ML20095K975
| 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)
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 ACTIVATED CONCRETE REMOVAL Page 4
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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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% 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:
l l
- 289 Survey Packages 1
- 100,300 Measurement Locations
- 390,900 Measurements f
Page 13
l l
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 2 New Spent Fuel Shipping Casks
- 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 %
- NRC Concurrence Will Be Requested in Accordance With Information Notice 89-25 l
l l
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
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
l Page 21
1 SUPPLEMENTAL INFORMATION
- STAFFING CHART e
l Page 22
FORT ST. VRAIN 1
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