ML20082C080

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Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co
ML20082C080
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 03/16/1995
From:
OAK RIDGE ASSOCIATED UNIVERSITIES
To:
Shared Package
ML20082C064 List:
References
CON-FIN-A-9076 PROC-950316, NUDOCS 9504060149
Download: ML20082C080 (12)


Text

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PROPOSED CONFIRMATORY SURVEY PLAN FOR TIIE REPOWER AREA FORT ST. VRAIN l

PLA'ITEVILLE, COLORADO i

INTRODUCTION Fort St. Vrain (FSV) was a 330 MWe High Temperature Gas-Cooled Reactor (HTGR) owned and operated by Public Service Company (PSC) of Colorado. The site consists of 6995 hectares

_ (2798 acres) owned by PSC, of which approximately one square mile was designated as the l

exclusion area during plant operation. The licensee maintained complete control over this area.

l The basic installation included a reactor building, turbine building, cooling towers, and an electrical switchyard.

FSV was permanently shutdown in August 1989, with the decision to decommission the facility made during December 1989. On November 23,1992, the Nuclear Regulatory Commission (NRC) issued the Order to Authorize Decomrnissioning of Fort St. Vrain and Amendtnent No.

85 to Possession Only License No. DPR-34.8 During the period 1989 to 1991, a radiological characterization of the FSV site was performed. Currently, the FSV decommissioning is

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approximately 70 % complete, with completion expected early in 1996 (excluding the final site i

survey).

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PCS has committed to the Colorado Public Utilities Commission to resume electrical generation l

at FSV through the installation of gas turbines. In order to perform this project, a small section j

of land in the southwest area of the site has been cleared in preparation for the repower effort.

This area is referred to as the repower area, where PSC plans to install natural gas-fired j

combustion turbines and heat recovery boilers to repower the facility.

Prepared by the Environmental Survey and Site Assessment Program, Energy / Environment Systems DI 2'?on, 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 of Energy.

Feet St. Vrsin. March 16, t995 9504060149 950316

{DR ADOCK 05000267 PDR

Duiing plant operations, pre-fabricated steel buildings were located in the repower area. These

. buildings accommodated a construction workshop, a quality control facility that performed radiography, a small warehouse and a flammable storage building.

The repower area does not have a known history of radioactive contamination. This was reaffirmed by the evaluation of the characterization results for the repower area, which did not identify radioactive contamination due to licensed activities. The repower area was therefore classified as an unaffected area. However, elevated levels of Cs-137 were identified in surface soil collected from a localized area outside, but adjacent to the repower area. This area had previously been used for temporary storage of spent iel shipping casks.

SITE DESCRIPTION The FSV facility is located approximately 35 miles north of Denver and 3.5 miles northwest of the town of.Platteville, in Weld County, Colorado. The site consists of 6995 hectares owned by PSC of which approximately one square mile was designated as the exclusion area during plant operation.

The repower survey area is located within the restricted area of the FSV facility on the east side of the turbine building, north of the electrical switchyard (Figure 1).

This location is approximately 12,225 square meters in size. The area has been isolated from the remainder of the restricted area by a chain link fence and locking gates controlled by FSV Security. ~ The boundaries of the repower area include portions of the original restricted area fence on the south -

and east sides and newly erected fence on the west and north sides (Figure 2). The boundary also includes the east, and a portion of the south exterior walls of the evaporative cooler building.

l Fort sc. Vrain - Mmb 16,1995 2

OBJECTIVES The objectives of the confirmatory 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.

RESPONSIBILITY Work described in this survey plan will be performed under the direction of William L. (Jack)

Beck, Program Director and Eric Abelquist, Project Leader 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.

DOCUMENT REVIEW ESSAP has reviewed the licensee's final survey report and radiological survey data.2 Procedures and methods utilized by the licensee were reviewed for adequacy and appropriateness. The data were reviewed for accuracy, completeness and compliance with guidelines.

PROCEDURES Survey activities will be conducted in accordance with the ORISE/ESSAP Survey Procedures and Quality Assurance Manuals. Specific survey procedures applicable to this survey are listed on Pages 7 and 8 of this survey plan. Deviat:ons to the survey plan or procedures will be documented in the site log book.

1 SURVEY PROCEDURES The final survey of the repower area included two general categories of survey units: surfaces and structures, and open land areas. The area was further divided into survey units. The Fod St. Vrain. Mmh 16,1995 3

surfaces and structures survey units within the repower area included the Valve Pit, Miscellaneous Metal Surfaces, Concrete Slab at the Security Fence, Miscellaneous Concrete Surfaces, Evaporative Cooler Building (east and south walls below 2 m), and Evaporative Cooler Building (east and south foundation walls). The open land areas survey units included the general soil area within the repower area, leach field soil area, septic system, and monitoring wells.

4.

Instrumentation and Procedures Comnarison ORISE and Fort St. Vrain (FSV) final survey instrumentation and procedures will be reviewed and compared to ensure consistency between FSV final survey data and ORISE confirmatory survey data..A plan was prepared to facilitate this on-site comparison.3 Items to be evaluated include surface activity measurements using the gas proportional detector, determination of.

specific material and area background radiation levels, detector calibration, exposure rate measurements and smear sampling techniques.

Reference Grid i

ORISE will select specific measurement and sampling locations from each of the survey units.

Because survey maps illustrating the measurement locations were not provided by the licensee, ORISE will depend on the licensee to identify the selected measurement and sampling locations.

Measurement and sampling locations will be referenced to prominent structure features and recorded on survey maps.

Surface Scss Exterior soil surfaces will be scanned for gamma radiation using NaI scintillation detectors. A 25% scan of the soil in the general and leach field soil areas will be performed. Structure surfaces will also be scanned with gas proportional detectors. Particular attention will be given j

to cracks and joints in the surfaces and walls, ledges, ducts, drains, and other locations where material may have accumulated. All detectors will be coupled to ratemeters or ratemeter-scalers Fort St. Wasa - March 16,1995 4

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. with; audible indicators. Locations of elevated direct radiation will be marked for further

. investigation.

Surface Activity Measurements Direct measurements'for total beta activity will be performed on the surfaces and structures within the repower area, using gas proportional detectors, coupled to portable ratemeter-scalers.

Approximately five to ten direct measurements will be performed per survey unit. Additional -

direct measurements will be performed at locations of elevated direct radiation identified by surface scans. Smear samples, for determining removable activity levels, will be collected from each direct measurement location.

Soll Sampling i

A total of ten soil samples will be collected from both the general soil areas and leach field soil areas. Soil samples will also be collected from any exterior locations of elevated direct radiation identified by surface scans.

li Miscellaneous Samoline Miscellaneous samples may be collected from cracks, piping, 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 2

of 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 will be converted to units of disintegrations per minute per 100 square 2

centimeters (dpm/100 cm ). Exposure rate measurements will be measured and reported in units 1

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Fort SL Vrain - March 16,1995 5

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of R/h. ~~ Soil and any' miscellaneous samples will be analyzed by gamma spectrometry and/or

~ alpha spectrometry. The radionuclides ofinterest are Co-60 and Cs-137; however, spectra will be reviewed for other identifiable photopeaks. Gamma spectrometry data will be reported in pCi/g. The data generated will be compared with the licensee's documentation and NRC 1

guidelines established for release to unrestricted use. Results will be presented in a report and provided to the NRC.

GUIDELINES The primary contaminants of concern 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:4 Total Activity 2

2 5,000 dpm/100 cm total, averaged over a 1 m area 2

2 15,000 dpm/100 cm, total, maximum in a 100 cm area 4

Removable Activity 2

1,000 dpm/100 cm i

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-1500.5.6 The exposure rates guideline, measured at 1 m above the surface, is 5 pR/h above background.7 Fod 5t Vrnin - March 16,1995 6

+

c TENTATIVE SCHEDULE Measurement and Sampling March 21 - 22,1995 Sample Analysis April 1995 Draft Report May 1995 LIST OF CURRENT PROCEDURES

' Applicable procedures from the ORISE ESSAP Survey Procedures Manual (Revision 8; December 31,1993) include:

Section 5.0 Instrument Calibration and Operational Check-Out 5.1 General Information 5.2 Electronic Calibration of Ratemeters 5.3 Gamma Scintillation Detector Check-Out and Cross-Calibration 5.5 GM Detector Calibration and Check-Out 5.6 Proportional Detector Calibration and Check-Out 5.7 Pressurized Ionization Chamber Calibration and Check-Out 5.13 Field Measuring Tape Calibration Section 6.0 Site Preparation 6.2 Reference Grid System i

l Section 7.0 Scanning and Measurement Techniques 7.1 Surface Scanning 7.4 Beta Radiation Measurement 7.5 Gamma Radiation (Exposure Rate) Measurement Section 8.0 Sampling Procedure

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8.7 Determination of Removable Activity re se vr.a - u.,<6 i6. i995 7

8.8 Miscellaneous Sampling 8.9 Sample Identification and I2beling Section 9.0 Integrated Survey Procedures 9.2 General Survey Approaches and Strategies Section 10.0 Health and Safety Control of Cross Contamination 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 1

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 Section 11 Records Handling and Storage l

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FIGURE 2: Repowec Areo Overview Xxxx Fort SL Vres. himh 16,1995

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REFERENCES 1.

Public Service Company of Colorado," Final Survey Report for Release of Repower Area," March 2,1995.

2.

Oak Ridge Institute for Science and Education, letter from E. W. Abelquist to D.

Fauver, NRC/NMSS, " Document Review - Final Survey Report for Release of the Repower Area, Fort St. Vrain, Platteville, Colorado," March 13, 1995.

3.

Oak Ridge Institute for Science and Education, letter from E. W. Abelquist to D.

- Fauver, NRC/NMSS, " Instrument Comparison Plan for ORISE and Fort St. Vrain Survey Instrumentation (Docket No. 50-267)," March 15,1995.

4.

U.S. Nuclear Regulatory Commission, " Termination of Oyz. ting Licenses for Nuclear

- Reactors," Regulatory Guide 1.86, Washington, D.C., June 1974.

5.

NUREG/CR-5512, " Residual Radioactive Contamination from Decommissioning,"

Volume 1, October 1992.

6.

NUREG-1500, " Working Draft Regulatory Guide on Release Criteria for Decommissioning: NRC Staff's Draft for Comment," August 1994.

7.

NUREG-0586, " Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities," August 1988.

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PERFORMANCE PERIOD SPENDING PLAN From To Name of Laboratory:

Mar-95 Apr-95 Oak Ridge Institute for Science and Education RFTA Est. Project Cost Title of Project: #287 95 17

$41,900.00 i

FORT ST. VRAIN NRC Fin Number ORISE Number TAC Number.

A9076 1286.02 lR.%%%Wm

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W m i r ~ V % *l s N + k ' % h%d%)

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COST ELEMENTS Oct 94 Nov 94 Dec 94 Jan 95 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 0.00 %

0.00 %

0.00 %

0.00 %

COST ELEMENTS Feb-95 Mar 95 Apr-95 May 95 Direct Costs

$0.00

$25,000.00

$5,500.00

$0.00 Indirect Costs-(G&A, DOE Factor)

$0.00

$9,400.00

$2,000.00

$0.00 Total Estimate Costs

$0.00

$34,400.00

$7,500.00

$0.00 Project Completion 0.00 %

82.10%

100.00 %

100.00%

COST ELEMENTS Jun 95 Jul-95 Aug-95 Sep 95 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%

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ACTIVITY INFORMATION Hours Estimated Cost Site Visit 0.0

$0.00 Document Review 8.0

$1,800.00 Presurvey 18.0

$4,100.00 Travel Labor 42.0

$9,600.00 Travel Other Expenses

$3,900.00 Survey Activities 40.0

$9,200.00 Report Preparation 48.0

$11,400.00 Sample Analysis

$1,900.00 Other 0.0

$0.00 Total 156.0

$41,900.00 3 95 287 FT.ST.VRAIN SP, 3/16,95-smn

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