ML20095K975

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Fort St Vrain Project Update Presentation to NRC, on 951207 & 15
ML20095K975
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/15/1995
From:
PUBLIC SERVICE CO. OF COLORADO
To:
References
NUDOCS 9512290351
Download: ML20095K975 (24)
v • d • e


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)

L____________________________________ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

AGENDA

  • Decommissioning Status Safety and Radiological Performance

- Final Release Survey

  • Spent Fuel Status -- DOE Agreement
  • PSCo Corporate Merger
  • Repowering Status
  • Present Concerns l
  • Conclusions 1

l 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 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
  • 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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% CUT COMPLETE PREPARED BY BOB GUNNERSON

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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:

l (Cubic Feet Shipped from FSV) l l

l Total Project Estimate 245,000 Shipped to 12/1/95 218,600

  • 71,380 Curies l
  • 442 Shipments 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 />):

FSV 0.47 l 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 />):

l l FSV 45.7 l l i 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

Page 13

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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)

> FSV SGLVs are 4,000 dpm/100 cm2(Average),

12,000 dpm/100 cm 2(Individual)

> All Measurements Are Expected < 50,000 dpm/100 cm 2After 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 Reduced Below 100,000 dpm/100 cm 2

> 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

S. CONCLUSION l

  • 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 i > Survey Packages Were Thorough, Although 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 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., Maintenance, Defueling, Decommissioning, Regulatory Changes l

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 %

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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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Page 18

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

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  • PSCo APPRECIATES NRC'S PROFESSIONALISM AND l DEDICATION DURING FSV DECOMMISSIONING PROJECT I

l Page 21

1 SUPPLEMENTAL INFORMATION

  • STAFFING CHART e

l Page 22

FORT ST. VRAIN 1

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