ML20133D766
| ML20133D766 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/16/1996 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20133D763 | List: |
| References | |
| PROC-960916, NUDOCS 9701100060 | |
| Download: ML20133D766 (16) | |
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CONFIRMATORY SURVEY PLAN FOR THE FORT ST. VRAIN NUCLEAR STATION PUBLIC SERVICE COMPANY OF COLORADO PLATTEVILLE, COLORADO INTRODUCTION l
Public Service Company of Colorado (PSC) operated a 330 MWe High Temperature Gas Cooled Reactor (HTGR) from July 1979 until August 1989. The plant, designated as the Fort St. Vrain Nuclear Station (FSV), was authorized for construction on September 17,1968 when the U.S.
Nuclear Regulatory Commission (NRC) issued a provisional construction permit. Construction was completed in December 1973 and a facility operating license, Docket No. 50-267, License DPR-34, was granted on December 21,1973. Fuel loading commenced on December 26,1973 and initial criticality was achieved January 31,1974. After a prolonged period of startup testing, low-power operation and plant modifications, the plant was committed for commercial operation on July 1, 1979. Full power was achieved November 6,1981 (PSC 1995a).
In the nuclear steam supply system for FSV, heat was produced by fission in the HTGR utilizing a uranium-thorium fuel cycle. Graphite was used for the moderator, core structure, and reflector.
High temperature helium was used as the primary coolant to produce superheated and reheated steam at a temperature of 1,000 F to match conventional thermal station conditions. The entire nuclear steam supply system, including the reactor core, graphite moderator and reflector, steam generators and helium circulators, was contained within a Prestressed Concrete Reactor Vessel (PCRV).
During the time frame of operation, FSV operated for approximately 890 effective full-power days.
FSV was shutdown on August 18,1989, the PSC Board of Directors reviewed and confirmed the Executive Management decision that FSV would not be restarted, and that PSC would pursue i
Prepared by the Environmental Survey and Site Assessment Program, Environmental and Health Sciences Division, Oak Ridge Institute for Science and Education, under interagency agreement (NRC FIN No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Department j
of Energy.
Fort St. Vrain Nuclear Station September 16.1996 hAessaptplansisvplani.002 9701100060 960916 PDR ADOCK 05000267 H
decommissioning of FSV. The decision to permanently shutdown and decommission FSV was based on related technical and fmancial considerations. Problems were identified with the control rod drive assemblies and the steam generator ring headers that presented significant technical obstacles which could be overcome, but at significant cost in dollars and time to PSC. In addition, due to the uniqueness of the HTGR fuel cycle, the cost to purchase new fuel was prohibitive. This, in conjunction with low plant availability and correspondingly high operating costs, made continued operation of FSV imprudent.
1 PSC's objective is the dismantlement and decommissioning of FSV to release all site areas for i
i unrestricted use. To accomplish this, a portion of the PCRV structure and the radioactive balance-of-plant equipment which exceed the limits for unrestricted use will be decontaminated or removed as described in the Fort St. Vrain Decommissioning Plan. In May,1991 a 10 CFR 50 Possession Only License was granted by the NRC. On November 23,1992, the NRC issued the Order to Authorize Decommissioning of Fort St. Vrain and Amendment No. 85 to Possession Only License No. DPR-34 (PSC 1995b).
The radiological status of the FSV facility and environs has been evaluated in the FSV Initial Radiological Site Characterization Report in order to provide information pertinent to the decommissioning and final survey of FSV (PSC 1992). There were no spills or accidents during operation of FSV which had the potential of contaminating the site.
The Radiological Environmental Monitoring Program (REMP) will be continued throughout the decommissioning to ensure that any contamination of the site environs which could occur as a result of decommissioning activities is detected.
The FSV facility will be largely left intact following decommissioning. Dismantlement of structures will be confined to the PCRV, and portions of the Reactor Building, Turbine Building, and Liquid Waste System. Removal will be for purposes of removing contaminated structures and to provide paths for removal of contaminated piping and equipment.
2 Fort St Vram Nudear Station. September 16.1996 33e,,p. i o f,vpi ni.co2 p
.e.
Following defueling, the PCRV contained the majority of the remaining radioactive material inventory. Portions of the PCRV concrete are activated due to direct irradiation from the reactor core, and will be removed prior to final survey and disposed of as radioactive waste at a licensed radioactive waste disposal facility. Thus, the radioactive source term at FSV is primarily a result of neutron activation of both metallic and concrete components of the PCRV and neutron activation ofimpurities contained in graphite components of the PCRV. These activation products include beta-gamma emitters such as Co-60, Eu-152, and Eu-154, and low-energy beta and x-ray emitters such as 11-3, C-14, and Fe-55. It should be noted that II-3 and Fe-55 are the largest contributors to the total radionuclide inventory (PSC 1995a).
l To date, seventeen balance-of-plant systems have been identified as being contaminated in excess of the limits for unrestricted use. All piping and equipment contaminated in excess of the limits for unrestricted use will be decontaminated and left in-place, decontaminated and free-released, or dismantled and removed from the facility and disposed of as radioactive waste at a licensed radioactive waste disposal facility.
FSV's final survey will include all pertinent structures, surfaces, systems and components, concentrating on those previously identified as contaminated or potentially contaminated during the dismantlement / decommissioning phases. The final survey will include:
Sampling outside the restricted area of PSC property, soil, pavement, water, and liquid effluent ditch and pond sediment for radioisotopic analysis and measurement of gamma exposure rate, Sampling inside the restricted area of PSC property, soil, basin sediment, pavement and water for radioisotopic analysis and measurement of gamma exposure rate, Radiological surveys of the PCRV and Reactor Building, and a
3 Fort St. Vrmn Nuclear Station September 16,19%
u,mpspi,onopioniw
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Radiological surveys of the Turbine Building, Radwaste Compactor Building, New Fuel Storage Building, Radiochemistry Laboratory, Ilelium Transfer and Storage System, and Liquid 1
l Radwaste System.
At the request of the NRC's Division of Waste Management, the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) performed an independent confirmatory survey of the repower area in March 1995 at the Fort St.
Vrain site in Platteville, Colorado (ORISE 1995a). Subsequent independent survey activities included licensee survey package reviews, confirmatory surface scans, and comparison surface activity measurements (e.g., side-by-side measurements) performed from September 25 through 27, 1995 (ORISE 1996a). During the period January 22 through 25,1996, ESSAP performed instrument comparison activities-including side-by-side surface activity measurements and surface scans-and reviews of the licensee's embedded piping program and planned use ofin situ gamma spectrometry for determining the licensed material contribution to exposure rate (ORISE 1996b).
The NRC's Division of Waste Management has requested that ESSAP perform independent confirmatory surveys activities relating to the site areas comprised in FSV's first final survey report submittal-Volumes 1 through 5-and other areas designated by NRC (PSC 1996).
SITE DESCRIPTION The FSV facility is located approximately 56 kilometers (35 miles) north of Denver and 5.6 kilometers northwest of the town of Platteville, in Weld County, Colorado. The site is located in an agricultural area with gently rolling hills. Grade elevation at the plant is 1,460 meters (4,790 feet) above sea level. The site consists of 6995 hectares (17,300 acres) owned by PSC, identified as the Owner-Controlled Area, of which approximately one square mile was designated as the exclusion area during plant operation. Farming has been continued on Owner-Controlled areas of the site, but there are no farming operations or permanent residences located within the Restricted Area. The Restricted Area is surrounded by a Security fence, and access is controlled for purposes of protection ofindividuals from exposure to radiation.
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l Fort St. Vrain Nuclear Station - September 16.1996 h%ssap' plans' fsyplan t.002
The station is located approximately two miles south of the confluence of the South Platte River and the St. Vrain Creek. Neither of these two streams are considered navigable. Cooling for the plant is provided by mechanical draft cooling towers. Make-up to the cooling towers is obtained from the two streams, and is supplemented by shallow well water. Nineteen shallow wells are located on the site. The licensee also owns surface water rights in four irrigation ditches which traverse portions of the site.
The major structures within the Restricted Area include the Reactor Building which contains the PCRV, Turbine Building, Radwaste Compactor Building, New Fuel Storage Building, Technical Support Building which contains the Radiochemistry Laboratory, Mechanical Draft Cooling Towers, Warehouse and Construction Workshops, Evaporation Ponds, and the Electrical Switchyard. The ground surface covering within the Restricted Area is composed primarily of gravel and vegetation, with smaller portions devoted to concrete or asphalt roadways and laydown areas.
OBJECTIVES The objectives of the confinnatory survey are to provide independent contractor field data reviews and radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and final status survey results. Confirmatory survey activities will also provide the NRC with independent contractor reviews oflicensee decommissioning program elements.
RESPONSIBILITY Work described in this survey plan will be performed under the direction of William L. (Jack) Beck, Program Director and Eric W. Abelquist, Assistant Program Director with ESSAP. The cognizant site supervisor has the authority to make appropriate changes to the survey procedures as deemed necessary. After consultation with the NRC site representative, the scope of the survey may be altered based on findings as the survey progresses.
5 hat, sap pianstrispiani.co2 Fort St. Vrmn Nudear Station - September 16.1996
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DOCUMENT REVIEW j
l ESSAP has reviewed the licensee's fmal status survey documentation for those survey units contained within Volumes 1 through 5 (PSC 1996). Review of additional documentation will be dependent upon findings as the surveys progress. Documents were reviewed for adequacy, accuracy, completeness, and consistency. Data were reviewed for appropriateness of calculations and interpretations relative to the guidelines and a comment letter documenting fmding submitted to the NRC (ORISE 1996c).
PROCEDURES A survey team from ESSAP will perfonn independent visual inspections, measurements, and sampling of building surfaces and structures, plant systems, and open land areas associated with the first submittal of the FSV Final Survey Report (Volumes 1 through 5) and other areas designated by NRC. Approximately 5 percent of the completed survey units for building surfaces and structures, and plant systems, will be selected both randomly and based onjudgement by ESSAP for independent confirmatory survey activities. This breakdown will include 2 survey units from Group A areas,3 survey units from Group B areas,6 survey units from Group C areas, and I survey unit from Group D areas. Additional scan surveys may be performed in other survey units not included in Groups A through D. Field survey activities will be conducted in accordance with the applicable sections of the ESSAP Survey Procedures and Quality Assurance Manuals (ORISE 1995b and c).
Specific procedures are listed on pages 12 and 13 of this plan.
TECIINICA1, ASSISTANCE ACTIVITIES As directed by the NRC, ESSAP will provide technical assistance to assist the NRC in their inspection oflicensee decommissioning-related activities. Technical assistance activities will be determined through consultation with the NRC site representative and may include instrument comparison measurements, review of decommissioning program elements, and other activities deemed appropriate by the NRC.
b h Mssap' plans'fsvplan t.002 Fort St. Vrain Nuclear Station. September 16,1996
SURVEY PROCEDURES The following procedures apply to survey units selected for independent confirmatory activities.
Referente System The reference systems established by FSV will be used by ESSAP for referencing measurement and sampling locations. The grid size or reference interval established by FSV for a given survey unit is dependent upon the classification of the survey unit (affected versus unaffected) and surface (floor, lower wall, upper wall, ceiling, equipment, or plant system). Measurement and sampling locations on ungridded surfaces will be referenced to prominent building features or the existing grid.
Surface Scans Surface scans for beta and gamma activity, will be performed over 100% of floor and lower wall surfaces and up to 50% of equipment surfaces, within each building surface and structure survey unit selected for confirmatory survey activities. Scans for alpha activity may be performed in those survey units that have some potential for alpha contamination-e.g., areas were fuel was handled or stored. Additional scans may be perfonned over portions of upper wall, ceiling, and plant system surfaces as well as locations, such as drains and ductwork, where material may have settled or accumulated. Locations of elevated direct radiation identified by scans will be marked for further investigation. Scans will be performed using gas proportional, GM, ZnS, and/or Nal scintillation detectors coupled to ratemeters or ratemeter-scalers with audible indicators.
Surface Activity Measurements For each building surface and plant system survey unit selected, ESSAP will perform a minimum of thirty direct measurements for total beta surface activity. ESSAP will also perfomi additional direct measurements at locations of elevated direct radiation detected by surface scans. At measurement locations, where the average NRC surface contamination guideline is exceeded, the 7
Fort St. Vrain Nuclear Station - Septeniber 16.1996 hSessap plansIsvplant.002
9 size of the contaminated area and the average activity in the contiguous 1 m area will also be 2
determined. Total alpha surface activity measurements may also be performed at each direct measurement location for survey units that exhibit the potential for alpha contamination.
Measurements will be performed using GM, gas proportional, and/or ZnS detectors coupled to ratemeter-scalers.
A smear sample for determining removable activity level will be collected from each direct measurement location.
Exposure Rate Measurements A minimum of five exposure rate measurements will be performed within each survey unit. All exposure rates will be measured at I meter above surfaces using a pressurized ionization chamber (PIC). Background exposure rates will be determined from a minimum of ten locations within a building of similar construction, but without a history of radioactive materials use.
Miscellaneous Sampline Miscellaneous samples may be collected from cracks, ledges, piping, ducts, and drains, where material may have accumulated.
SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data will be returned to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for analysis and interpretation. Direct measurements for surface activity will be converted to units of 2
disintegrations per minute per 100 square centimeters (dpm/100 cm ). Smears will be analyzed for gross alpha and gross beta activity using a low background gas proportional counter, and the results 2
will be converted to units of disintegrations per minute per 100 square centimeters (dpm/100 cm ),
Some smear samples will be analyzed for H-3 and Fe-55 activity. Exposure rate measurements will be measured and reported in units of pR/h. Miscellaneous samples will be analyzed by gamma 0
h%ssap plans fsvplant 002 Fort St. Vrain Nudear Station. September 16,1996
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spectrometry and/or alpha spectrometry. The radionuclides of interest are Co-60 and Cs-137; l
however, spectra will be reviewed for other identifiable photopeaks. Sample analyses will be performed in accordance with the ORISE/ESSAP Laboratory Procedures Manual (ORISE 1995d).
Gamma spectrometry data will be reported in pCi/g for solid samples or pCi/L for liquid samples.
The data generated will be compared with the licensee's documentation and NRC guidelines l
established for release for unrestricted use. Results will be presented in a report and provided to the 1
NRC.
DATA EVALUATIONS AND COMPARISONS The results of each survey unit sampled will be statistically tested. The goal of the test is to determine, with a given confidence level, that the FSV survey data is not biased low compared to ESSAP. The null hypothesis will be that in a survey unit, surface activities or soil concentrations, as calculated by FSV are greater than or equal to those determined by ESSAP, i.e., H : Prsv 2 PESSAP-o For surface activity comparisons, it should be noted that side-by-side comparisons performed during a previous ESSAP site visit (ORISE 1996b), have determined that ESSAP's measurements are biased low as compared to FSV's measurements. The likely explanation for this bias is that ESSAP and FSV used different source-to-detector spacings during calibration-ESSAP calibrates in contact with the source (about 0.10 cm), while FSV calibrates at a spacing of 0.27 cm; a difference that may increase the ESSAP efficiency relative to the FSV efficiency by a couple of percent.
i This hypothesis will be tested at the 95% confidence level (0.05 level of significance). If the hypothesis is rejected at that confidence level, the alternative hypothesis will be accepted i.e., II A Prsv < PESSAP. The test statistic, t, will be calculated using the following equation:
'Ys _ X, (n -1)S' + (n -1)S * ' n, + n g
g g
g "E
A "LE F
F )
g l
I I
l 9
fort St Vrain Nudcar Station. September 16,1996 h \\essap'plansIsvplanlM2
a,.
where:
Xr is the FSV mean for a survey unit Xu is the ESSAP mean for the same survey unit is the number of FSV measurement / sampling data points nr is the number of ESSAP measurement / sampling data points ne Sr.Se are the standard deviations for the FSV and ESSAP measurement data, respectively.
The calculated I is then compared to the critical value of Student's t-distribution (one-tailed) for the appropriate degrees of freedom at the 95% confidence level (0.05 level of significance). If the Hj Prsv 2 PESSAP is rejected, then ESSAP will evaluate additional options and alternatives and confer with the NRC as to the recommended approach.
GUIDELINES The primary contaminants of concem for this site are beta-gamma emitters resulting from the operation of the FSV facility. The applicable NRC guidelines for beta-gamma emitters in unaffected areas are (NRC 1974):
Total Activity 2
2 5,000 dpm/100 cm averaged over a 1 m area 2
2 15,000 dpm/100 cm maximum in a 100 cm area Removable Activity 2
1,000 dpm/100 cm The guideline values for radionuclide concentrations in soil are the radionuclide-specific concentrations which could result in an average annual total effective dose equivalent (TEDE) of 10 mrem to an individual in a population group exposed to radioactive material following decommissioning. These values will be determined in accordance with the methodology contained in NUREG/CR-5512, Volume 1 and as presented in NUREG-1500 (NRC 1992 and 1994a).
10 hussar pians rivpiani co2 Fort St. Vrain Nuclear Station. September 16, im
t.,
The exposure rates guideline, measured at 1 meter above the surface, is 5 pR/h above background (NRC 1988).
The NRC has approved site-specific allowable surface contamination guidelines for H-3 and Fe-55, particularly in activated concrete and steel (NRC 1994b). These guidelines are:
Total Activity 2
2 200,000 dpm/100 cm, averaged over 1 m 2
2 600,000 dpm/100 cm, maximum in a 100 cm area Removable Activity 2
1,000 dpm/100 cm FSV has assessed the radionuclide composition at the site and determined the site-specific surface activity guideline for affected areas. The effective beta gamma surface contamination limits are:
Total activity 2
2 4,000 dpm/100 cm, averaged over a 1 m area j
i 2
2 12,000 dpm/100 cm, maximum in a 100 cm area Removable activity 2
750 dpm/100 cm TENTATIVE SCIIEDULE l
Document Review August 1996 Confirmatory Survey October 7 to 10,1996 Sample Analysis October 1996 Draft Report December 1996 i
I Fort St Vrain Nudear Station - September 16, im 11 h%ssap'planstfsyplant 002 I
I
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LIST OF CURRENT PROCEDURES Applicable procedures from ORISE ESSAP Survey Procedures Manual (Revision 9; April 30,1995) include:
Section 5.0 Instrument Calibration and Operational Check-Out 5.1 GeneralInformation 5.2 Electronic Calibration of Ratemeters 5.3 Gamma Scintillation Detector Check-Out and Cross-Calibration 5.4 Alpha Scintillation Detector Check-Out and Cross-Calibration 5.5 GM Detector Calibration and Check-Out 5.6 Proportional Detector Calibration and Check-Out 5.8 Pressurized Ionization Chamber Calibration and Check-Out 5.10 Floor Monitor Check-Out 5.13 Field Measuring Tape Calibration Section 6.0 Site Preparation 6.2 Reference Grid System Section 7.0 Scanning and Measurement Techniques 7.1 Surface Scanning 7.3 Alpha Radiation Measurement 7.4 Beta Radiation Measurement 7.5 Gamma Radiation (Exposure Rate) Measurement Section 8.0 Sampling Procedure 8.7 Determination of Removable Activity 8.8 Miscellaneous Sampling 8.9 Sample Identification and Labeling Section 9.0 Integrated Sun'ey Procedures 9.2 General Survey Approaches and Strategies i
12 Fort St. Vram Nuclear Statmn. September 16.1996 hw. ppiansw.vpiant oo2
9 s.
s Section 10.0 Health and Safety Control of Cross Contamination l
Section 11.0 Quality Assurance and Quality Control Applicable procedures from the ORISE/ESSAP Quality Assurance Manual (Revision 7; January 31, 1995) include:
Section 5 Training and Certification Section 6 Equipment and Instrumentation Section 7 Quality Control Section 8 Sample Chain-of-Custody Section 9 Data Management Section 10 Data Review and Validation j
Section 1i Records Handling and Storage l
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a 13 Fort St Vrain Nuclear Statmn September 16,1996 ug,,,,,1 pion, r,vpian i.oo2
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I REFERENCES Oak Ridge Institute for Science and Education (ORISE). Confirmatory Survey for the Repower l
Area, Fort St. Vrain, Platteville, Colorado. Oak Ridge, TN; June 1995a.
Oak Ridge Institute for Science and Education. Survey Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, Tennessee; April 30,1995b.
Oak Ridge Institute for Science and Education.
Quality Assurance Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 7. Oak Ridge, Tennessee; January 31,1995c.
Oak Ridge Institute for Science and Education.
Laboratory Procedures Manual for the Energy / Environment Systems Division, Environmental Survey and Site Assessment Program, Revision 9. Oak Ridge, Tennessee; January 31,1995d.
Oak Ridge Institute for Science and Education. Final Report--ORISE Support of NRC License Inspection at Fort St. Vrain on September 25 to 27,1995. Oak Ridge, TN; March 1996a.
Oak Ridge Institute for Science and Education. Final Report--ORISE Support of NRC License Inspection at Fort St. Vrain on January 22 to 25,1996. Oak Ridge, TN; March 1996b.
Oak Ridge Institute for Science and Education. Document Review--Fort St. Vrain Nuclear Station Decommissioning Project Final Survey Report (Volumes 1 through 5), Fort St. Vrain, Platteville, Colorado. Oak Ridge, TN; August 1996c.
Public Service Company of Colorado (PSC). Fort St. Vrain Initial Radiological Site Characterization Report. April 30,1992.
Public Service Company of Colorado. Final Survey Plan for Site Release, Revision 1. May 25, 1995a.
Public Service Company of Colorado. Final Survey Report for Release of Repower Area. March 2, 1995b.
Public Service Company of Colorado. Fort St. Vrain Nuclear Station Decommissioning Project, Initial Final Survey Report (Volumes I through 5). May 31,1996.
U.S. Nuclear Regulatory Commission (NRC). Termination of Operating Licenses for Nuclear Reactors. Regulatory Guide 1.86. Washington, D.C.; June 1974.
U.S. Nuclear Regulatory Commission. Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities. NUREG-0586; August 1988.
U.S. Nuclear Regulatory Commission. Residual Radioactive Contamination from Decommissioning.
NUREG/CR-5512, Volume 1; October 1992.
4 h/essap plansifsyplan t.002 Fort St. Yr:un Nuclear Station. Sepember 16.1996
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REFERENCES (Continued)
U.S. Nuclear Regulatory Commission. Working Draft Regulatory Guide on Release Criteria for Decommissioning: NRC Staft's Draft for Comment. NUREG-1500; August 1994a.
U.S. Nuclear Regulatory Commission (letter from C.L. Pittiglio), to A.J. Bortz, Long Island Power Authority, subject " Approval of a Modification of Facility Release Criteria for Tritium and Iron-55 i
Surface Contamination at Shoreham Nuclear Power Station, Unit 1," June 7,1994b.
i 15 Fort St. Vrain Nudear Station September 16. Im h:1essap'pians rispiani.co:
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ATTACIIMENT A
\\
s PERFORMANCE PERIOD FY 96 - 97 SPENDING PLAN From To Name of Laboratory:
Aug-96 Oct-96 Oak Ridge Institute for Science and Education RFTA Est. Project Cost Title of Project: #621 96-05
$45,300.00 Fort St. Vrain - Confirmatory 1, Platteville, CO NRC Fin Number ORISE Number TAC Number A9076 1286.02
%f@?WWinhu5h%x W%$%MM%@%R1%@MMNO&GNWilW$$$
COST ELEMENTS Aug 96 Sep-96 Oct-96 Nov-96 Direct Costs
$3,432.00
$3,432.00
$27,455.00
$0.00 Ilndirect Costs-(G&A, DOE Factor)
$1,098.00
$1,098.00
$8,785.00
$0.00 Total Estimate Costs
$4,530.00
$4,530.00
$36,240.00
$0.00 Project Completion 10.00 %
20.00 %
100.00 %
100.00 %
COST ELEMENTS Dec-96 Jan-97 Feb-97 Mar-97 Direct Costs
$0.00
$0.00
$0.00
$0.00 Indirect Costs-(G&A, DOE Factor)
$0.00
$0.00
$0.00
$0.00 Total Estimate Costs
$0.00
$0.00
$0.00
$0.00 Project Completion 100.00 %
100.00 %
100.00 %
100.00 %
COST ELEMENTS Apr-97 May-97 Jun-97 Jul-97 Direct Costs
$0.00
$0.00
$0.00
$0.00 Indirect Costs-(G&A, DOE Factor)
$0.00
$0.00
$0.00
$0.00 Total Estimate Costs
$0.00
$0.00
$0.00
$0.00 Project Completion 100.00 %
100.00 %
100.00 %
100.00 %
GQ$0hlGaM wg wk W kn
%%5%f6& d dQfsyis Wds % d% M 589$$$
ACTIVITY INFORMATION Hours Estimated Cost Site Visit 0.0
$0.00 Document Review 36.0
$5,200.00 Presurvey 30.0
$3,100.00 Travel-Labor 72.0
$7,400.00 Travel-Other Expenses
$9,000.00 Survey Activities 108.0
$10,900.00 Report Preparation 80.0
$8,300.00 Sample Analysis 12.2
$1,400.00, Other 0.0
$0.00 Total 338.2
$45,300.00 226M621.FSV.SP,8/26/96-bu I6