reactor j
- Began constructionin 1968 ;
-Initialpower generationin 1976 -
- Permanently shut down in August 1989 j l
-l a
5 r
BACKGROUND (Continued) 9
- i o
+ Factors Behind 1989 Shutdown: a m:
"l
- Poor operationalperformance w
+
g
- High fuel cost
' - Continuing economic loss to PSCo !l si
- Control rod drive failures a
- Steam generator ring header failures ji j'
- Significant time and costs to make repairs at G
S i
I
,'~
E i;
SPENT FCEL DISPOSITION E g
j
+ PSCo needed to defuel Reactor Vessel (PCRV): i; i - Fuel in PCRV would delay dismalement ;l 1
- Needed licensed personnel to defuel p 1
- Ongoing cost ofmaintaining staff !l
=
+ FSV was not ready to defuel at time of shutdown: l
. - On-site storage for only 1/3 ofreactor core [ :
i - DOE facility inIdaho not available 1
! - Governor ofIdaho refused to store FSV fuel B e
i i
o
.i O
i; SPENT FLEL DISPOSITION (Continued) j]
n!
+ PSCo decided to build Independent Spent Fuel ij StorageInstallation(TSFSI?: "
- Passively cooled, Modu: ar Vault Dry Store system
{
- Separate from rest ofplant !!
w
- Fuel stored vertically in sealed steel canisters
- 6 fue:. elements per canister [
! - Construction and loading completed June 10,1992, [
l 10 weeks ahead of schedule "i E
ri
(
)
i
I i
a; PROJECT NPLEMENTATION l Plant Shut Down August 1989 l.
ISFSI Construction Started February 1991 ISFSIFuel Loading Complete June 1992 ;
Decommissioning Order November 1992 Physical Activities Complete March 1996 Final Survey Complete October 1996 j License Termination 1st Quarter 1997 l l .
l
FROM PSC FORT ST. urn]N TO N A CtJ ASHDC Pn3E.011
,DEC,10 '96 15:15 I
)
i 8
m
- S i
\\ t / .
\\
w i
\\ ,
\'s . , \ \N ,
\\
.f l
g ,- ! ' '
i
.I W.
O
.h SPENT FGL DISPOSITION (Continued) ;
+ PSCo and DOE reached historic spent fuel agreement !
on February 9,1996:
- DOE has taken title to FSV spent fuel ;
- DOE is applying for 3RC license to operate ISFSI g
- DOE to reimburse PSCo for operating and maintenance costs l
- DOE paid PSCo $16 million ~ i6
- DOE responsible for shipping FSV spent fuel
- DOE responsible for decommissioning ISFSI j s
. - - . . . . , - - - - - . . . - . - . - - . . = . . - ~ . - . - - - - - - . - . - . . _ -
- DEC 10 '96 15 16 'FROM PSC FORT LT. VRolN TO NRCWOSHDC POGE.013 1
I e
9 4
I i'
i l
i
,1 "
- Z, m
l 1
- x, ~
- m
! E6
$ m 5 i
i w
! 8 i
i, I
i i
I J
1 4
DEO 10 '96 15s16 FROM PSC FORT SV. VMalH YlF RWt'.LitTb'R19w mas . s a w A
! PRESTRESSED CONCRETE REACTOR VESSEL (PCRV) l ( cee i N /
c._. h_ ___- s_ ,g l
g j -
- CONTROL R00 OfEVES i
i 6d ?
i '
g ACTIVATIB CONCRETE i e l
! ~ _T l I
- m m aggggg 1
l ..
CORE SUPPORT STEAM MTOR IIODULES PLOOR - /
l ,, - HEJutsCmCULATORS
! k O j d I
l uneR -
dj ,
! 31' es. ~
- =
l - -
- i N
. ; _ k _ _ ,10
/ g i -
} . . -
, DEC,10 '95 15s17 FROM PSC FORT ST. urn 1H TO NRCWOSHDC Pn3E.015 1
i 1
\' -
i i
1 PGtYDiKMAN11,EngEN1' i
t d [/
) '?
- N w ,
~
mu avaman m m SEr!Enf MMNQ NODSMAvE -
1 BEENMADE 10 JtH57AnUQt e*o*f
- l ing wAM CatcvLmNn sistnat.
f _o_o_ -
i l
1 l l w
! I!
W d 5 k II4td W W
)
!Gs % ;
y b ' i, 3
7
! %~
.i
,DEC,10 '9S 15 17 FROM PSC FORT ST. urn!H TO NRCunSHD0 PAGE.015 I
~
x 11
~
l ,$ ._.
l i da C ,
I all - -
,I l >
W ,
i l
O -
Q. ii iiiiiiiiiiins l
b a NJ j A .
E
- 7. J ll el l ll] h
h -
u n
a
~0 E
~ '
DEC 10 '96 15s19 FROM PSO FORT ST. VRolH TO NRCWASKOO POSE . O l f' e cNt g s V n oirr P u 3 0 R M E A FOUn POW JACKING SW Mar SE INETAUAD m SV990RT mg COM * -
SUNORTPLOOR nNKK mgCORESUF M
,j ;
j COLUMM Ante RENQ cVT. .g, .
4 amp m AMIE 7NK /mi- ' 's congSUNOltrFLOOR M nm PQtY MFHEAD \
ang4 musar trWEA i BE SEGMENIED l I
l l
l I I N:M7 T s.-s V
I
I. . . . ... . . .
. / E" L8888 #
Pcay O' W - ancanoes i car a srAnr
- j POsmON 270 Tens F cap suppony STEAM GENEnAron %Da{,!
OUCTS Je COLUM CSF FOUR PolNT JACKING SYSTF.M
FROM PSC FORT ST. URo1H TO HRCWOSHDC PnGE.019
,DEC,10 '95 15s19 1
l 4
h M M MAL - 1 N$ [t W3W
- s".
i u m m amuras L ,f g f .
OF TER core serscar l rimas, sus waars \- d, l
spear autunaeums -
i WIss as amurup As
! cospEars es23r amp i FACEmmi MW
- AEINWF.
1 i
1
/ O O -
1 . -
- W p N
i I i r ,
- '~
M, l
! ~
w- # %
l sit 04 % te les %
l l'
b ) a .>
l
! min nute .
~ .
, , ,- i. ,
} I ,1,
- y 4
i Q-d 4
,e -
. . _ _ . _ . _ _ . _ . _ _ . . _ _ _ _ . _ _ _ . . _ _ _ . ._.._____......-_m. .
DEO 10 '96 15s19 FROM PSC FORT ST. urn]H TO NRCWOSHDO PAGE.019 ._____l i
i 1 l -- ,
=> l t' . 1 i f '
?/ ,
I
/
%g 4p m I u
$ V Q's' 1
T ASBIESOf M l
, p y' concerra cursAM '
yJ
%4 is MdoruaRO7Nr
- W VERTICAL, m l
} Q>
TURES AS COnMKNTS r
WN POR TMtOLAMONO MM M W.
3
" mrconcorras4. Ass -
. s _ .
AMnEuovnoAnnt .
1 s o
'I PACKAGED SQR '
l l SHIAHgM1;'
! . e i 1 i
. l l
,4 ,
. y y -
1
. 1 PCRV ACTIVATED CONCRETE REMOVAL l
I ~ DEC 10 '9G 15:19 FROM PSC FOAT ST. VRO1H TO NRCWOSHDC POG$.'W2@
I i
, n. NY St ,
(I' l
d d <
1 .
l
%Q l %4 l
! d M i >j b* I ,
l4 I i , .v l
ik (
!b Q :' q CLOS (Mrs Mal MAinDE M 1 [' M a Jg s -
tnt nwNgno
- AND ThtMRV
\ HELL MLarr v,
v s
Q' '
- FORLQhqTaw 310Mego z
DISAddNRagyr j t j'
A i s st
- DIO i
k N i @
rA g' i
i f a.
i
- y>
l U
- , ,, s " '
3 l- i i
a l
1 1
4 f PCRV FINAL DISPOSITION 4
1 i
gl SAFETY AND RADIOLOGICAL "
PERFORMANCE 5!
+ OccupationalRadiation Exposures (Person-REM): !i
- i
- Total Estimate 433 perDecommissioning Plan ;j
- Actual Project Exposure 380 i 0
ai OI o,
I
. 8:
n b!
"i I
r
l .!
a SAFETY AND RADIOLOGICAL 1 s
PERFORMANCE (Continued) [
M
- + Low Level Radioactive Waste Shipping (Cu. ft.) ij
- Total project estimate 290,000 l
- Actual volume shipped 289,600 p 2
+ FSV shipments:
l
- 511 Shipments
- 127,650~ cu. ft. buried at Richland,WA (
- 14,400 cu. ft. buried at Beatty, NV I
- 159,100 cu.ft. sent to processors ]
E i
so j 4 SAFETY AND RADIOLCGICAL !!
PERFORMANCE (Continued) i:l oI Industrial safetyindicators: ll m:
+ Only 6 losttime workinjuries jj
+ Lost work day incidence rate (per 200,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) ij
- FSV 0.70 jj
- Typical Construction Projects 5.5 e
+ Severity rate (per 200,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) i st
- FSV 52 !!
e;
- Typical Construction Projects 132 0!
I i
I
_ - - _ - - - - - - - - - - - - - - _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - --_ ____--____i
i ot S!
, 6[
m FINAL RADIOLOGICAL SURVEY .-
+ Documents that decontamination efforts met project ij acceptance criteria [
m
. + Final Survey Report is over 11 feet long -- 46 binders ;j
+ 221,000 fmal measurements in 312 survey areas jj
- Otaer characterization and investigation
- measurements bring total to over 400,000 [
+ FSV site and buildings are decontaminated to permit ll future use without restriction -- offices, industrial, "
continued agriculturaluse f
Y
r
'R
. a
- 5 REPOWERING -
i
+ 130 MW Combustion turbine is currently in !
operation 5
+ Construction of a 102 MW heat recovery steam ;
generator is in progress, with completion scheduled j for May 1998 '
- Utilizes existing FSV turbine-generator :
+ An additional combustion turbine and heat recovery l l steam generator will be added by 1999 I l: + Total FSV capacity will be 471 MW g r
S 5 W _-___------ -_-__--_ ________-_-______-_-_--____- -- ________