ML20072P403

Revised, Confirmatory Survey Plan for Radwaste Bldg & Suppression Pool for Plant

ML20072P403
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	08/17/1994
From:	OAK RIDGE ASSOCIATED UNIVERSITIES
To:	NRC
Shared Package
ML20072P161	List: ML20072P159 ML20072P403
References
CON-FIN-A-9076 NUDOCS 9409070231
Download: ML20072P403 (18)

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CONFIRMATORY SURVEY PLAN t FOR TIIE RADWASTE BUILDING AND SUPPRESSION POOL SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK INTRODUCTION  !

The Long Island Lighting Company (LILCO) constructed a boiling water reactor known as the Shoreham Nuclear Power Station (SNPS). The plant was designed to provide a gross electrical  ;

output of 849 Megawatts and achieved initial criticality in February 1985. The U.S. Nuclear Regulatory Commission (NRC) License No. NPF-82 (NRC Docket File No. 50-322) issued for ,

the facility allowed reactor operations at power levels not to exceed 5% of full power. Low '

power testing in accordance with the license then commenced in July 1985 and continued intermittently until January 1989, at which time power generating operations were terminated.

The total reactor operating history was equivalent to 2.03 effective full powel days of fuel exposure. The irradiated fuel, which was a standard low enrichment (2 to 3% uranium-235). +

uranium fuel, was subsequently removed from the reactor vessel and placed into the spent fue1 poolin August 1989.

Various reactor components, piping systems, and other equipment became radiologically contaminated as a result of reactor operation. The primary contaminants which have been identified during characterization studies include iron-55, cobalt-60, nickel-63, and smaller i

quantities of tritium, carbon-14, nickel-59, manganese-54, zine-65, and europium-152.8 The Long Island Power Authority (LIPA) was established to decommission the facility and release the site for unrestricted use. The LIPA Decommissioning Plan was approved for  ;

implementation by the NRC in June 1992 and will include decontamination or removal of Prepared by the Environmental Survey and Site Assessment Program, Energy / Environment Systems 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 of Energy.

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contaminated portions of the reactor and other plant systems and equipment. A major consideration of the decommissioning plan is to maintain the integrity when possible, of plant structures and systems. The decommissioning and termination surveys are being conducted in phases, terminating in the removal of the spent fuel from the site and completion of the final surveys in October 1994. Phase 1 included the termination survey of the internal components of the main turbine, the Turbine Building, site grounds, and exterior site structures. The current phases, Phase 2 and 3, include the Reactor Building Suppression Pool and the Radwaste Building.

The NRC Headquarters' Division of Waste Management has requested that the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conduct conGrmatory radiological surveys of the SNPS decommissioning-project. ESSAP has completed the confirmatory survey of the Turbine Internal components, the Turbine Building, site grounds, and exterior site structures. The results of which are the subject of separate final and draft reports.2.3 SITE DESCRIPTION The SNPS is located in the Town of Brookhaven, New York on 'he north shore of Ieng Island, approximately 80 km (50 mi) east of La Guardia Airport and the confluence of the East River and Long Island Sound (Figure 1). The SNPS is located on a 32.4 ha (80 ac) portion of a larger 202 ha parcel ofland owned by the LILCO. The site is bounded on the north by Long Island Sound, on the east by the Wading River Marshland, on the west by other LILCO property, and on the south by Route 25A. A cyclone fence encloses the 8 ha site secured area. Within this boundary are the buildings and grounds classified as the Restricted Area, also known as the power block, where radiological controls were necessary (Figure 2). Each of the buildings that which have been or will be addressed during the confirmatory process are located here and are shown on Figure 2 as the Turbine Building, the Reactor Building, and the Rad Waste Building.

Construction of these buildings is predominately structural steel and concrete. Total floor space 2

of the three buildings is approximately 45,600 m (490,000 ft). The building interiors contain a multitude of process specific and environmental control equipment and piping.

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LIPA has classified plant systems, building surfaces, and outside areas into two categories which J are based on the potential for residual contamination. The two area categories referred to as affected or unaffected are defined as follows: affected areas are areas of the SNPS that are potentially contaminated or have knoven contamination, or a system which circulated, stored or I processed radioactive materials such that they could become contaminated, or experience,

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neutron activation, or where records indicated spills or other occurrences may have resulted in I contamination; unaffected areas are those portions of the SNPS that are not expected to contain  ;

residual radioactivity. Area classification was determined by radiological use history, environmental monitoring activities, and the results of a previous characterization survey.

Affected and unaffected areas are further subdivided into survey units (SU). Survey units are categorized as structures (floors, walls, ceilings, and exterior surfaces of piping and equipment),

plant systems (equipment and piping internals), and outdoor areas (grounds and building exteriors). In addition, affected survey units also have sub-classifications as suspect or non-suspect, and may also be classified as alpha affected if involved with fuel handling or storage.

Table 1 provides a summary of the facilities addressed by this plan and the number and type of survey units associated with each.

OBJECTIVES The objectives of this confirmatory survey are to provide independent document reviews, review and field observations of the LIPA procedures for embedded piping surveys, and radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensce's procedures and termination survey results.

RESPONSIBILITY Work described in this survey plan will be performed under the direction of Jack Beck, Acting Program Director and Tim Vitkus, Project Leader of ESSAP. The cognizant site supervisor has the authority to make appropriate changes to the survey with the approval of the NRC site representative. Deviations to this survey plan will be documented in the site log book.

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DOCUMENT REVIEW AND LIPA PROCEDURE SURVEILLANCE ESSAP will review LIPA's release records for those survey units selected for confirmatory survey. Review of additional release records will be dependent upon findings as the surveys progress. Documents will be reviewed for adequacy, accuracy, completeness, and consistency.

Data will be reviewed for appropriateness of calculations and interpretations relative to the guidelines.

PROCEDURES A survey team from ESSAP will perform independent visual inspections, measurements, and sampling of survey units associated with the Radwaste Building and the Reactor Building Suppression Pool. Table 2 lists the survey units selected for confirmatory surveys. Of the total, ,

9 were selected randomly and 5 were selected by the NRC site representative. Field survey activities will be conducted in accordance with the applicable sections of the ESSAP Survey Procedures and Quality Assurance Manuals. The following procedures apply to survey units >

selected for independent confirmatory surveys. Additionalinformation regarding selection of confirmatory survey units and the implementation of this plan may be found in the general site confirmatory survey plan.4 SURVEY PROCEDURES Reference Systeql The reference systems established by LIPA will be used by ESSAP for referencing measurement and sampling locations. The grid size or reference interval established by LIPA for a given survey unit will be dependent upon the classification survey unit (affected vs. unaffected) and surface (floor, lower wall, upper wall, ceiling, or equipment).

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l Surface Scans Surface scans for alpha, beta, and gamma activity, will be performed over 100% of floor, and lower wall surfaces and up to 50% of equipment surfaces, within each structural survey unit.

Additional scans will be performed over portions of upper wall, ceiling, and system surfaces as well as locations, such as drains, where material may have settled or accumulated. Locations of elevated direct radiation detected by scans will be marked for further investigation. Scans will be performed using gas proportional, GM, ZnS, and/or NaI detectors coupled to ratemeters or ratemeter-scalers with audible indicators.

Surface Activity Measurements For each survey unit, ESSAP will perform a minimum of thirty direct measurements for total beta surface activity. ESSAP will also perform additional direct measurements at locations of elevated direct radiatio:t detected by surface scans. At measurement locations, where the average NRC surface contamination guideline is exceeded, the size of the contaminated area and the average activity in the contiguous 1 m2 area will also be determined. Total alpha surface activity measurements will also be performed at each direct measurement location when a selected survey unit is classified as alpha affected or if alpha contamination is identified by surface scans. 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.

Exoosure Rate Measurements Exposure rate measurements will be performed within each survey unit, excluding system interiors, at the approximate location where LIPA performed measurements. All exposure rates will be measured at 1 m above surfaces using a pressurized ionization chamber (PIC).

Background exposure rates were previously determined during the confirmatory survey of the Turbine Building.3 Iw- te IWhs & Surprea.ma Pool- Aus=t 17. Im 5 e w.gv w w -.* w - .mi

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Embedded Pipine A minimum of ten sections of embedded piping will be selected, based on recommendations of the NRC site representative, where access may be gained through drains, traps, or openings where pipe sections have been removed. ESSAF will perform surface scans and direct measurements for beta activity over a length of eacio, elected pipe run, nominally 4 m in either direction of the access point. Direct measurements will be made at any locations of elevated direct radiation detected by scans and at 10 additional locations. The surface activity data collected will then be compared to the LIPA generated data for the corresponding section of each pipe section and the NRC surface activity guidelines.

Additional confirmatory activities for embedded piping will include an on-site review of the LIPA embedded piping termination survey program as well as the LIPA data and records for each of the above selected embedded piping subunits. For each subunit, the Termination Survey Design (LIPA Procedure SP Number 67X001.10) will be compared to the field records and evaluated for appropriateness and consistent implementation. The control and calibration records for the specific detector / instrument combination used during termination and QC survey data acquisitions for each subunit will be compared with, and evaluated against, criteria established in the LIPA procedures. These instrumentation procedures include the following:

1. Control of Health Physics Instrumentation (SP Number 61X080.01)

2. Chi-Square Test and Control Chart Review (SP Number 61X081.01)

3. Detector Calibration (SP Number 66X020.11)

4. Instrument Calibration (SP Number 66X022.02)

Instrument / detector combinations will be evaluated against each required parameter including calibration, operational checkout, etc.

The surface activity data generated at 10 to 20 measurement locations with these instruments will then be tracked through the LIPA data management system, including the QC comparisons. The applicable LIPA procedures that will be reviewed and records compared with include:

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1. Data Receipt and Management (SP Number 67X001.05)

2. Termination Survey Data Processing (SP Number 67X001.11)

Specific attention will be given to the validation of computer generated data by performing manual calculation of critical levels and surface activity.

LIPA will then be requested to resurvey portions of the selected embedded piping subunits and the results compared with the original survcy data.

Systems LIPA intends to provide access points into the system components listed in Table 2. Beta and gamma surface scans will then be performed within the accessible portions of the system, followed by 5 to 30 direct measurements and smear samples (dependent upon component size).

Scans and direct measurements will be performed using gas proportional, GM, ZnS, and/or NaI detectors coupled to ratemeters or ratemeter-scalers.

Confirmatory Analyses Smear or miscellaneous samples, collected by LIPA, may be requested for confirmatory analyses.

SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data will be retumed to ESSAP's Oak Ridge laboratory for analysis and interpretation. Smears wi.'l be analyzed for gross alpha and gross beta activity using a low background proportional counter. Smear and direct measurement data will be converted to units of dpm/100 cm2 and exposure rates to R/h. Data will then be compared to the LIPA results and NRC guidelines. Survey results will be presented in a draft report at the completion of this confirmatory phase and submitted to the NRC for review and comment.

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1 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 LIPA survey data is not biased low compared to ORISE. The null hypothesis will be that in s survey unit, surface activities as calculated by LIPA are greater than or equal to those determined by ESSAP, i.e., H,: MuPA b MESSAP. 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.,

H:4 FuPA < FosSAp. The test statistic, t, will be calculated using the following equation:

Xz ~X t .

t= *

(n,-1)Sj + (nt-1)Sj 'n, + nt '

) n, + ng -2 n,nz ,

where:

5 Is the LIPA surface activity or soil concentration mean for a survey unit Tz Is the ESSAP surface activity or soil concentration mean for the same survey unit no Is the number of LIPA direct measurement or soil concentration data points na Is the number of ESSAP direct measurement or soil concentration data points St, Sn Are the standard deviations.

4 The calculated t 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 H : FuPA h MESSAP is rejected, then ESSAP will evaluate additional options and alternatives and confer with the NRC as to the recommended approach.

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l GUIDFJ,INES 1

The applicable Regulatory Guide 1.86 guidelines are those for beta-gamma emitters and the l

alpha contamination guidelines are those for uranium and associated decay products. The i beta-gamma guidelines are:

l Total Activity 5,000 B-y dpm/100 cm2 , averaged over Im2 15,000 6-7 dpm/100 cm2 , maximum in a 100 cm2 area Removable Activity 1,000 B-y dpm/100 cm2 The alpha guidelines are:

Total Activity 5,000 a dpm/100 cm 2, averaged over 1 m 2 15,000 a dpm/100 cm2 , maximum in a 100 cm2 area Removable Activity 1,000 a dpm/100 cm2 The NRC has approved site-specific allowable surface contamination guidelines for H-3 and Fe-55, particularly in activated concrete and steel.5 These guidelines are:

Total Activily 200,000 dpm/100 cm2, averaged over 1 m 2 600,000 dpm/100 cm2 , maximum in a 100 cm2 area Removable Activity 1,000 dpm/100 cm 2 Ral-aste IMkimg & Suppreenka Pool- Auguat 17.1WI 9 m rww--w mi 1

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l The exposure rate guideline currently being used by the NRC is 5 R/hr above background, measured at I m.6 The site specific NRC criterion for soils is 8 pCi/g average concentration l l

of Shoreham produced gamma-emitting radionuclides.

Tentative Confirmatory Schedule Phase III: Radwaste Building Surveys Document Review August 1994 .

Confirmatory Survey . August 22 through August 26,1994 i

Sample Analysis September 1994 Draft Report October 28,1994 LIST OF CURRENT PROCEDURES TO BE USED IN TIIE SURVEY Applicable procedures from ORISE ESSAP Survey Procedures Manual (Revision 8; December 31,1993) include:

Section 5.0 Instrument Calibration and Operational Check-Out General Information 5.1 5.2 Electronic Calibration of Ratemeters 5.3 Gamma Scintillation Detector Check-Out and Cross Calibration 5.4 Alpha Scintillation Detector Calibration and Check-Out 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 5.8 Floor Monitor Check-Out 5.10 Field Measuring Tape Calibration .

Section 7.0 Scanning and Measurement Techniques 7.1 Surface Scanning 7.2 Alpha Radiation Measurement R Jwaste BuMmg & Suppressionl'ool- August 17, im 10 hwww--w-=.ml

7.3 Beta Radiation Measurement 7.4 Gamma Radiation (Exposure Rate) Measurement Section 8.0 Sampling Procedures 8.7 Determination of Removable Activity 8.9 Sample Identification and Labeling Section 9.0 Integrated Survey Procedures 9.2 General Survey Approaches and Strategies Section 10.0 Health and Safety and Control of Cross Contamination Section 11.0 Quality Assurance and Quality Control l

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TABLE 1 l

SUMMARY

OF TIIE SNPS FACILITIES .AND ASSOCIATED SURVEY UNITS i l

. No of Affected No. of Unaffected Total No. of Desen.p tion Survey Units Survey Units Survey Units Turbine Building Structures 10 104 114 Reactor Building Structures 110 0 110 Rad Waste Building Structures 77 0 77 Drywell 22 0 22 Suppression Pool 13 0 13 Plant Systems 38 44 82 Site Grounds 0 10 10 Site Exteriors 0 32 32 Total 270 190 460 I

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1 TABLE 2 RADWASTE BUILDING 1 AND SUPPRESSION POOL SURVEY UNITS I SELECTED FOR CONFIRMATORY SURVEY I

Survey Anected (A)/ Stmetum/

Survey Unit Name Unit / Component Unaffected (U) System RadWaste Building RW013 RadWaste - 15' North Hallway A Structure RW017 Cation / Anion Reger and Resin A Structure Storage Tanks Area RWO23 (Cubicle A) Liner Fill Stations /BW Storage A Structure Rooms RWO40 Waste Evaporator / Regen. Evap. A Structure Distil. Room RWO42 RadWaste - 37' North Hallway A Structure  ;

RWO69 "B" RW O/G HEPA after Filter A Structure Area I

RWO72 Off Gas Desiccant Dryers Area A Structure SUO14/ Tank RadWaste Building Drain A System IG11-Tk-66 Piping System SUO14/ Flat Bed RadWaste Building Drain A System Floor Drain Filter Piping System 1G11-FL-012 SUO14/ Waste RadWaste A System Collector Tank Equipment / Components 1Gil Tk-10A SUO14/RadWaste RadWaste Building Drain Piping A System Equipment Drain System Sump IGil-Tk-071 SUO43/ Tank E Condensate Demineralizes A System IN52-DE-002E Ral asu 11uMing & Suppresion Puol. August 17, im 15 m ortri- w. w-- mi

TABLE 2 (Continued) l RADWASTE BUILDING (Continued) l AND SUPPRESSION POOL SURVEY UNITS SELECTED FOR CONFIRMATORY SURVEY Survey Affected (A)/ Structure /

umy nit Name Unit / Component Unaffected (U) System Reactor Building SP004 Suppression Pool - NW A Structure Quadrant SP005 Suppression Pool Area Inside A Structure Vessel Pedestal i

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REFERENCES

1. Ieng Island Lighting Company, "Shoreham Nuclear Power Station Site Characterization Program Final Report," May 1990.

2. T. J. Vitkus, ORISE, " Confirmatory Survey of the Turbine Internal Components, Shoreham Nuclear Power Station, Brookhaven, New York," July 1993.

3. T. J. Vitkus, ORISE, Draft Report " Confirmatory Survey of the Turbine Building, Site Grounds, and Site Exteriors, Shoreham Nuclear Power Station, Brookhaven, New York,"

February 1994. ,

4. Letter from T. J. Vitkus, ORISE to D. Fauver, U.S. Nuclear Regulatory Commission,

" Final Confirmatory Survey Plan from the Shoreham Nuclear Power Station, Brookhaven, New York [ Docket File No. 50-322]," November 4,1993.

5. Letter from C.L. Pittiglio, U.S. Nuclear Regulatory Commission, to A.J. Bortz, Long Island Power Authority, subject " Approval of a Modification of Facility Release Criteria for Tritium and Iron-55 Surface Contamination at Shoreham Nuclear Power Station, Unit 1", June 7,1994.

6. U.S. Nuclear Regulatory Commission, " Guidance and Discussion of Requirements for an Application to Terminate a Non-Power Reactor Facility Operating License," Revision 1, September 1984.

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I APPENDIX A l CONFIRMATORY SURVEY PLAN  ;

FOR TIIE RADWASTE BUILDING AND SUPPRESSION POOL SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK i RadWaste Building and l Activity g, ppy,,,,,, p,,, j i

Plan Preparation Total Cost: $13,700 Document Review  % of 1%

Survey Preparation Total Cost

• 8% f On-Site Activities Total Cost: $98,500 l Travel 27 % i Surface Scans g or 17 % [

Direct Measurements Total Cost

• 23 % i i

Sampling <1% i Sample Analysis Total Cost: $1, goo  !

i Smear Analysis  % of 1% {

Total Cost

• l>

Repo 1 Preparation Total Cost: $32,000 W

Data Tabulation 8% f Illustration  % of 7% l' Total Cost

• Draft and Final Report Text Preparation & 7% l Review  !

Total Cost Estimate $146,000 )

" Percentages are provided for estimating purposes only and may not be indicative of actual project cost distributions. l l

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