ML20071L874

Forwards Confirmatory Survey Plan for Radwaste Building & Suppression Pool for Review & Comment

ML20071L874
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	07/29/1994
From:	Vitkus T OAK RIDGE ASSOCIATED UNIVERSITIES
To:	Fauver D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9408030307
Download: ML20071L874 (18)

Text

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. ORISE OAK frl(Ksf IN5f tf u1E FOR SCit'NCF AND F DUC AtlON t I #f $M J V /f f JVl4 Jf 4MI N f SY te t f M% Di v f 5 tral 1 July 29,1994 hir. David Fauver

• Division of Low-Level Waste hianagement - NhtSS U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, h1D 20852 SUllj ECT: CONFIRMATORY SURVEY PLAN FOR Tile RADWASTE IlUILDING AND SUPPRESSION POOL, SilOREllAM NUCLEAR POWER STATION, IIROOKil AVEN, NEW YORK [ DOCKET FILE NO. 50-322]

Dear Mr. Fauver:

Enclosed is the subject document for your revi::w and comment. To enable us to meet the proposed August 22,1994 survey start date, we will need to receive the Survey Plan Approval Form by August 17, 1994. Please do not hesitate to contact me at (615) 576-5073 should you have any questions, i

Sincerely, s

//hh 4_ -

Timothy J. Vitkus Environmental Project Leader ,

Environmental Survey and  !

Site Assessment Program t I

TJV:dac Enclosure cc: T. h10, NRC/Nh1SS/TWFN/8A33 D. Tiktinsky, NRC/NMSS/TWEN/8A23 L Pattiglio, NRC/NMSS/7F27 l R. Nimitz, NRC/ Region 1  !

PMDA, NRC/NMSS/TWEN/8A23 J. Ileck, ORISF/ESSAP File /258 0 c,0 7J LsM c ,, i 9400030307 94o729 PDR P ADDCK 05000322 PDR P O BOX 117, OAK RIDGE, TENNESSEE 378310117 l Monoped and operated tn Ook Ridge Anociated UnWeroties for the U 5. Deparwent of Energy j J

CONFIRSIATORY SURVEY PLAN FOR Tile RADWASTE IlUILDING AND SUPPRESSION POOL SIIOREllANI NUCLEAR POWER STATION llROOKIIAVEN, NEW YORK ,

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INTRODUCTION l

r The 1.ong 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 l l

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 l

intermittently until January 1989, at which time power generating operations were terminated.

The total reactor operating history was equivalent to 2.03 effective full power days of fuel j ex posure. 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 fuel .

pool in August 1989.

f 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 l quantities of tritium, carbon-14, nickel-59, manganese-54, zine-65, and europium-152.'  !

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The Long Island Power Authority (LIPA) was established to decommission the facility and i release the site for unrestricted use. The LIPA Decommissioning Plan was approved for

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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 Gnal 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.

It is the policy of the NRC to perform confirmatory surveys of facilities that have undergone decommissiming and have requested NRC license termination. The NRC Headquarters' Division of low-Level Waste Management and Decommissioning has requested that the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conduct con 6rmatory 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.23 SITE DESCRIPTION The SNPS is located in the Town of Brookhaven, New York, on the north shore of Long Island, approximately 80 km (50 mi) east of La Guardia Airport and the confluence of the East River and lmng Island Sound (Figure 1). The SNPS is located on a 32.4 ha (80 ac) portion of a larger 202 ha parcel of land 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 es 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 Radaante Itmidmg & hppicumn Pmd July 29, AW4 2 h heap plawend*matesrudwaste WI

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.

LIPA has classified plant systems, building surfaces, and outside areas into two categories which 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 known contamination, or a system which circulated, stored or processed radioactive materials such that they could become contaminated, or experience, neutron activation, or where records indicated spills or other occurrences may have resu' ext in 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. i l

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l OIUECTIVES The objectives of this confirmatory survey are to provide independent document reviews, review and field observations of the LIPA procedures for embedde.1 piping surveys, and radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and termination survey results.

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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 ESS AP. The cognizant site supervisor has aw .. n a.im,a sorr - ,.., u . u 3. m 3  %.psew i. - ,w... mi

l 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.

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. Additional information regarding selection of confirmatory survey units and the implementation of this plan may be found in the general site confirmatory survey plan."

SURVEY PROCEDURES Reference Svsiem The reference systems established by LIPA will be used by ESS AP 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). j i

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Surface Sc:tn3 Surface scans for alpha, beta, and gamma activity, will be performed over 100% of Door, and lower wall surfaces and up to 50% of equipment surfaces, within each structural survey unit.

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

Entface Activitv Meithnremtt115 For each survey unit, ESSAP will perform a minimum of thirty direct measurements for total beta smface activity. ESSAP will also perform 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 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.

Exposure Ratellrai!!remen.13 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).

llackground exposure rates were previously determined during the confirmatory survey of the Turbine 13uilding.3  ;

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E111beddnLPiping Con 6rmation of the radiological status of embedded piping will be accomplished primarily through data and records review including instrument calibrations and quality control factors.

In addition, random independent measurements will be made at accessible openings and traps within the Radwaste 13uilding.

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, LIPA intends to provide access points into the system components listed in Table 2. Ileta and l

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 Nal detectors coupled to ratemeters or ratemeter-scalers.

Q11tGrnistory Atlables Smear or miscellaneous samples, collected by LIPA, may be requested for confirmatory analyses.

SAMPLE ANALYSIS AND DATA INTERPRETATION l

Samples and data will be returned to ESSAP's Oak Ridge laboratory for analysis and interpretation. Smears will 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 pR/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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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 a survey unit, surface activities as calculated by LIPA are greater than or equal to those determined by ESSAP, i.e., H,: uPA 2 F emap. 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:3 Fura < FimP. The test statistic, t, will be calculated using the following equation:

Xe ~X L (ng-1)S2 (y _3)S 2 ,ygy 3

) Hg+Hz ~2 \

nH gg ,

where:

$ Is the LIPA surface activity or soil concentration mean for a survey unit Xr 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 nn is the number of ESSAP direct measurement or soil concentration data points So, Se Are the standard deviations.

The calctilated i is then compared to the critical value of Student's I-distribution (one-tailed) for ,

1 the appropriate degrees of freedom at the 95% confidence level (0.05 level of significance). If the H o: FuPA k FimP is rejected, then ESSAP will evaluate additional options and alternatives and confer with the NRC as to the recommended approach.

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GUIDELINES The applicable Regulatory Guide 1,86 guidelines are those for beta-gamma emitters and the alpha contamination guidelines are those for uranium and associated decay products. The beta-gamma guidelines are:

Total Activity 5,000 6-7 dpm/100 cm2 , averaged over Im 2 15,000 B-y dpm/100 cm2 , maximum in a 100 cm2 area Rgmovable Activity 1,000 B-y dpm/100 cm 2 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 cm 2 The exposure rate guidelin: currently being used by the NRC is 5 pR/hr above background, measured at I m.5 The site specific NRC criterion for soils is 8 pCi/g average concentration of Shoreham produced gamma-emitting radionuclides.

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4 Tentative Confirmatory Schedule Phase III: Radwaste Building Surveys Document Review August 1994 Confirmatory Survey August 22 through September 26,1994 Sample Analysis September 1994 Draft Report October 28,1994 I lST OF CURRENT PROCEDURES TO llE USED IN TIIE SURVEY Applicable procedures from ORISE ESSAP Survey Procedures hianual (Revision 8; December 31,1993) include:

Section 5.0 Instrument Calibration and Operational Check-Out 5.1 General Information 5.2 Electronie 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 Afeasuring Tape Calibration Section 7.0 Scanning and Measurement Techniques 7.1 Surface Scanning 7.2 Alpha Radiation Measurement 7.3 Beta Radiation Measurement 7.4 Gamma Radiation (Exposure Rate) Measurement l

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TAllLE I SU5131AIW OF Tile SNPS FACILITIES AND ASSOCIATED SURVEY UNITS mI No. of Affected No. of Unaffected Total No. of Descr t.ip ion Sur vey Units Survey Units Survey Units Turbine lluilding Structures 10 104 114 Reactor Iluilding Structures 110 0 110 Rad Waste Iluilding Structures 77 0 77 Drywell 22 0 22 Suppression Pool 13 0 13 Plant Systems 38 44 82 Site Grounds 0 10 10 Site lixteriors 0 32 32 Total 270 190 460

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             .                                                     TAllLE 2 RADWASTE BUILDING AND SUPPRESSION POOL SURVEY UNITS SELECTED FOR CONFIRMATORY SURVEY Survey                                                 Affected (A)/           Structure /

Survey Unit Name Unit / Component Unaffected (U) System RadWaste Building RWOl3 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 RWO72 Off Gas Desiccant Dryers Area A Structure SUO12/ Valves Reactor Building Hi Pressure A System Coolant E410lV3049 and Injection System E4101V3050 SUO15/Non Reactor Water Clean up A System Regenerative Heat Exchanger IG33-E-014 SUO14/ Valve RadWaste Building Drain A System 1G11-AOV-38 Piping System SU-14/ Flat Bed RadWaste Building Drain A System Floor Drain Filter Piping System 1G1l FL-012 listwenw buikimg & Suppeemamen 1%I July 29,1994 }4 h. Weap\plansireds amteiradwnste Axil

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           .                                         TABLE 2 (Continued)

RADWASTE BUILDING (Continued) AND SUPPRESSION POOL SURVEY UNITS SELECTED FOR CONFIRMATORY SURVEY , i Survey AUected (A)/ .Stmetum/  ! Survey Unit Name Unit / Component Unaffected (U) System SUO14/RadWaste RadWaste Building Drain Piping A System [ Equipment and System Floor Drain Survey ' Sump i I G11-Tk-054 SUO43/ Tank E Condensate Demineralizes A System l IN52-DE-002E  : Reactor Iluilding , 3 SP004 Suppression Pool - NW A Structure Quadrant SP005 Suppression Pool Area Inside A Structure Vessel Pedestal , l l l l l l na.. n .w.n. A sw - ru . u n9.iwe 15 6w r1ri s.u. uw. un

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     .                                             REFERENCFS

1. Long 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. 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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APPENDIX A CONFIRS1ATORY SURVEY PLAN FOR TIIE RADWASTE IlUILDING AND SUPPRESSION POOL SilOREllAS1 NUCLEAR POWER STATION llROOKil AVEN, NEW YORK RadWaste Building and Activity Suppression Pool Plan Preparation Total Cost: $13,700 Document Review  % of 1% Survey Preparation Total Cost' 8% On-Site Actisities Total Cost: $98,500 Travel 27 % Surface Scans g or 17 % Direct Measurements Total Cost

• 23 %

Sampling <1% Saniple Anal3 sis Total Cost: $1,800 Smear Analysis  % of 1% Total Cost

• Report Preparation Total Cost: $32,000 Data Tabulation 8%

lliustration  % of 7% Draft and Final Report Text Preparation & 7% Review Total Cost Estimate $146,000

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

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