ML20095K975

Fort St Vrain Project Update Presentation to NRC, on 951207 & 15

ML20095K975
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/15/1995
From:	PUBLIC SERVICE CO. OF COLORADO
To:
References
NUDOCS 9512290351
Download: ML20095K975 (24)

Text

ENCLOSURE 2 FORT ST. VRAIN PROJECT UPDATE Presentation to tite Nna6lee?

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FORT ST. VRAIN UPDATE l

PUBLIC SERVICE COMPANY OF COLORADO PRESENTATION TO THE s

NUCLEAR REGULATORY COMMISSION December 7,1995 (Washington)

December 15,1995 (Region IV)

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AGENDA Decommissioning Status Safety and Radiological Performance Final Release Survey Spent Fuel Status -- DOE Agreement PSCo Corporate Merger Repowering Status Present Concerns Conclusions l

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l Supplemental Information Page 1

DECOMMISSIONING STATUS Page 2

PRESTRESSED CONCRETE REACTOR VESSEL (PCRV)

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PCRV FINAL DISPOSITION Page 5 L.___.

DECOMMISSIONING STATUS PROGRESS SINCE MAY 1995:

Removal of 12 Steam Generators Complete Removal of Activated Upper Beltline Concrete Complete Removal of Fuel Storage Wells Complete Removal of Shield Water System Complete, Release of Shield Water Complete Final Survey of Buildings Outside Restricted Area Complete PCRV and BOP Dismantlement, Decontamination Activities Are Approximately 90% Complete Characterization Surveys and Decontamination of Reactor Building Structures and Systems Are in Progress Page 6

DECOMMISSIONING STATUS REMAINING ACTIVITIES:

Removal of Lower Beltline Concrete from PCRV Removal of Lower Plenum insulation Decontamination of Embedded Piping and PCRV Internal Surfaces Characterization and Decontamination of Reactor Building Surfaces and Systems Remove Reactor Building Ventilation System and Liquid Waste System Final Radiological Survey l

Turbine Building Surfaces Buildings and Areas inside Restricted Areo Unaffected Systems Effluent Pathways Reactor Building Surfaces Affected Systems Open Land Areas l

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SAFETY AND RADIOLOGICAL PERFORMANCE OCCUPATIONAL RADIATION EXPOSURES:

(Person-REM)

Total Estimate per Decommissioning Plan 433 Expected Total Project Dose 392 Actual Dose to 12/1/95 366 l

l LOW LEVEL RADIOACTIVE WASTE SHIPPING:

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Total Project Estimate 245,000 l

Shipped to 12/1/95 218,600 71,380 Curies 442 Shipments l

l Page 11

SAFETY AND RADIOLOGICAL PERFORMANCE (Continued)

TIME WORKED IN RADIOLOGICALLY CONTROLLED AREAS (RCA):

(Porson-Hours)

Actual RCA Hours to 12/1/95 573,000 Original Project Estimate 367,100 (per Decommissioning Plan)

PERSONNEL CONTAMINATIONS:

(Contaminations per 10,000 RCA hours)

FSV 4.5 PWR Outages 6.5 BWR Outages 14.5 l

LOST WORKDAY INDICATORS:

Only 3 Lost Time Work injuries Lost Work Day incidence Rate (per 200,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />):

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Typical Construction Projects 6.9 (National Bureau of Labor Statistics)

Severity Rate (per 200,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />):

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FSV 45.7 l

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Typical Construction Projects 132 Page 12

FINAL RELEASE SURVEY 1.

REMAINS MAJOR CHALLENGE OF PROJECT 2.

PROGRAM OVERVIEW:

FSV Buildings, Systems, and Land Areas Divided into 9 Survey Groupings Groups A through I include:

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289 Survey Packages 1

100,300 Measurement Locations 390,900 Measurements f

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l FINAL RELEASE SURVEY (Continued) 3.

EMBEDDED PIPING REPRESENTS SIGNIFICANT CHALLENGE 30,000 feet of Small Diameter Piping 5% of Measurements May Exceed Fixed Contamination Site Specific Guideline Values (SGLV) 2 FSV SGLVs are 4,000 dpm/100 cm (Average),

2 12,000 dpm/100 cm (Individual)

All Measurements Are Expected 50,000 2

dpm/100 cm After Aggressive Decontamination PSCo/WT Submitted Proposed Treatment on October 12,1995:

Aggressive Decontamination Fill Piping With Grout That Exceeds SGLVs NRC Approval of Measurements That Cannot Be 2

Reduced Below 100,000 dpm/100 cm Requested Approval By December 31,1995 Dose Consequences 2.4 mrem Per Year from 2

100,000 dpm/100 cm Cost of Additional Decontamination or Removal Efforts to Meet SGLVs is From $3.1 Million to $33.9 Million

-- Not ALARA Page 14

FINAL RELEASE SURVEY (Continued) 4.

BACKGROUND Widely Varying Background Complicates Demonstration That Exposure Rate Meets Release Criteria Release criteria is 5 pR/hr above background Background varies from 5 - 30 pR/hr WT developing methodology including use of in situ gamma spectrometer Need to Ensure NRC's Confirmatory Survey Uses Same Survey Protocol, Groundrules as PSCo l

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NRC Inspected Final Survey Program September 25-28 Reviewed Procedures and Records ORISE Performed independent Field Measurements GPU Independent Measurements Were Consistent With SEG, Expect Consistent with ORISE NRC Found that Program Was Being implemented l

in Sound Manner Survey Packages Were

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incomplete At Time of Inspection PSCo Appreciates NRC Efforts to Perform Confirmatory Survey in Parallel With PSCo/WT Final Survey Significant Savings in Time and Possible Rework Excellent Communications With NRC Staff Page 15

SPENT FUEL STATUS - DOE AGREEMENT PSCO AND DOE HAVE REACHED AGREEMENT IN PRINCIPLE DOE Takes Title to All FSV Fuel in ISFSI DOE Takes Title to ISFSI When 10 CFR 72 License Transfer Occurs, With NRC Approval DOE Takes Title to 2 New Spent Fuel Shipping Casks DOE Pays PSCo $16 Million of ISFSI Costs DOE Responsible For All Future Costs Before and After Title

Transfer, e.g.,

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Decommissioning, Regulatory Changes l

l Page 16

PSCo CORPORATE MERGER 1

On August 23,1995, PSCo and Southwestern Public Service Company (SPS) of Amarillo, Texas Announced Intent for Merger, Under New Holding Company PSCo Will Remain an Entity Under New Holding Company, and Will Retain Existing Licenses Current Financial Assurance Provisions Unchanged SPS Has Substantial Generating Capacity with Primarily Coal and Natural Gas -- No Nuclear Involvement PSCo Will Own 61.9 % of Common Equity of New Holding Company: SPS Will Own 38.1 %

NRC Concurrence Will Be Requested in Accordance With Information Notice 89-25 l

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l Page 17

l REPOWERING STATUS l

l PROJECT CONSTRUCTION IS PROCEEDING ON SCHEDULE Combustion Turbine and Generator Arrived On-site By Rail On September 6,1995 Installation 45% Complete Natural Gas Pipe Installation in Progress NRC Approval Received July 31,1995 First Ignition Startup Test Scheduled for February 2, 1996 a

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l PRESENT DECOMMISSIONING CONCERNS Completion of Final Survey for Site Release Approval of Embedded Piping Treatment Confirmation That Established FSV Site Release Criteria Will Not Be Subject to Change Final License Termination Process l

Successful Completion of ISFSI License Transfer to DOE Page 19 l

CONCLUSION FORT ST. VRAIN DECOMMISSIONING IS PROGRESSING WELL RADIOLOGICAL AND INDUSTRIAL SAFETY PERFORMANCE IS EXCELLENT THE PROJECT WILL BE COMPLETED AHEAD OF PROGRAM SCHEDULE AND UNDER BUDGET 1

PSCo APPRECIATES NRC'S PROFESSIONALISM AND l

DEDICATION DURING FSV DECOMMISSIONING PROJECT I

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1 SUPPLEMENTAL INFORMATION STAFFING CHART e

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FORT ST. VRAIN DECOMMISSIONING STAFF LEVELS 1

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