|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20077P9291991-08-15015 August 1991 Final Rept, Verification of Fort St Vrain Activation Analysis ML20072V5031991-04-12012 April 1991 Summary of Existing & Planned Work for Activation Verification,910415 ML20029B6731991-03-0505 March 1991 Nonproprietary Estimated Blast Effect from Ft St Vrain Well 11 Analysis Methods Summary. ML20059L5921990-09-13013 September 1990 Determination of Upper Bounds on Radiation Exposure Rates at Refueling Floor Above Defueled Region W/Crd Orifice Assemblies Radiation Shielding Removed ML20042F9071990-05-0101 May 1990 Conceptual Plan & Cost Estimate for Early Dismantlement of Fort St Vrain Pcrv. ML19332E8181989-12-0101 December 1989 Rev a to Fort St Vrain Site-Specific Decommissioning Cost Estimate Basis for Preliminary Decommissioning Plan. ML19332C2831989-10-0909 October 1989 Fort St Vrain 3-D Neutron Source Analysis Using DIF3D. ML19332E8191989-08-31031 August 1989 Rev a to Fort St Vrain Activation Analysis. ML20245L4061989-08-31031 August 1989 Safety Analysis Rept for Reactor Defueling ML20246K1321989-07-31031 July 1989 Pcrv Tendon Surveillance Rept for Jul 1989.W/four Oversize Drawings ML20245J3261989-06-14014 June 1989 Rev B to Evaluation of Cable/Equipment Separation for Bearing Water Pumps P-2101-S,P-2102 (Train B),P-2102-S (Train B) & P-2107 (Train B) for App R Requirements ML20245C4581989-05-11011 May 1989 CRD Partial Scram Test Results & Max Daily Temp Rept, 890511-0531 ML19332E8211989-02-23023 February 1989 Fort St Vrain Plateout Analysis for Decommissioning Study. ML20206K1111988-11-21021 November 1988 Rev a to Engineering Evaluation of Interaction & Effects of Plant Protection Sys & Steam Line Rupture Detection/ Isolation Sys ML20154E0981988-08-31031 August 1988 Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings ML20077B9091988-05-31031 May 1988 Vols I & II of Activation Analysis ML20154A5451988-04-28028 April 1988 Integrated Sys Study of CRD Mechanism Rod Position Instrumentation ML20154A5501988-04-28028 April 1988 Temp Prediction for CRD Mechanism Motors ML20235A5591988-01-31031 January 1988 Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings ML20148G7941988-01-22022 January 1988 Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities ML20148G8511988-01-22022 January 1988 Helium Circulator Insp Schedule ML20195H8731988-01-14014 January 1988 Final Rept on Fort St Vrain 871002-03 Fire ML20236J2911987-10-30030 October 1987 Preliminary Rept on Impact of Fort St Vrain 871002 Fire ML20235H4731987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification for Returning to Power Operation ML20235K2721987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage Including Licensing Assessment ML20195G9681987-08-11011 August 1987 Analyses Re Fort St Vrain DBA-2 Core Damage Frequency ML20235W6091987-07-31031 July 1987 Pcrv Tendon Interim Surveillance Rept ML20234C1091987-06-25025 June 1987 Issue B to Effect of Firewater Cooldown Using EES Bundle on Steam Generator Structural Integrity ML20214Q9981987-05-31031 May 1987 Verification Rept for Buckle Computer Program ML20215J8711987-05-0404 May 1987 Rev a to Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling ML20214P3381987-04-30030 April 1987 Rev 3 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 4, Exemptions & Mods ML20214P3141987-04-30030 April 1987 Rev 5 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 2, Electrical Reviews ML20214P3061987-04-30030 April 1987 Rev 7 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 1, Shutdown Model 1997-04-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado. W/940405 Ltr ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning. ML20045A4291993-06-0303 June 1993 LER 93-003-00:on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well operator.W/930603 Ltr ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 ML20092D0081992-01-31031 January 1992 Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station ML20102B2241992-01-22022 January 1992 Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122 ML20094N6701991-12-31031 December 1991 Public Svc Co Annual Financial Rept for 1991 ML20091J6251991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ ML20094D6711991-11-30030 November 1991 Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1 ML20090M1871991-11-20020 November 1991 FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan ML20086D6891991-11-15015 November 1991 Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ 1997-07-01
[Table view] |
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
l l
- Supplemental Information Page 1
DECOMMISSIONING STATUS Page 2
PRESTRESSED CONCRETE REACTOR VESSEL (PCRV)
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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
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
- 100,300 Measurement Locations
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 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 %
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
- 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
l Page 21
1 SUPPLEMENTAL INFORMATION
l Page 22
FORT ST. VRAIN 1
l DECOMMISSIONING STAFF LEVELS l Legend W WESTINGHOUSE TEAM CONTRACT EMPLOYEES PSC EMPLOYEES soo 700 k k i
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