ML19327B807
| ML19327B807 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 11/07/1989 |
| From: | Williams P NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Joshua Wilson NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| NUDOCS 8911130364 | |
| Download: ML19327B807 (6) | |
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Advanced Reactor 5 and Jerry N. Wilson, Section Leader, ion of Regulatory EMORANDUM FOR:
Standardization Section, Divis Applications, Office of Nuclear Regulatory Research j
FROM:
Peter M. Williams, Advanced Reactors and Standardization f
Section. Division of Regulatory Applications, Office of i
Nuclear Regulatory Research
SUBJECT:
MEETING ON UTILIZATION OF DATA FROM THE DEC0t941SSIONING OF FORT ST. YRAIN TO SUPPORT THE REVIEW 0F THE MHTGR Summary i
AjointNRR/RESmeetingw)iththeDepartmentofEnergy(DOE)andPublicService Company of Colorado (PSC was held on October 26, 1989, to discuss the utilization of data from Fort St. Vrain to support the review of the NHTGR. A list of attendees is given in Enclosure 1.
The staff and DOE realize the potential benefit that data from it. St. Vrain can have to both NRC and DOE and; therefore, consider it worthwhile to exchange ideas regarding what can be learned prior to and during the decomissioning of the plant. Accordingly, this meeting was to exchange ideas and learn the status of DOE's plans to obtain data.
.Because of equipment concerns, decomissioning costs, and concerns of data I
quality, DOE does not plan to pursue the use of Fort St. Vrain (FSV) to obtain data on reactor physics, fluid flow, heat transfer, and depressurization phenomena prior to its decommissioning. Rather, DOE will concentrate on the examination of components, structures, fuel, and materials during and after decomissioning.
Items of potential interest were identified by PSC in r.
i Fort St. Vrain is now permanently shutdown and expects to begin unloading fuel on November 27, 1989. A prelimine.ry DOE-PSC technology transfer contract is in effect and a draft transfer technology plan was completed in September 1989, with the final resolution of the technology transfer scope and the implementation of technology transfer to be developed in the future.
I DISCUSSION Mr. Larry Brey of PSC presented the status of the DOE /PSC HTGR technology transfer program for Fort St. Vrain. A sumary of this program is given in where the historical, current, and future activities are identified.
Items being considered for both the pre-decommissioning and decomissioning phases are listed. A final determination of the transfer scope has not yet been made nor has a decision to " safe store" the reactor vessel er to proceed immediately with dismantlement. This ih partly an economic decision OF#f 8911130364 891107 gDR ADOCK 05 % h7
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and will affect the scope of the technology transfer program. DOE is doing a cost effectiveness su ty. The DOE NPR-MHTGR program may contribute to cost of the technology t naster program.
The NRC staff expressed its views regarding information useful to the staff to
,upport its review of the MHTGR which possibly could be obtained during the decommissioning phase. This included examination of the steam generator (adhesion of particulates and inspection of bimetallic welds), structural performance of the graphite core supports, vibration effects on metals, and fuel perfomance by means of established post irradiation examination techniques including examinations for fuel coating microporosity.
Evaluation of operational history is also considered important and includes analysis of information from the Data Acquisition System (DAS), inservice inspections, and operator responses to abnormal events.
DOE plans to remove the plateout probe in the primary system as its first action under the preliminary technology transfer agreement. This will exercise the preliminary plan and lead to a final agreement.
i S.J. Ball (ORNL) outlined tests and experiments that DOE might consider in Fort l
St. Vrain before decommissioning. The tests were not discussed in detail i
because of DOE's decision that such activities would not be cost effective in terms of decommissioning costs and concerns of data quality. The discussions on FSV utilization with DOE are expected to continue in forthcoming separate meetings, after DOE plans are more firm.
Peter M. Williams Advanced Reactors & Standardization Section
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Division of Regulatory Applications t
Office of Nuclear Regulatory Research Distribution:
[FT. ST VRAIN) subj-circ-chron t
Reading Files
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Name: PW1111ams:rg Date:.11/1/89 0FFICIAL RECORD COPY
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ATTENDEES AT MEETING ON FSV UTILIZATION l
OCTOBER 26, 1989 r
Name Organization f
Ken Heitner NRC/NRR Syd Ball ORNL Pete Williams NRC/RES Charles Daily NRC/ACRS l
Jerry Wilson NRC/RES Peter G. Kroeger BNL i
John Cleveland ORNL Thomas King NRC/RES i
Robert P. Wichner ORNL i
Ray Mills MHTGR/ PDC 0 A. C. Millunzi DOE PSC T
L. Brey NRC/NRR Peter B. Erickson S. H. Weiss NRC/NRR Dana 11e Weaver Energy Daily Med EL-Zeftawy ACRS l
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i PSC Handout i
HTGR Technology Transfer from FSV
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HISTORICAL PSC; EPRI and GCRA Discuss Research on FSV Reactor Materials
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for niun Development - Pay 1987 i
')iscussions Initiated on Technology Transfer Betwten PSC and r
NL (I6aho & NL), LSU - 5eptem er 1955 DOE-Idaho and EGG Personnel Ba,d,g d for Access to Fort St. Vrain Witness Plant Operations l
Interview Plant Personnel l
Assess Plant Design 6
DOE /PSC Technology Transfer Contact in Effect p
1 DOE Detemines Tasks of Interest t
Agreement is Reached on Scope, Cost, and Schedule of Tasks Work is Performed and PSC is Reirbursed for Efforts Expended l
Meetings Established to Develop Technology Transfer Plan L
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DOE / EGG (IdahoandPSC-May 22, 1989 DOE (Idaho and NE), EGG, GCRA, EPRI, and PSC - June 8,1989 t
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EPRI Funds Development of Preliminary Technology l
l Transfer Plan Working Group Meeting - June 23, 1989 Review Draft of Technology Transfer Plan DOE (Idaho and NE), EGG, GCRA, EPRI, and PSC - August 2,1989 i
Reviewed and Established Priorities Preliminary Technology Transfer Plan Completed - September 1989 7,
l Identifies Technology Available from FSV L
Identifies Needs for NPR and NHTGR Programs l
l Identifies Priorities, Risks, and Schedules for Each Task 4
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Current PSC Announces Permanent FSV Shutdown - August 29, 1989 Steam /Cenerator and Control Rod Drive Problems 4
DOE / EGG (Idaho) and PSC Meeting - September 11, 1989 j
Reviewed Steam / Generator and CED Issues Discussed Technology Transfer Methodology l
Reviewed items of Potential Interest (Pre-Deconnissioning) l l
Plateout Probe
- Fuel Test Elements Control Rod Drive & Absorbers
- H451 Graphite Purification HTFA and LTFA
- Helium Circulator Detailed FSV Radiation Survey F
Detailed Tritium Balance l
Agreed on Removal of Plateout Probe as initial Project i
Utilizing DOE /PSC Contract Agreed on Formulation of Task Team as Formal Mechanism in Accomplishing Technology Transfer Objectives i
keviewed items of Potential Interest (Deconnissioning Phase)
- Tube Sheet Flow Control Valve
- Reflector Blocks i
Core Support Post & 3 eat
- Core Barrel Seals Core Barrel Spring Posts
- Hot Gas Duct & Insulation Class C losulation
- Helium Transfer & Recirc.
Compressors l
i Plant, System & Component Operation and Maintenance History l
Detailed Visual Inspection of Upper Plenum l
NRC, 00E, PSC Meeting on Technology Transfer - October 26, 1989 Fuel Test Elements and Graphite Performance l
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Future Implementation of Technology Transfer Task Team Final Resolution of Technology Transfer Scope Incorporation of Scope into FSV Defueling & Decommissioning Schedule:
FSV Schedule:
November 26 - End of 100-Day Cooldown November 27 - Comence befueling August 1990 - Proposed Decommissioning Plan Submitted to NRC December 1991-Defueling Complete Begin Control Rod & Helium Circulator Removal Component Removal Complete June 1992 3