ML20138G729

Summary of 961203 Meeting W/Psc in Plattville Co Re Decommissioning & License Termination of Fsv.Slides,Encl

ML20138G729
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/03/1996
From:	NRC COMMISSION (OCM)
To:	NRC COMMISSION (OCM)
References
NUDOCS 9701020225
Download: ML20138G729 (34)

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* "*%

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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  !

• Public Service Company (PSC) Of Colorado, Licensee

- 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

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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

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United States Nuclear -

Regulatory ~Comniission

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L D. Blair Spitzberg, Ph.D.

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= INSPECTION PRO.CEDURES Implemented During; Fort St. Vrain ,

... x Debommissi.oning:' -

, INSPECT 10N PROCEDURE MCDULE NUMBERS

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m i I I I S 42700 62702 81018 83000  !

e 9ertOperatiors Martenesco Pogram Security Plai Oossoutleapedon i 6 Impemerstg Proaxbres Survey i z .

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"- 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

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-;l FORT ST. VRATK &

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PUBLIC MEETING ,,

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-i Mary J. Fisher gl 1:

Decommissioning Program Director Public Service Company ofColorado $2; E!

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AGFNDA v ro , l I

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+ Background s,

+ Spent Fuel Disposition g s

+ Dismantlemem Methodology .

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+ Safety and Radiological Performance r

+ FinalRadiological Survey :l w

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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

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BACKGROUND (Continued) 9

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+ Factors Behind 1989 Shutdown: a m:

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- Poor operationalperformance w

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- 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

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SPENT FCEL DISPOSITION E g

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+ 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

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+ 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

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i; SPENT FLEL DISPOSITION (Continued) j]

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+ PSCo decided to build Independent Spent Fuel ij StorageInstallation(TSFSI?: "

- Passively cooled, Modu: ar Vault Dry Store system

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- 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

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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 .

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+ 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

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PERFORMANCE 5!

+ OccupationalRadiation Exposures (Person-REM): !i

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- Total Estimate 433 perDecommissioning Plan ;j

- Actual Project Exposure 380 i 0

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PERFORMANCE (Continued) [

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+ Low Level Radioactive Waste Shipping (Cu. ft.) ij

- Total project estimate 290,000 l

- Actual volume shipped 289,600 p 2

+ FSV shipments:

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- 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 ]

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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  !!

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- Typical Construction Projects 132 0!

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_ - - _ - - - - - - - - - - - - - - _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - --_ ____--____i

i ot S!

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m FINAL RADIOLOGICAL SURVEY .-

+ Documents that decontamination efforts met project ij acceptance criteria [

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. + 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

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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 _-___------ -_-__--_ ________-_-______-_-_--____- -- ________